ML022980007

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Surrey Power Stations, Units 1 and 2, Request for Additional Information on Virginia Electric and Power Company'S Reload Nuclear Design Methodology Topical Report VEP-FRD-42
ML022980007
Person / Time
Site: Surry, North Anna  Dominion icon.png
Issue date: 10/25/2002
From: Edison G, Stephen Monarque
NRC/NRR/DLPM/LPD2
To: Christian D
Virginia Electric & Power Co (VEPCO)
Monarque S, NRR/DLPM, 415-1544
References
TAC MB3141, TAC MB3142, TAC MB3151, TAC MB3152
Download: ML022980007 (4)


Text

October 25, 2002 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

NORTH ANNA POWER STATION, UNITS 1 AND 2, AND SURRY POWER STATIONS, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION ON VIRGINIA ELECTRIC AND POWER COMPANYS RELOAD NUCLEAR DESIGN METHODOLOGY TOPICAL REPORT VEP-FRD-42 (TAC NOS.

MB3141, MB3142, MB3151, AND MB3152)

Dear Mr. Christian:

The purpose of this letter is to request additional information regarding the analytical models that are used in Topical Report VEP-FRD-42, Revision 2, Reload Nuclear Design Methodology, submitted for staff approval by letter dated October 8, 2001, by Virginia Electric and Power Company (VEPCO).

VEPCO had requested approval of this topical report to allow the North Anna and Surry Power Stations, Units 1 and 2, to utilize either Westinghouse or Framatome-ANP fuel. The staffs safety evaluation dated July 29, 1986, had restricted the applicability of VEP-FRD-42, Revision 1-A, to only Westinghouse-supplied reloads.

The analytical methods section of Topical Report VEP-FRD-42, Revision 2, included a discussion of four computer codes that VEPCO revised under the provisions of Title 10 of the Code of Federal Regulations Section 50.59. These codes are the PDQ Two Zone, NOMAD, RETRAN, and TIP/CECOR codes. The topical reports for the prior versions of these codes were reviewed and approved by the NRC staff, and are referenced in VEP-FRD-42, Revision 1-A dated September 1986. VEPCO had requested staff approval of later revisions of these codes through 1996, but these actions were not completed.

Topical Report VEP-FRD-42 is referenced in the Core Operating Limits Report (COLR) sections of the North Anna Improved Technical Specifications (ITS) and Surry Technical Specifications.

Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits From Technical Specifications, requires that limits in a COLR be calculated using an NRC-approved methodology. Therefore, VEP-FRD-42, Revision 2, including the analytical methods that are described within this topical report, must be approved by the staff prior to their use. This is also consistent with North Anna ITS Section 5.6.b that requires the analytical methods described in Topical Report VEP-FRD-42, which are used to determine the core operating limits, be reviewed and approved by the NRC.

While conducting a review of the PDQ Two Zone, NOMAD, RETRAN, and TIP/CECOR codes, the NRC staff located the latest revisions that will be reviewed. VEPCO is requested to confirm

that the submittals listed below are the latest revisions for these codes that have not received NRC staff approval.

1. PDQ - The staff will review Topical Report VEP-NAF-1, July, 1990, submitted in a letter from VEPCO to NRC dated October 1, 1990.
2. NOMAD - The staff will review Topical Report VEP-NFE-1A, Supplement 1, September 1996, submitted in a letter from VEPCO to NRC dated November 11, 1996.
3. TIP/CECOR - The staff will review Topical Report VEP-NAF-2, November 1991, submitted in a letter from VEPCO to NRC dated December 20, 1991.
4. RETRAN - The staff will review the information submitted in a letter from VEPCO to NRC dated August 10, 1993. The information provided in this submittal was only applicable for North Anna, Units 1 and 2.

Since the NRC staff does not have the RETRAN model submittal for Surry Power Station, Units 1 and 2, VEPCO is requested to provide the submittal that contains the latest revision to this model. The NRC staff requests a response to this request for additional information within 45 days of the date of this letter.

