ML061710242

License Amendments, Issuance of Amendments to Reinstate Previous Reactor Coolant System Pressure and Temperature Limits (TAC Nos. MD1236 and MD1237)

ML061710242
Person / Time
Site:	Surry
Issue date:	06/29/2006
From:	Stephen Monarque NRC/NRR/ADRO/DORL/LPLC
To:	Christian D Virginia Electric & Power Co (VEPCO)
Monarque, S R, NRR/DORL, 415-1544
Shared Package
ML061710263	List: ML061710242 ML061800269
References
TAC MD1236, TAC MD1237
Download: ML061710242 (16)

Text

June 29, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, VA 23060-6701

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS TO REINSTATE PREVIOUS REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS (TAC NOS. MD1236 AND MD1237)

Dear Mr. Christian:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 248 to Renewed Facility Operating License No. DPR-32 and Amendment No. 247 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.

The amendments change the Technical Specifications (TS) in response to your application dated April 20, 2006, as supplemented by letter dated May 15, 2006.

These amendments reinstate the reactor coolant pressure and temperature limits, low-temperature overpressure protection system (LTOPS) setpoint values, and LTOPS enable temperatures that were in place prior to the approval of License Amendments 245 and 244.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Stephen Monarque, Project Manager Plant Licensing Branch II-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281

Enclosures:

1. Amendment No. 248 to DPR-32

2. Amendment No. 247 to DPR-37

3. Safety Evaluation cc w/encls: See next page

June 29, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6701

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS TO REINSTATE PREVIOUS REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS (TAC NOS. MD1236 AND MD1237)

Dear Mr. Christian:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 248 to Renewed Facility Operating License No. DPR-32 and Amendment No. 247 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.

The amendments change the Technical Specifications (TS) in response to your application dated April 20, 2006, as supplemented by letter dated May 15, 2006.

These amendments reinstate the reactor coolant pressure and temperature limits, low-temperature overpressure protection system (LTOPS) setpoint values, and LTOPS enable temperatures that were in place prior to the approval of License Amendments 245 and 244.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Stephen Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281

Enclosures:

1. Amendment No. 248 to DPR-32

2. Amendment No. 247 to DPR-37

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

Public RidsOgcRp RidsNrrDssSbwb(GCranston)

LPL2-1 R/F RidsAcrsAcnwMailCenter RidsRgn2MailCenter(KLandis)

RidsNrrDorlLplc(EMarinos) GHill(4 hard copies) RidsNrrDciCvib(MMitchell)

RidsNrrPMSMonarque RidsNrrDirsItsb(TKobetz) RidsNrrDciCvib(NRay)

RidsNrrLAMOBrien RidsNrrDssSbwb(LLois) BSingal, DORL DPR Package No. ML061710263 Tech Spec No. ML061800269 Amendment No. ML061710242 NRR-058 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CVIB/BC NRR/SBWB/BC OGC NRR/LPL2-1/BC NAME SMonarque MOBrien MMitchell GCranston JEM EMarinos DATE 6/8/06 6/19/06 06/06/2006 06/05/2006 6/16/06 6/28/06 OFFICIAL RECORD COPY

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 Renewed License No. DPR-32

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Virginia Electric and Power Company (the licensee) dated April 20, 2006, as supplemented by letter dated May 15, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-32 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 248, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. DPR-32 and the Technical Specifications Date of Issuance: June 29, 2006

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 247 Renewed License No. DPR-37

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Virginia Electric and Power Company (the licensee) dated April 20, 2006, as supplemented by letter dated May 15, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-37 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. DPR-37 and the Technical Specifications Date of Issuance: June 29, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 LICENSE AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License Pages License Pages License No. DPR-32, page 3 License No. DPR-32, page 3 License No. DPR-37, page 3 License No. DPR-37, page 3 TS Pages TS Pages 3.1-9 3.1-9 3.1-10 3.1-10 3.1-11 3.1-11 3.1-23a 3.1-23a Figure 3.1-1 Figure 3.1-1 Figure 3.1-2 Figure 3.1-2

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281

1.0 INTRODUCTION

By application dated April 20, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061110056), as supplemented by letter dated May 15, 2006 (ADAMS Accession No. ML061350295), Virginia Electric and Power Company (the licensee) requested changes to the Technical Specifications (TSs) for the Surry Power Station, Unit Nos.

