ML032400316

Amendments 235 & 234 to Licenses DPR-32 and DPR-37 Respectively. Amendments Make Administrative Changes to Section 6 of Technical Specifications to Adopt Format for Topical Report References

ML032400316
Person / Time
Site:	Surry
Issue date:	08/27/2003
From:	Gratton C NRC/NRR/DLPM/LPD2
To:	Christian D Virginia Electric & Power Co (VEPCO)
Gratton C, NRR/DLPM 415-1055
References
TAC MB9502, TAC MB9503, TSTF-363 Rev 0
Download: ML032400316 (13)

Text

August 27, 2003 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060-6711

SUBJECT:

SURRY UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISIONS OF THE CORE OPERATING LIMITS REPORT REFERENCES (TAC NOS. MB9502 AND MB9503)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 235 to Renewed Facility Operating License No. DPR-32 and Amendment No. 234 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 transmitted by letter dated June 9, 2003, as supplemented July 28, 2003.

These amendments make administrative changes to Section 6 of the Surry Power Station Technical Specifications (TS) for Units 1 and 2 to adopt the format for topical report references that are described in Industry/Technical Specifications Task Force Traveler, TSTF-363, Rev 0, Revised Topical Report References in Improved Technical Specification (ITS) 5.6.5, COLR.

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/

Christopher Gratton, Sr. Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281

Enclosures:

1. Amendment No. 235 to DPR-32

2. Amendment No. 234 to DPR-37

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

ML032400316 OFFICE PDII-1/PM PDII-2/LA IROB(A) SRXB(B) OGC PDII-1/SC NAME CGratton EDunnington SMagruder FAkstulewicz RWeisman JNakoski DATE 7/31/2003 7/30/2003 7/31/2003 8/14/2003 8/20/2003 8/27/2003 DATED: August 27, 2003 AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 1 AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 2 PUBLIC PDII Rdg.

E. Dunnington C. Gratton E. Hackett J. Nakoski OGC G. Hill (4), TWFN, 5/C/3 ACRS K. Landis, RII F. Akstulewicz T. Boyce

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 235 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 June 9, 2003, as supplemented July 28, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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. 235, are hereby incorporated in the 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 and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 27, 2003

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 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 June 9, 2003, as supplemented July 28, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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. 234, are hereby incorporated in the 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 and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 27, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 LICENSE AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages TS 6.2-2 TS 6.2-2 TS 6.2-3 --

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 234 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 letter dated June 9, 2003, as supplemented in a letter dated July 28, 2003, Virginia Electric and Power Company (VEPCO, the licensee) requested changes to the Surry Power Station, Units 1 and 2, Technical Specifications (TS). The proposed changes would make administrative changes to the Surry Power Station, Units 1 and 2, TS to adopt the format for topical report references as described in Industry/Technical Specifications Task Force Traveler, TSTF-363, Revision 0, Revised Topical Report References in Improved Technical Specifications (ITS) 5.6.5, COLR [Core Operating Limits Report]. The July 28, 2003, letter provided clarifying information only and did not change the initial proposed no significant hazards consideration determination or expand the scope of the initial application.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the operating license. The content of the TS is specified in Title 10 of the Code of Federal Regulations, Section 50.36, Technical Specifications.

Traditionally, cycle-specific parameter limits have been listed in the plant TS. In an effort to avoid TS changes for every fuel reload cycle that results in the changing of the cycle-specific parameter limits, licensees have relocated the cycle-specific core operating parameters from the TS to the COLR. This is done in accordance with the guidelines of Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications. GL 88-16 also provides that licensees identify in the TS section named Reporting Requirements the previously approved analytical methods used to determine the core operating limits by identifying the topical report number, title, and date (or identify the staffs safety evaluation for a plant-specific methodology by NRC letter and date).

In a letter dated December 15, 1999, the NRC staff accepted a method proposed by Siemens Power Corporation of referencing approved topical reports. The proposed method would allow licensees to use current topical reports to support limits in the COLR without having to submit

an amendment request for the facility operating license each time a revision to the topical report is approved by the NRC. This method would allow the references to approved topical reports in the TS to be cited using the report number and title. The citation in the COLR would include specific information for each of the TS references to topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements). This method of referencing topical reports was subsequently accepted for incorporation into standard technical specifications by TSTF-363. The licensee should ensure that any revision made to a methodology does not invalidate its applicability to the Surry Power Station and must implement the methodology in a manner that is consistent with any restrictions imposed by the NRC staff as part of the methodologys approval.

