[Federal Register Volume 72, Number 104 (Thursday, May 31, 2007)]
[Notices]
[Pages 30399-30402]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-10470]


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NUCLEAR REGULATORY COMMISSION

[HLWRS-ISG-03]


Preclosure Safety Analysis--Dose Performance Objectives and 
Radiation Protection Program; Availability of Final Interim Staff 
Guidance Document

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of availability.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is announcing the 
availability of the final interim staff guidance (ISG) document, 
``HLWRS-ISG-03 Preclosure Safety Analysis--Dose Performance Objectives 
and Radiation Protection Program,'' and NRC responses to the public 
comments received on this document. The ISG clarifies or refines 
guidance provided in the Yucca Mountain Review Plan (YMRP) (NUREG-1804, 
Revision 2, July 2003). The YMRP provides guidance to NRC staff for 
evaluating a potential license application for a high-level radioactive 
waste geologic repository constructed or operated at Yucca Mountain, 
Nevada.

ADDRESSES: HLWRS-ISG-03 is available electronically at NRC's Electronic 
Reading Room, at http://www.nrc.gov/reading-rm.html. From this site, a 
member of the public can access NRC's Agencywide Documents Access and 
Management System (ADAMS), which provides text and image files of NRC's 
public documents. The ADAMS accession number for ISG-03 is ML071240112. 
If an individual does not have access to ADAMS, or if there are 
problems in accessing the documents located in ADAMS, contact the NRC 
Public Document Room (PDR) Reference staff at 1-800-397-4209, or (301) 
415-4737, or (by e-mail), at pdr@nrc.gov.
    This document may also be viewed electronically on the public 
computers located at NRC's PDR, Mail Stop: O-1F21, One White Flint 
North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction 
contractor will copy documents, for a fee.
    NRC Responses to Public Comments on Hlwrs-ISG-03: In preparing 
final ``HLWRS-ISG-03 Preclosure Safety Analysis--Dose Performance 
Objectives and Radiation Protection Program,'' ADAMS ML071240112, the 
NRC staff reviewed and considered 18 comments, including one editorial 
comment, received from two organizations during the public comment 
period. Three comments were related to the ISG process; and the 
remaining comments included recommendations on specific clarifying 
changes to the ISG. The three comments on the ISG process were 
consistent with the comments made earlier on HLWRS-ISG-01, and were 
addressed in responses to public comments on HLWRS-ISG-01 [see 71 FR 
57582, Comments 13 (a) and (b)].
    The following discussion indicates how the comments were addressed, 
and the changes, if any, made to ISG-03 as a result of the comments. 
Line numbers in the following comments refer to draft

[[Page 30400]]