1 and 2 (Surry 1 and 2). The supplement dated May 15, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on April 28, 2006 (71 FR 25249).

By letter dated December 17, 2004 (ADAMS Accession No. ML050190317), the licensee requested changes to the TSs for Surry 1 and 2 to revise the reactor coolant system (RCS) pressure/temperature (P/T) operating limits, the low temperature overpresuure protection system (LTOPS) setpoint, and the LTOPS enable temperature (Tenable) basis for cumulative core burnups up to 47.6 effective full power years (EFPY) and 48.1 EFPY (corresponding to the period of the renewed licenses). This TS change corresponded to the period of the renewed licenses for Surry 1 and 2. On January 3, 2006, the Nuclear Regulatory Commission (NRC) staff approved of the proposed TSs as License Amendments 245 and 244 for Surry 1 and 2, respectively (ADAMS Accession No. ML060040243). However, subsequent to the issuance of these license amendments, the licensee discovered an error in the technical basis that supported the proposed TSs change and was relied upon by the NRC staff in its safety evaluation. Specifically, the revised RCS P/T limit curves did not consider the most limiting material property data at the 3/4 thickness (3/4-T) reactor vessel thickness location. As such, by letter dated April 20, 2006, as supplemented by letter dated May 15, 2006, the licensee requested to withdraw License Amendments 245 and 244 and reinstate the RCS P/T operating limits, the LTOPS setpoint, and LTOPS Tenable basis that were in place prior to the approval of License Amendments 245 and 244 for Surry 1 and 2, respectively, on January 3, 2006.

2.0 REGULATORY EVALUATION

In issuing an amendment to an operating license, the NRC staff states when the amendment is effective and, if necessary, when the amendment must be implemented. The implementation dates for Surry 1 and 2 are given in Enclosures 1 and 2 of the amendments and are part of the operating licenses for both of these units. Therefore, a change to the implementation date is a change to the operating license for either Surry 1 or 2. Although there are no regulatory requirements on the implementation date specified in an amendment, the licensee is required by the operating license to fully implement the amendment by the date specified (i.e., by a date no later than that specified) or be in violation of its operating license.

The NRC staff evaluated the acceptability of the licensees proposed changes based on the following guidance:

Regulatory Guide (RG) 1.190, March 2001, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, describes methods and assumptions acceptable to the NRC staff for determining the RPV neutron fluence.

3.0 TECHNICAL EVALUATION

3.1 Licensees proposed Changes By letter dated April 20, 2006, the licensee proposed to replace TS Figures 3.1-1 and 3.1-2 and the cumulative core burnup limits that were previously approved by the NRC staff in License Amendments 245 and 244 with TS Figures 3.1-1 and 3.1-2 that were previously approved by the NRC staff in License Amendments 207 and 207, dated December 28, 1995 (ADAMS Accession No. ML012710054). In addition, the licensee requested to revise the EFPYs from 47.6 and 48.1, which were previously approved by the NRC staff in License Amendments 245 and 244, to 28.8 and 29.4 for Surry 1 and 2, respectively. The NRC staff had previously approved of 28.8 EFPY and 29.4 EFPY in License Amendments 207 and 207. The licensee also proposed associated TS Basis changes to facilitate a return to the previous TS Basis text that had been approved before License Amendments 245 and 244.

The licensee proposed to revise TS 3.1.G.1.c(4) to change the Power Operated Relief Valve (PORV) setting from a value of 395 psig., which was previously approved by the NRC staff in License Amendments 245 and 244, to a value of 390 psig., which was previously approved by the NRC staff in License Amendments 207 and 207 at Surry 1 and 2, respectively.

Because the operating limits and setpoints approved in License Amendments 245 and 244 were not implemented, the licensee has continued to operate using the limits and setpoints that were approved by the NRC staff prior to the issuance of License Amendments 245 and 244.

