ML020430200
| ML020430200 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/11/2002 |
| From: | Dan Collins NRC/NRR/DLPM/LPD1 |
| To: | Myers L FirstEnergy Nuclear Operating Co |
| Collins D, NRR/DLPM, 415-1427 | |
| References | |
| TAC MB2300 | |
| Download: ML020430200 (8) | |
Text
February 11, 2002 Mr. L. W. Myers Senior Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT RELATED TO EXEMPTION FROM REQUIREMENTS OF 10 CFR, SECTION 50.60(a) AND 10 CFR PART 50, APPENDIX G (TAC NO. MB2300)
Dear Mr. Myers:
This letter provides a copy of the Environmental Assessment and Finding of No Significant Impact related to your request, dated June 29, 2001, for an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.60 and 10 CFR Part 50, Appendix G. The proposed exemption would allow application of American Society of Mechanical Engineers, Code Case N-640, in establishing the reactor vessel pressure limits at low temperatures for Beaver Valley Power Station, Unit No. 1.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Daniel Collins, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Environmental Assessment cc w/encl: See next page
February 11, 2002 Mr. L. W. Myers Senior Vice President Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT RELATED TO EXEMPTION FROM REQUIREMENTS OF 10 CFR, SECTION 50.60(a) AND 10 CFR PART 50, APPENDIX G (TAC NO. MB2300)
Dear Mr. Myers:
This letter provides a copy of the Environmental Assessment and Finding of No Significant Impact related to your request, dated June 29, 2001, for an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.60 and 10 CFR Part 50, Appendix G. The proposed exemption would allow application of American Society of Mechanical Engineers, Code Case N-640, in establishing the reactor vessel pressure limits at low temperatures for Beaver Valley Power Station, Unit No. 1.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Daniel Collins, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Environmental Assessment cc w/encl: See next page DISTRIBUTION:
PUBLIC MO'Brien ACRS PDI-1 Reading DCollins BPlatchek, RGN-I EAdensam OGC JTappert JMunday PTam ACCESSION NO: ML020430200 DOCUMENT NAME: C:\MYFILES\Copies\AmendExempEA2.wpd OFFICE PDI-1/PM PDI-1/PM PDI-1/LA RLEP/SC OGC PDI-1/SC(A)
NAME DCollins PTam MOBrien JTappert JMoore JMunday DATE 2/4/02 2/4/02 2/04/02 2/7/02 2/8/02 2/11/02 OFFICIAL RECORD COPY
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION PENNSYLVANIA POWER COMPANY OHIO EDISON COMPANY FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.60(a), and 10 CFR Part 50, Appendix G, for Facility Operating License No. DPR-66, issued to FirstEnergy Nuclear Operating Company (the licensee), for operation of the Beaver Valley Power Station, Unit No. 1 (BVPS-1), located in Beaver County, Pennsylvania. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
Appendix G to 10 CFR Part 50 requires that pressure/temperature (P/T) limits be established for reactor pressure vessels during normal operating and hydrostatic or leak rate testing conditions. Specifically, this regulation states, The appropriate requirements on both the pressure-temperature limits and the minimum permissible temperature must be met for all conditions. Additionally, it specifies that the requirements for these limits are contained in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
Section XI, Appendix G.
To address provisions of an amendment to the Technical Specification P/T limits, the
licensee requested in its application dated June 29, 2001, as supplemented by letters of October 4 and December 1, 2001, that the NRC staff exempt BVPS-1 from the requirements of 10 CFR, Section 50.60(a), and 10 CFR Part 50, Appendix G, to allow application of ASME Code Case N-640 in establishing the reactor vessel pressure limits at low temperatures.
ASME Code Case N-640 permits the use of an alternate reference fracture toughness (KIC fracture toughness curve instead of the KIa fracture toughness curve) for reactor vessel materials in determining the P/T limits. Since the KIC fracture toughness curve shown in ASME Code,Section XI, Appendix A, Figure A-2200-1 (the KIC fracture toughness curve), provides greater allowable fracture toughness than the corresponding KIa fracture toughness curve of ASME Code,Section XI, Appendix G, Figure G-2210-1 (the KIa fracture toughness curve), using Code Case N-640 for establishing the P/T limits would be less conservative than the methodology currently endorsed by 10 CFR Part 50, Appendix G. Therefore, an exemption is required in order to apply ASME Code Case N-640.
The proposed action is in accordance with the licensees application for exemption dated June 29, 2001, and supplements dated October 4 and December 1, 2001.
The Need for the Proposed Action:
ASME Code Case N-640 is needed to revise the method used to determine the reactor coolant system (RCS) P/T limits.