HLWRS-ISG-03, ADAMS ML070230090, which was made available for public 
comment on February 20, 2007 (72 FR 7778).
    Comment 1. One commenter recommended that the reference to 10 CFR 
63.111 on line 14 be revised to 10 CFR 63.111(a), so that the reference 
was explicit to Category 1 event sequences. The commenter stated that 
the entire 10 CFR 63.111 does not apply to preclosure.
    Response. NRC disagrees that the entire 10 CFR 63.111 does not 
apply to preclosure. This section of 10 CFR Part 63 provides the 
regulatory requirements for performance objectives for the geologic 
repository operations area (GROA) through permanent closure, which is 
the preclosure period. However, NRC agrees that, in the context of the 
sentence (ISG lines 12-14), the reference is to 10 CFR 63.111(a). 
Therefore, the reference needs to be revised.
    ISG line 14 has been revised to change ``10 CFR 63.111'' to ``10 
CFR 63.111(a).''
    Comment 2. The commenter recommended specific revisions to footnote 
1 (below line 38), to define an off-normal condition. The proposed 
revision could be interpreted to mean that certain deviations from 
procedures or equipment failures, that involve important to safety 
(ITS) structure, system, and component (SSC) failures during the 
preclosure period, may be classified as off-normal, not Category 1 
events.
    Response. NRC disagrees with the commenter that footnote 1 should 
be revised. As defined in 10 CFR 63.2, SSCs are designated as ITS, if 
they are relied on to satisfy the preclosure performance objectives for 
Category 1 or Category 2 event sequences. In contrast, the SSCs that 
are relied on for normal operations are not designated as ITS SSCs. 
Therefore, as stated in footnote 1, equipment failures that do not 
involve ITS SSCs and do not lead to significantly elevated exposures 
are considered as off-normal, and not Category 1 event sequences.
    No changes to the ISG were made as a result of this comment.
    Comment 3. The commenter recommended deleting the last part of 
footnote 2 (below line 74), which reads ``if the GROA is licensed,'' 
because, if the GROA is not licensed, then there would be no radiation 
protection program implementation to inspect.
    Response. NRC agrees with the commenter that the last part of the 
footnote is not needed because implementation of the radiation 
protection program can only be inspected if NRC has already licensed 
the geologic repository at Yucca Mountain.
    The ISG has been revised to delete ``if the GROA is licensed,'' in 
footnote 2.
    Comment 4. The commenter recommended specific revisions to ISG 
lines 67-70, which state that NRC should focus on those event sequences 
that lead to the most significant exposure fields and locations of 
representative persons who may receive the greatest exposure. The 
commenter stated that ISG lines 67-70 are inconsistent with the 
discussion of ``representative exposure locations,'' in ISG line 114, 
and ``potential high-exposure locations may be eliminated from 
consideration,'' in ISG lines 118-119.
    Response. NRC disagrees that ISG lines 67-70 are inconsistent with 
ISG lines 114, 118, and 119. ISG lines 67-70 refer to the Radiation 
Protection Program; whereas ISG lines 114 and 118-119 refer to the 
Estimation of Doses. It is appropriate to focus on those persons who 
may receive the greatest exposure, when NRC reviews the adequacy of a 
Radiation Protection Program, and establishment of restricted areas and 
access controls; whereas for dose estimates, potential high-exposure 
locations may be eliminated from consideration because of access 
controls and personnel monitoring.
    No changes to the ISG were made as a result of this comment.
    Comment 5. The commenter recommended revising lines 85 through 87, 
and lines 92 through 94, by deleting the word ``back,'' since this 
implies that recovery actions are needed to achieve compliance with 
Part 63.
    Response. NRC agrees with the suggested change.
    ISG lines 85-87, and 92-94, have been revised to delete the word 
``back.''
    Comment 6. The commenter stated that the method for aggregating 
annual doses in the ISG cannot, in all cases, be used to demonstrate 
compliance with the requirements of 10 CFR 63.111, and that it is not 
consistent with the performance objectives of Part 63. The commenter 
stated that the approach in the ISG does not allow consideration of the 
frequency of a Category 1 event sequence in aggregating the dose. The 
commenter recommended a specific definition of aggregate annual dose 
that is based on a statistical approach, where all doses from all 
Category 1 event sequences are frequency-weighted.
    Response. NRC disagrees that the method in the ISG for aggregating 
annual doses cannot, in all cases, be used to demonstrate compliance 
with the requirements of 10 CFR 63.111, and that it is not consistent 
with the performance objectives of Part 63. The method proposed in the 
ISG consists of summing the doses from normal operational doses, all 
occurrences of Category 1 event sequences occurring one or more times 
per year, and the maximum Category 1 event sequence expected to occur 
less than once per year. This is consistent with Part 63's approach of 
using the frequency of event sequences to categorize them in broad 
frequency bins of Category 1 and Category 2 event sequences. This 
approach is a reasonable way to estimate annual doses during the design 
review, because it does not require exactly determining frequencies for 
each and every event sequence, which would be necessary if all Category 
1 event sequences were frequency-weighted to determine the aggregate 
annual dose.
    There are many ways to aggregate doses and this method is one 
simple and direct approach to determine whether the applicant has 
demonstrated compliance with the performance objectives of Part 63. The 
applicant may propose another method in a license application, which 
NRC will review. According to the ``Statement of Considerations'' for 
Part 63, November 2, 2001 (66 Federal Register Notice 55742), the 
approach in the rule is to provide the U.S. Department of Energy (DOE) 
with the flexibility to select the type of analysis it believes most 
appropriate for the license application.
    Regardless of the approach used to demonstrate compliance, NRC will 
inspect for, and enforce compliance with, the preclosure dose limits 
during operations. If during actual operations, operational releases or 
events (e.g., multiple Category 1 event sequences in a single year) 
call into question the basis of NRC's safety decision, NRC would 
reevaluate the licensing basis, to determine the safety significance 
and take appropriate regulatory action.
    Comment 7. The commenter stated that Table 1, ``Part 63 Performance 
Objectives,'' could be interpreted to mean that there are separate 
performance objectives for normal operations and Category 1 Event 
Sequences because the Total Effective Dose Equivalent values for these 
are in separate columns.
    Response. NRC agrees that, in Table 1, lines 150-163, there should 
only be one column for the aggregated annual dose from normal 
operations and Category 1 Event Sequences.
    ISG lines 150 through 163 have been revised to combine the columns 
for normal operations and Category 1 Event Sequences.
    Comment 8. The commenter suggested deleting the word ``expected''