3.2 Neutron Fluence During the review of the licensees submittal dated April 20, 2006, the NRC staff noted the licensees analysis, as described in License Amendments 207 and 207, dated December 28, 1995, utilized a methodology for determining neutron fluence that has since been replaced by RG 1.190. Specifically, License Amendments 207 and 207 did not apply the latest neutron cross-section library of the Evaluated Nuclear Data file (ENDF/B-VI). RG 1.190 provides an updated ENDF/B-VI cross-section data that has been demonstrated to provide a more accurate determination of the flux attenuation through iron. In addition, the licensee was requested to confirm that the RCS P/T operating limits curves and LTOPS setpoint remained conservative with respect to the more recently performed analyses, described in Topical Report

BAW-2241PA, Revision 1, Fluence and Uncertainty Methodologies. Subsequently, on May 15, 2006, the licensee provided a supplemental response to the NRC staff that addressed these questions.

3.2.1 Methodology At the time the NRC staff approved of License Amendments 207 and 207, the licensee used a reactor fluence analysis that had been performed by Westinghouse and utilized the ENDF/B-IV cross section library. At the time these amendments were issued on December 28, 1995, RG 1.190 had not been issued and ENDF/B-VI was not the latest neutron cross section library.

Subsequently, in its letter dated, May 15, 2006, the licensee recalculated the Surry vessel fluence for both units. These calculations were performed by AREVA (Framatome) using the NRC staff approved methodology described in Topical Report BAW-2241P. The NRC staffs approval of the AREVA methodology does include one limitation that is relevant to the proposed license amendment for Surry, and that is the adequacy of the benchmarking. The licensee, in its letter dated May 15, 2006, satisfied the limitation by indicating that the data base used for the code benchmarking included surveillance capsule data from Surry. In addition, the licensees methodology followed the guidance in RG 1.190 by using the cross sections derived from the ENDF/B-VI file. Therefore, the NRC staff finds the licensees methodology acceptable.

3.2.2 Fluence Values The RCS P/T operating limits and LTOPS setpoints originally approved in License Amendments 207 and 207 were based on a limiting 1/4-T nil-ductility transition reference temperature (RTNDT) of 228.4 °F, and a limiting 3/4-T RTNDT of 189.5 °F. The licensee first developed the RCS P/T operating limits and LTOPS setpoints, then determined that the RTNDT values bounded all reactor vessel beltline materials at the end of the 40-year license fluences. These fluences corresponded to 28.8 EFPY and 29.4 EFPY for Surry 1 and 2, respectively.

By letter dated May 16, 2006, the licensee recalculated the reactor vessel neutron fluence for the license extension application. At the reactor vessel neutron fluence projections corresponding to 32 EFPYs, the licensee identified the intermediate to lower shell circumferential weld (SA-1585/72445) to be the limiting element for both units. The recalculated 1/4-T location is 2.282x1019 n/cm2 (from 2.45x1019 n/cm2) and at 3/4-T is .849x1019 n/cm2 (from

.938x1019 n/cm2). The corresponding RTNDT values for the SA-1585, at 1/4-T is 224.3°F and at 3/4-T is 188.9°F. The licensee performed this calculation for 32 EFPYs while the estimated EFPY values for Surry 1 and 2 are 28.8 and 29.4, respectively. The value of 32 EFPYs is considered to be a more conservative value than the 40-year operating period. The NRC staff concludes that these values justify the licensees analysis that the existing P/T operating limit curves and the LTOP setpoints are conservative. As such, the NRC staff finds the licensees proposed changes acceptable.

3.3 PORV Lift Setpoints The licensee has proposed to change the PORV lift setting from a value of 395 psig., which was previously approved by the NRC staff in License Amendments 245 and 244, to a value of 390 psig. The NRC staff previously approved 390 psig. in License Amendments 207 and 207 at Surry 1 and 2. The licensees proposal to reinstate the PORV lift setpoints does not affect any technical or safety aspects of plant operation at Surry 1 and 2. Because the setpoints approved in License Amendments 245 and 244 have not been implemented, the licensee has continued to operate, during this period, using the 390 psig setpoints. Therefore, there is no

safety issue involved with the continued use of this value, and the NRC staff finds this value acceptable.

