[Federal Register Volume 59, Number 170 (Friday, September 2, 1994)] [Notices] [Page 0] From the Federal Register Online via the Government Publishing Office [www.gpo.gov] [FR Doc No: 94-21767] [[Page Unknown]] [Federal Register: September 2, 1994] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-424 and 425] Georgia Power Company, et al; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License Nos. NPF-68 and NPF-81 issued to Georgia Power Company, Ogelthorpe Power Corporation Municipal Electric Authority of Georgia, City of Dalton, Georgia (the licensee) for operation of the Vogtle Electric Generating Plant, Units 1 and 2, located in Burke County, Georgia. The proposed amendment will relocate the requirements of Technical Specification 3/4.7.10, Area Temperature Monitoring, to section 16.3 of the VEGP Final Safety Analysis Report (FSAR). With this relocation to the FSAR, GPC plans to clarify the basis for areas to be monitored and modify these surveillance requirements. This change is being proposed in accordance with NUREG-1431, ``Standard Technical Specifications, Westinghouse Plants.'' Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: The purpose of area temperature monitoring is to provide reasonable assurance that the normal operating temperatures in the selected rooms will remain consistent with the temperatures assumed for the environmental qualification of safety related equipment. The normal operating temperature is significant for its effect on the qualified life of the components as well as the predicted environmental transients (i.e., pressure, temperature, and radiation) that occur under accident conditions. The following justifications are provided for the proposed changes to the area temperature monitoring program: 1. The proposed change to perform temperature surveillance only when the normal ventilation system is out of service is justified based on the following: a. The HVAC systems at VEGP have been designed to maintain the room temperatures at less than the maximum normal temperature specified for environmental qualification purposes. The HVAC calculations have conservatively considered the worst case heat load conditions with a nominal safety factor when sizing the cooling systems that serve the subject rooms. As a result, the plant is generally maintained at temperatures well below the level assumed for normal operation and used for environmental qualification of equipment. b. Temperature monitoring activities per Technical Specification 3/ 4.7.10 have been in place for 6 years on Unit 1 and 4 years on Unit 2. The data collected during this time demonstrate that the temperatures have remained well within environmental qualification limits with the exception of the main steam isolation valve (MSIV) area which has exceeded its reportability limits on several occasions. The MSIV area has since been provided with a new ventilation system and temperature monitoring instrumentation. When the normal ventilation system for one of the specified rooms is not functioning, temperature monitoring activities will resume at the previously specified rate of once every 12 hours. The proposed change to monitor these rooms only when the normal ventilation system is out of service will provide a level of assurance that is similar to that provided by the current Technical Specification. Therefore, continued monitoring is not warranted as long as the normal ventilation systems are functioning. 2. The proposed change in room selection criteria to eliminate rooms that are classified as mild environment is justified based on the current methods of environmental qualification. The qualified life of safety related equipment in mild environment is no longer based on environmental qualification, but is based on a combination of design life, trending, and periodic maintenance and surveillance as discussed in FSAR section 3.11.B. Therefore, the monitoring of mild rooms is not required to verify that the normal design temperature is being maintained. However, the existing Technical Specifications not only require monitoring of the normal room temperature, but also require actions to evaluate equipment operability if an abnormal condition temperature limit is exceeded. To address this abnormal temperature condition, the rooms that are not monitored based on mild environment will not exceed 150 deg.F following a complete loss of normal HVAC for a 7-day period.\1\ The abnormal temperature limits currently shown in the Technical Specifications are the calculated room temperatures with a loss of normal HVAC for a 24-hour period. The new criterion is based on an equipment qualification analysis that demonstrates that short duration temperature excursions of up to 24 hours at 150 deg.F have an insignificant effect on the qualified life of electrical and mechanical equipment. The limitation is further supported by Appendix F of NUMARC Report 87-00 that concludes that electrical and mechanical equipment will operate in station blackout conditions with no loss of function with temperatures of up to 150 deg.F for short durations (i.e., 4 hours). \1\Per project calculations, the loss of normal HVAC for 7 days has been shown to be sufficient time to achieve steady state temperature conditions. --------------------------------------------------------------------------- 3. Relocation of area temperature monitoring to the FSAR and the revision of the TS reporting requirements are justified as follows: a. As discussed in enclosure 