3.0 TECHNICAL EVALUATION

The licensee proposed the following changes to TS 6.2.C, Core Operating Limits Report:

• Eliminate revision numbers and dates from topical reports listed in the REFERENCES section. Delete associated information detailing which limits are associated with each reference. The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements); and

• Revise reference 2f (WCAP-12610-P-A) to reflect the approval status.

The licensee stated the proposed changes do not change the licensing or design basis of the Surry Power Station, Units 1 and 2, nor are the safety margins assumed in the accident analyses affected by the proposed changes. The licensee stated that the proposed changes are administrative and do not alter the operation of the facility.

The NRC staff reviewed the proposed changes regarding the relocation of revision number and document dates in the REFERENCES section of TS 6.2.C against the guidance in TSTF-363, GL 88-16, and the requirements of 10 CFR 50.36. The NRC staff finds that the licensees proposed change to eliminate the revision numbers and dates from topical reports listed in the REFERENCES section of the TS conforms to the guidance in TSTF-363 and GL 88-16. In implementing the methodologies listed in proposed TS 6.2.C, as specified in each COLR, the licensee must conform to the restrictions imposed by the NRC staff as part of each methodologys approval. Therefore, the requested amendment is acceptable.

As part of the proposed amendment, the licensee also proposed relocating from the TS to the COLR certain parenthetical information detailing which TS limits are associated with a specific topical report (hereafter parenthetical information). The relocation of this parenthetical information was not evaluated under TSTF-363. In the licensees July 28, 2003, supplemental response, the licensee provided additional information regarding the acceptability of relocating this parenthetical information to the COLR. The licensee stated that the parenthetical information did not meet the definition of an administrative control as defined in 10 CFR 50.36(c)(5), did not satisfy any of the four criteria provided in 10 CFR 50.36(c)(2)(ii)(A) through (D), and did not meet any of the criteria for inclusion in the TS as a limiting condition for operation. The licensee also stated that the parenthetical information was added to the Surry TS as part of the amendment implementing the provisions of GL 88-16, but was not required by GL 88-16.

The NRC staff reviewed the licensees additional information and evaluated it against the requirements of 10 CFR 50.36 and the guidance in GL 88-16. The NRC staff concludes that the parenthetical information does not meet requirements in 10 CFR 50.36 for inclusion in the TS and was not needed as part of the change provided in the GL 88-16. Therefore, the NRC staff concludes that the relocation of the parenthetical information to the COLR is acceptable.

The licensee also proposed that Reference 2f (WCAP-12610), VANTAGE+ Fuel Assembly Report, be annotated to reflect that the NRC staff has approved the use of this topical report.

The NRC staff accepted this topical report in a letter to Westinghouse Electric Corporation dated July 1, 1991. Therefore, the NRC agrees that it is appropriate to annotate Reference 2f in the manner proposed in the licensees June 9, 2003, application.

Consequently, the NRC staff concludes that the proposed changes will have no adverse effect on plant safety; therefore, the NRC staff finds the proposed changes to TS 6.2.C acceptable.

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 recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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.

Principal Contributor: C. Gratton Date: August 27, 2003

Mr. David A. Christian Surry Power Station Virginia Electric and Power Company Units 1 and 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 Millstone Power Station Richmond, Virginia 23219 Building 475, 5th Floor Rope Ferry Road Mr. Chris L. Funderburk, Director Rt. 156 Nuclear Licensing & Operations Support Waterford, Connecticut 06385 Virginia Electric and Power Company Innsbrook Technical Center Mr. Richard H. Blount, II 5000 Dominion Blvd.

Site Vice President Glen Allen, Virginia 23060-6711 Surry Power Station Virginia Electric and Power Company Mr. David A. Heacock 5570 Hog Island Road Site Vice President Surry, Virginia 23883-0315 North Anna Power Station Virginia Electric and Power Company Senior Resident Inspector P. O. Box 402 Surry Power Station Mineral, Virginia 23117-0402 U. S. Nuclear Regulatory Commission 5850 Hog Island Road Mr. William R. Matthews Surry, Virginia 23883 Vice President - Nuclear Operations Virginia Electric and Power Company Chairman Innsbrook Technical Center Board of Supervisors of Surry County 5000 Dominion Boulevard Surry County Courthouse Glen Allen, Virginia 23060-6711 Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. O. Box 1197 Richmond, Virginia 23209 Robert B. Strobe, M.D., M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218