3.4 Bases Change In License Amendments 245 and 244, the NRC staff approved of the licensees request to use the stress intensity factor K1c that was obtained from Section XI to the American Society for Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code). By letter dated April 20, 2006, the licensee proposed to reinstate the KIR stress intensity factor defined in Appendix G to the ASME Code. Because License Amendments 245 and 244 were not implemented, the licensee has continued to use the KIR stress intensity factor. The KIR stress intensity factor was originally approved by the NRC staff in License Amendments 147 and 143, dated October 24, 1990 (ADAMS Accession No. 9011010236), for Surry 1 and 2, respectively.

Since 1990, there have been no safety issues associated with the use of the KIR stress intensity factor. As such, the NRC staff finds the licensees proposal acceptable.

3.3 Conclusion The NRC staff has reviewed the submitted information regarding the reinstatement request by the licensee, for the P/T operating limit curves, LTOPS setpoints, KIR stress intensity factor, and PORV lift setpoints, and finds that the licensees proposed changes are acceptable. This finding is based on the licensees calculational method that adhered to the guidance in RG 1.190.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comment.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 25249). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1. Letter from B. Buckley, NRC, to J. P. OHanlon, Virginia Electric and Power Company, Surry Units 1 and 2 - Issuance of Amendments Re: Surry, Units 1 and 2, Reactor Vessel Heatup and Cooldown Curves (TAC Nos. M92537 AND M92538), dated December 28, 1995.

2. Letter from L. N. Hartz, Virginia Electric and Power Company to NRC Virginia Electric and Power Company Surry Power Stations Units 1 and 2 Proposed Technical Specification Change Request for Reactor Coolant System Pressure/Temperature Limits, LTOP Setpoint, and LTOP Enable Temperature with Exemption Request for Alternate Material Properties Basis per 10 CFR 50.609(b), dated December 17, 2004.

3. Letter from S. Monarque, NRC, to D. Christian, Virginia Electric and Power Company, Surry Power Station, Units 1 and 2 - Issuance of Amendments on Reactor Coolant System Pressure and Temperature Limits (TAC Nos. MC5509 and MC5510)," dated January 3, 2006.

4. Letter from E. S. Grecheck, Virginia Electric and Power Company, to NRC, Surry Power Station Units 1 and 2, Proposed Technical Specifications Change Request for Reinstatement of Previous Reactor Coolant System Pressure/Temperature Limits, LTOPS Setpoint, and LTOPS Enable Temperature Basis, dated April 20, 2006.

5. Letter from E. S. Grecheck, Virginia Electric and Power Company, to NRC, Surry Power Station Units 1 and 2, Proposed Technical Specifications Change Request for Reactor Coolant System Pressure/Temperature Limits, LTOPS Setpoint, and LTOPS Enable Temperature Basis Response to Request for Additional Information, dated May 15, 2006.

6. Framatome Topical Report BAW-2241PA, Revision 1, Fluence and Uncertainty Methodologies by Framatome ANP, December 1999.

7. Regulatory Guide (RG) 1.190, March 2001, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.

8. Letter from B. Buckley, NRC, to W. L. Stewart, Virginia Electric and Power Company, Surry Units 1 and 2 - Issuance of Amendments RE: Heatup and Cooldown Curves (TAC Nos. 67386, 67387, 71555, and 71556)," dated October 24, 1990.

Principal Contributors: L. Lois S. Monarque Date: June 29, 2006

Surry Power Station, Units 1 & 2 cc:

Ms. Lillian M. Cuoco, Esq. Office of the Attorney General Senior Counsel Commonwealth of Virginia Dominion Resources Services, Inc. 900 East Main Street Building 475, 5th Floor Richmond, Virginia 23219 Rope Ferry Road Waterford, Connecticut 06385 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Mr. Donald E. Jernigan Dominion Resources Services, Inc.

Site Vice President Innsbrook Technical Center Surry Power Station 5000 Dominion Blvd.

Virginia Electric and Power Company Glen Allen, Virginia 23060-6711 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218