[[Page 30401]]

before ``Category 1 event sequences,'' in ISG lines 309 and 333, and 
adding the word ``types of'' before ``Category 1 event sequences,'' in 
ISG line 333, to provide consistency in wording between the new Review 
Method 4 and Acceptance Criterion 4.
    Response. NRC agrees with the commenter. ISG lines 309 and 333 have 
been revised to delete ``expected,'' and ISG line 333 has been revised 
to add ``types of,'' before ``Category 1 event sequences.''
    Comment 9. The commenter suggests revising ISG lines 319-321 
because the commenter interpreted the word ``confirm'' in the ISG text 
as implying ``* * * an inspection activity to determine if a facility 
has been built as required.''
    Response. NRC disagrees with the revision suggested by the 
commenter. The intent of the ISG is clearly stated in ISG lines 1-9; 
namely, the review of a license application. The word ``confirm,'' as 
used in the ISG, refers to the review of the ``descriptions'' of the 
Radiation Protection Program, and not to an inspection activity to 
determine if a facility has been built as required.
    No changes were made to the ISG as a result of this comment.
    Comment 10. The commenter stated that the definition of 
Occupational Dose in ISG line 390 is incomplete, and should be revised 
to be the same as in 10 CFR 20.1003.
    Response. NRC agrees with the commenter.
    The ISG has been revised to add the following at the end of the 
sentence on ISG line 390: ``Occupational dose does not include doses 
received from background radiation, from any medical administration the 
individual has received, from exposure to individuals administered 
radioactive material and released under 10 CFR 35.75, from voluntary 
participation in medical research programs, or as a member of the 
public.''
    Comment 11. The commenter suggested the following editorial 
changes:
    Line 178: Replace the word ``does'' with ``do.''
    Line 269: Add ``The analysis required in the paragraph must 
include, but not necessarily be limited to, consideration of,'' at the 
beginning of the sentence.
    Line 330: Revise ``Page 2.1-80'' to ``Page 2.1-81.''
    Response. NRC agrees with the commenter. The ISG has been revised 
to reflect these suggested changes.
    Comment 12. The commenter stated that ``NRC appears to be 
communicating an expectation for a greater level of detail in the Yucca 
Mountain license application recovery action plan than is 
appropriate.'' The commenter stated that ``* * * the planning and 
monitoring of recovery actions should be done within the radiation 
protection program framework of the draft ISG, and that there is no 
need for more detail until a time nearer to planned operations.'' The 
commenter added that ``* * * the ISG should delineate expectations 
before construction authorization is granted, and additional 
expectations before a license to receive and possess radiological 
material is granted.''
    Response. NRC disagrees with the commenter because the license 
application must identify those Category 1 event sequences that are 
expected to occur during the lifetime of the facility. As a part of the 
license application review, NRC will verify that the applicant has 
planned for recovery from these events, and that they will be monitored 
under the Radiation Protection Program.
    The ISG recommends that the reviewer determine that the applicant 
has described key elements of the recovery action plans. A plan should 
provide enough detail to determine that the corrective actions taken 
will assure adequate access to vital areas, and protection of safety 
equipment. It should describe the basic steps taken to recover from an 
event and the radiation exposure levels that may be present.
    No changes to the ISG were made as a result of this comment.
    Comment 13. The commenter commended NRC on ``applying the risk-
informed principles in an exemplary manner,'' in ISG lines 59-66, and 
143-147. However, the commenter added that the section on ``Estimation 
of Doses in the PCSA'' (ISG lines 102-147) was ``* * * not consistent 
with the risk-informed principles,'' and the draft ISG ``* * * removes 
the flexibility intended by the regulation,'' in the area of the 
aggregate annual dose for normal operations and Category 1 event 
sequences.
    Response. NRC disagrees with the commenter. The ISG provides DOE 
with sufficient flexibility to estimate dose for selected 
representative radiation workers or classes, on-site persons, and off-
site members of the public, with no summation of doses from different 
classes or to perform single-bounding dose estimations for radiation 
workers or classes, on-site persons, and off-site members of the 
public.
    No changes to the ISG were made as a result of this comment.
    Comment 14. The commenter stated that the method in the ISG, to 
calculate an aggregate annual dose, does not allow the applicant to sum 
only those doses for an individual or class of workers, but instead 
requires the aggregate dose to include doses to all workers. Also the 
commenter stated that the summation of doses should not be interpreted 
to remove the licensee's flexibility to apply the planned special 
exposure provisions of 10 CFR 20.1206 in the mitigation of Category 1 
event sequences.
    Response. NRC disagrees with the commenter. There are many ways to 
aggregate doses and the method in the ISG is one acceptable way to 
demonstrate whether the applicant has demonstrated compliance with the 
performance objectives of Part 63. The applicant has the flexibility to 
propose another method in a license application, which NRC will review 
as long as it is supported by technical bases.
    Planned special exposures (PSEs), defined in 10 CFR Part 20, are 
infrequent exposures to radiation, separate from, and in addition to, 
annual dose limits. PSEs are for exceptional situations, whereas the 
estimation of annual dose in the ISG includes only those doses from 
normal operations and Category 1 event sequences. Since Category 1 
event sequences are those that are expected to occur one or more times 
during the life of the facility, these events are not an exceptional 
situation and are not precluded when determining the annual dose.
    No changes to the ISG were made as a result of this comment.
    Comment 15. The commenter suggested that the ISG clarify 
terminology used in two different instances. The commenter stated that 
the first term requiring clarification is ``controlled area site 
boundary,'' introduced in ISG line 21. ISG lines 36 and 37 define the 
``site boundary'' as analogous to the ``controlled area site boundary'' 
defined in Part 20. The commenter stated that NRC should not assume 
that the ``Yucca Mountain Repository site boundary'' and the 
``controlled area for preclosure purposes,'' are necessarily the same. 
DOE should be able to define the controlled area so long as it is 
outside the restricted area, but inside the site boundary, as long as 
the requisite safety and radiation protection requirements are met. The 
commenter also suggests the use of a different term, such as 
``preclosure controlled area,'' so that limitations are not placed on 
the applicant. The second term for which the commenter suggested 
clarification is in ISG line 102, ``* * * doses from those Category 1 
event sequences that are expected to occur one or more times