The purpose of 10 CFR 50.60(a), and 10 CFR Part 50, Appendix G, is to protect the integrity of the reactor coolant pressure boundary in nuclear power plants. This protection is accomplished through these regulations that, in part, specify fracture toughness requirements for ferritic materials of the reactor coolant pressure boundary. Pursuant to 10 CFR Part 50, Appendix G, it is required that P/T limits for the RCS be at least as conservative as those obtained by applying the methodology of the ASME Code,Section XI, Appendix G.
Current overpressure protection system (OPPS) setpoints produce operational constraints by limiting the P/T range available to the operator to heat up or cool down the plant.
The operating window through which the operator heats up and cools down the RCS becomes more restrictive with continued reactor vessel service. Reducing this operating window could potentially have an adverse safety impact by increasing the possibility of inadvertent OPPS actuation due to pressure surges associated with normal plant evolutions such as reactor coolant pump start and swapping operating charging pumps with the RCS in a water-solid condition. The impact on the P/T limits and OPPS setpoints has been evaluated for an increased service period to 22 effective full power years based on ASME Code,Section XI, Appendix G, requirements. The results indicate that the OPPS would significantly restrict the ability to perform plant heatup and cooldown, create an unnecessary burden to plant operations, and challenge control of plant evolutions required with OPPS enabled. Continued operation of BVPS-1 with P/T curves developed to satisfy ASME Code,Section XI, Appendix G, requirements without the relief provided by ASME Code Case N-640 would unnecessarily restrict the P/T operating window, especially at low-temperature conditions.
Application of ASME Code Case N-640 will provide results which are sufficiently conservative to ensure the integrity of the reactor coolant pressure boundary while providing P/T curves which are not overly restrictive.
In the associated exemption, the NRC staff would determine that, pursuant to 10 CFR 50.12(a)(2)(ii), the underlying purpose of the regulation will continue to be served by the implementation of ASME Code Case N-640.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that there are no significant environmental impacts associated with the use of ASME Code Case N-640 to develop the new P-T limits and OPPS setpoints.
The proposed action will not significantly increase the probability or consequences of accidents, no changes are being made in the types of any effluents that may be released off site, and there is no significant increase in occupational or public radiation exposure.
Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does not involve any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
This action does not involve the use of any resources not previously considered in the Final Environmental Statement for BVPS-1 dated July 1973.
Agencies and Persons Consulted:
On January 24, 2002, the staff consulted with the Pennsylvania State official, Mr. L. Ryan, of the Pennsylvania Department of Environmental Protection Bureau, Division of Nuclear Safety, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated June 29, 2001, as supplemented by letters dated October 4 and December 1, 2001.
Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland.
Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams/html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland this 11th day of February 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Daniel Collins, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Beaver Valley Power Station, Units 1 and 2 Mary OReilly, Attorney FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station FirstEnergy Corporation Post Office Box 4 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 ATTN: Kevin L. Ostrowski, Plant General Manager (BV-SOSB-7)
FirstEnergy Nuclear Operating Company Licensing Section Bureau of Radiation Protection Thomas S. Cosgrove, Manager (2 Copies) Pennsylvania Department of Beaver Valley Power Station Environmental Protection Post Office Box 4, BV-A ATTN: Larry Ryan Shippingport, PA 15077 Post Office Box 2063 Harrisburg, PA 17120 Commissioner Roy M. Smith West Virginia Department of Labor Mayor of the Borough of Building 3, Room 319 Shippingport Capitol Complex Post Office Box 3 Charleston, WV 25305 Shippingport, PA 15077 Director, Utilities Department Regional Administrator, Region I Public Utilities Commission U.S. Nuclear Regulatory Commission 180 East Broad Street 475 Allendale Road Columbus, OH 43266-0573 King of Prussia, PA 19406 Director, Pennsylvania Emergency Resident Inspector Management Agency U.S. Nuclear Regulatory Commission Post Office Box 3321 Post Office Box 298 Harrisburg, PA 17105-3321 Shippingport, PA 15077 Ohio EPA-DERR FirstEnergy Nuclear Operating Company ATTN: Zack A. Clayton Beaver Valley Power Station Post Office Box 1049 Post Office Box 4 Columbus, OH 43266-0149 Shippingport, PA 15077 ATTN: M. P. Pearson, Director Plant Dr. Judith Johnsrud Services (BV-NCD-3)
National Energy Committee Sierra Club Mr. J. A. Hultz, Manager 433 Orlando Avenue Projects & Support Services State College, PA 16803 First Energy 76 South Main Street FirstEnergy Nuclear Operating Company Akron, OH 44308 Beaver Valley Power Station Mr. J. J. Maracek Post Office Box 4, BV-A Shippingport, PA 15077