1 [of the licensee's February 3, 1994 submittal], the existing TS requirements for the area temperature monitoring program do not meet any of the criteria of the Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors and can safely be relocated to the FSAR. b. The area temperature monitoring program added to the FSAR will continue to ensure that room temperatures are maintained within the limits assumed for environmental qualification. The monitoring requirements of once every 12 hours when the normal ventilation system is not in service will ensure that a room would not experience a short duration temperature excursion for more than 24 hours without an evaluation of equipment operability. Although reporting requirements have been excluded from the FSAR description, an evaluation of equipment operability will continue to be performed in the event that the temperature limits are exceeded. The reporting of operability concerns to the NRC will be based on the reporting requirements for the specific equipment in an affected area after a determination of operability has been made. The current TS requires that a report be prepared and submitted to the NRC that demonstrates the continued operability of the affected equipment if the maximum normal temperature in an area is exceeded for more than 8 hours. The new FSAR description will continue to require an evaluation of equipment operability if either the normal temperature limit or abnormal condition temperature limit is exceeded. However, no report to the NRC will be required unless the equipment operability evaluation indicates a reportable condition. Based on the above considerations, GPC has concluded the following concerning 10 CFR 50.92. 1. The proposed change to the Technical Specifications does not involve a significant increase in the probability or consequences of an accident previously evaluated. The environmental qualification and operability of the safety related equipment will not be adversely affected by the proposed changes to the area temperature monitoring program. The relocation of TS to the FSAR and the changes to monitoring frequency will not increase the probability that the room temperature design limits will be exceeded or result in a loss of qualified life of safety related equipment. In addition, the consequences of exceeding the temperature limits will not significantly differ from the existing program since an evaluation of qualified life and operability will continue to be performed. 2. The proposed change to the Technical Specifications does not create the possibility of a new or different kind of accident from any accident previously evaluated. The relocation of area temperature monitoring to the FSAR and the changes in monitoring procedures do not change the design of individual equipment, systems, nor the plant operating procedures and therefore will not create the possibility of a new or different kind of accident from those already evaluated. 3. The proposed change to the Technical Specifications does not involve a significant reduction in the margin of safety because the revised monitoring requirements will continue to ensure that the environmental qualification temperature limits of safety related equipment scoped in the area temperature monitoring program will not be exceeded without an evaluation of equipment operability. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of the 30-day period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the Federal Register a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently. Written comments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to Room 6D22, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555. The filing of requests for hearing and petitions for leave to intervene is discussed below. By October 3, 1994, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at Burke County Public Library, 412 Fourth Street, Waynesboro, Georgia 30830. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order. As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) The nature of the petitioner's right under the Act to be made party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect(s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above. Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross- examine witnesses. If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment. A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at 1- (800) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Herbert N. Berkow: petitioner's name and telephone number, date petition was mailed, plant name, and publication date and page number of this Federal Register notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and to Arthur H. Domby, Troutman Sanders, Nations Bank Plaza, 600 Peachtree Street, NE., Atlanta, Georgia 30308, attorney for the licensee. Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1) (i)-(v) and 2.714(d). For further details with respect to this action, see the application for amendment dated February 3, 1994, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the local public document room located at the Burke County Public Library, 412 Fourth Street, Waynesboro, Georgia 30830. Dated at Rockville, Maryland, this 29th day of August, 1994. For the Nuclear Regulatory Commission. Louis Wheeler, Project Manager, Project Directorate II-3, Division of Reactor Projects--I/II, Office of Nuclear Reactor Regulation. [FR Doc. 94-21767 Filed 9-1-94; 8:45 am] BILLING CODE 7590-01-M