[[Page 30402]]

per year.'' The commenter states that, ``it is not clear why an 
acceptable design and operational concept would include planning for 
SSC failures, more often than once per year, that resulted in a 
radiation dose,'' and these should be considered ``as part of normal 
operations as opposed to as a Category 1 event sequence.''
    Response. The Part 63 definition of ``controlled area'' is found in 
Subpart L--``Postclosure Public Health and Environmental Standards,'' 
in section 63.302, and not in Subpart K--``Preclosure Public Health and 
Environmental Standards.'' Since 10 CFR 63.111(a) requires the GROA to 
meet the requirements of Part 20, the Part 20 definitions are to be 
applied within the context of Part 63. The site boundary is analogous 
to the controlled area, defined in Part 20, because the preclosure 
limits are based on the boundary of the site, defined for preclosure, 
as that area, surrounding the GROA, for which DOE exercises authority 
over its use, in accordance with the provisions of Part 63. DOE should 
clearly identify the controlled site boundary in its demonstration of 
compliance with Part 20 requirements. However, NRC agrees that the use 
of the term ``controlled area site boundary'' may be confusing, and 
thus is deleting that term from the ISG.
    The second term, ``doses from those Category 1 event sequences that 
are expected to occur one or more times per year'' is used in the ISG 
method to aggregate doses. Although NRC agrees with the commenter that 
ITS SSCs should be designed and maintained in such a manner to prevent 
or avoid frequent failure, this term does not imply that a design that 
plans for frequent occurrences of ITS SSCs will be acceptable to NRC. 
Rather, this term is used to ensure that if the applicant submits an 
application with a Category 1 event sequence that occurs more than once 
per year, then the reviewer will include all occurrences of that event, 
when determining if the estimated annual dose meets the performance 
objectives of Part 63.
    ISG line 21 has been revised by changing ``controlled site 
boundary'' to ``controlled area.''
    ISG lines 36 and 37 have been revised by deleting the sentence, 
``The site boundary * * * Part 20.''
    ISG lines 55 and 56 have been revised by changing ``controlled area 
site boundaries'' to ``the boundaries of the controlled area.''
    ISG line 136 has been revised by changing ``controlled area site 
boundary'' to ``boundary of the site.''
    ISG line 144 has been revised by changing ``controlled area site 
boundary'' to ``boundary of the site.''
    ISG lines 169 and 177 have been revised by changing ``controlled-
area boundary'' to ``controlled area.''

FOR FURTHER INFORMATION, CONTACT: 

Jon Chen, Project Manager, Division of High-Level Waste Repository 
Safety, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001 [Telephone: (301) 415-
5526; fax number: (301) 415-5399; e-mail: jcc2@nrc.gov];
Robert K. Johnson, Senior Project Manager, Division of High-Level Waste 
Repository Safety, Office of Nuclear Material Safety and Safeguards, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 
[Telephone: (301) 415-6900; fax number: (301) 415-5399; e-mail: 
rkj@nrc.gov].

    Dated at Rockville, Maryland this 22nd day of May, 2007.

    For the Nuclear Regulatory Commission.
Sheena Whaley,
 Chief, Engineering Branch, Division of High-Level Waste Repository 
Safety, Office of Nuclear Material Safety and Safeguards.
[FR Doc. E7-10470 Filed 5-30-07; 8:45 am]
BILLING CODE 7590-01-P