Sincerely,

/RA

/RA/

Stephen R. Monarque, Project Manager Gordon E. Edison, Sr. Project Manager Project Directorate II, Section 1 Project Directorate II, Section 1 Division of Licensing Project Management Division of Licensing Project Management Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation Docket Nos. 50-280, 50-281, 50-338, and 50-339

October 25, 2002 that the submittals listed below are the latest revisions for these codes that have not received NRC staff approval.

1. PDQ - The staff will review Topical Report VEP-NAF-1, July, 1990, submitted in a letter from VEPCO to NRC dated October 1, 1990.
2. NOMAD - The staff will review Topical Report VEP-NFE-1A, Supplement 1, September 1996, submitted in a letter from VEPCO to NRC dated November 11, 1996.
3. TIP/CECOR - The staff will review Topical Report VEP-NAF-2, November 1991, submitted in a letter from VEPCO to NRC dated December 20, 1991.
4. RETRAN - The staff will review the information submitted in a letter from VEPCO to NRC dated August 10, 1993. The information provided in this submittal was only applicable for North Anna, Units 1 and 2.

Since the NRC staff does not have the RETRAN model submittal for Surry Power Station, Units 1 and 2, VEPCO is requested to provide the submittal that contains the latest revision to this model. The NRC staff requests a response to this request for additional information within 45 days of the date of this letter.

Sincerely,

/RA/ /RA/

Stephen R. Monarque, Project Manager Gordon E. Edison, Sr. Project Manager Project Directorate II, Section 1 Project Directorate II, Section 1 Division of Licensing Project Management Division of Licensing Project Management Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation Docket Nos. 50-280, 50-281, 50-338, and 50-339 DISTRIBUTION:

PUBLIC GEdison (paper copy) PDII-1 R/F DMcCain RidsNrrDlpmLpdii MKowal, SRXB EDunnington (paper copy)

RidsOGCRp RidsAcrsAcnwMailCenter SMonarque RidsRgn2MailCenter FAkstulewicz KOrr UShoop

  • Previously concurred OFFICE LA:PDII/S2 PM:PDII/S1 PM:PDII/S1 SC:SRXB SC:PDII/S1 NAME EDunnington SMonarque GEdison FAkstulewicz* JNakoski DATE 10/23/02 10/23/02 10/24/02 10 /17 /02 10/24/02 COPY Yes/No Yes/No Yes/No Yes/No Yes/No OFFICIAL RECORD COPY

Mr. David A. Christian Virginia Electric and Power Company cc:

Ms. Lillian M. Cuoco, Esq. Office of the Attorney General Senior Nuclear Counsel Commonwealth of Virginia Dominion Nuclear Connecticut, Inc. 900 East Main Street Millstone Power Station Richmond, Virginia 23219 Building 475, 5th Floor Rope Ferry Road Mr. Stephen P. Sarver, Director Rt. 156 Nuclear Licensing & Operations Waterford, Connecticut 06385 Support Innsbrook Technical Center Mr. Richard H. Blount, II Virginia Electric and Power Company Site Vice President 5000 Dominion Blvd.

Surry Power Station Glen Allen, Virginia 23060-6711 Virginia Electric and Power Company 5570 Hog Island Road Mr. David A. Heacock Surry, Virginia 23883-0315 Site Vice President North Anna Power Station Senior Resident Inspector Virginia Electric and Power Company Surry Power Station P. O. Box 402 U. S. Nuclear Regulatory Commission Mineral, Virginia 23117-0402 5850 Hog Island Road Surry, Virginia 23883 Mr. C. Lee Lintecum County Administrator Chairman Louisa County Board of Supervisors of Surry County P.O. Box 160 Surry County Courthouse Louisa, Virginia 23093 Surry, Virginia 23683 Old Dominion Electric Cooperative Dr. W. T. Lough 4201 Dominion Blvd.

Virginia State Corporation Glen Allen, Virginia 23060 Commission Division of Energy Regulation Senior Resident Inspector P. O. Box 1197 North Anna Power Station Richmond, Virginia 23209 U.S. Nuclear Regulatory Commission 1024 Haley Drive Robert B. Strobe, M.D., M.P.H. Mineral, Virginia 23117 State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Mr. William R. Matthews Vice President - Nuclear Operations Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060-6711