ML031180728
| ML031180728 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/10/2003 |
| From: | Gratton C NRC/NRR/DLPM/LPD2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Gratton C, NRR/DLPM 415-1055 | |
| References | |
| Download: ML031180728 (17) | |
Text
April 10, 2003 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
CORRECTION OF RENEWED FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 FOR NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, AND RENEWED FACILITY OPERATING LICENSE NOS. DPR-32 AND DPR-37 FOR SURRY POWER STATION, UNIT NOS. 1 AND 2
Dear Mr. Christian:
By letter dated March 20, 2003, we issued the Renewed Operating Licenses for the North Anna Power Station (North Anna), Units 1 and 2, and Surry Power Station (Surry), Units 1 and 2. On March 31, 2003, your staff informed the U. S. Nuclear Regulatory Commission (NRC) by facsimile that Appendix A to the Surry, Units 1 and 2, Renewed Operating Licenses contained errors. The NRC staff also identified a typographical error in paragraph 2.C(2) of the North Anna, Units 1 and 2, Renewed Operating Licenses, and paragraph 3.B of the Surry, Units 1 and 2, Renewed Operating Licenses. I have enclosed the corrected pages for the North Anna, Units 1 and 2, Renewed Operating Licenses, the Surry, Units 1 and 2, Renewed Operating Licenses, and an Appendix A, in its entirety, for each Surry Power Station unit.
We regret any inconvenience this may have caused.
Sincerely,
/RA/
Christopher Gratton, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280, 50-281, 50-338, and 50-339
Enclosures:
- 1. Corrected Page for Renewed License No. NPF-4
- 2. Corrected Page for Renewed License No. NPF-7
- 3. Corrected Page for Renewed License No. DPR-32
- 4. Corrected Page for Renewed License No. DPR-37
- 5. Corrected Appendix As for Surry, Units 1 and 2, Renewed Operating Licenses cc w/encls 1 through 4: See next page
April 10, 2003 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
CORRECTION OF RENEWED FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 FOR NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, AND RENEWED FACILITY OPERATING LICENSE NOS. DPR-32 AND DPR-37 FOR SURRY POWER STATION, UNIT NOS. 1 AND 2
Dear Mr. Christian:
By letter dated March 20, 2003, we issued the Renewed Operating Licenses for the North Anna Power Station (North Anna), Units 1 and 2, and Surry Power Station (Surry), Units 1 and 2. On March 31, 2003, your staff informed the U. S. Nuclear Regulatory Commission (NRC) by facsimile that Appendix A to the Surry, Units 1 and 2, Renewed Operating Licenses contained errors. The NRC staff also identified a typographical error in paragraph 2.C(2) of the North Anna, Units 1 and 2, Renewed Operating Licenses, and paragraph 3.B of the Surry, Units 1 and 2, Renewed Operating Licenses. I have enclosed the corrected pages for the North Anna, Units 1 and 2, Renewed Operating Licenses, the Surry, Units 1 and 2, Renewed Operating Licenses, and an Appendix A, in its entirety, for each Surry Power Station unit.
We regret any inconvenience this may have caused.
Sincerely,
/RA/
Christopher Gratton, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280, 50-281, 50-338, and 50-339
Enclosures:
- 1. Corrected Page for Renewed License No. NPF-4
- 2. Corrected Page for Renewed License No. NPF-7
- 3. Corrected Page for Renewed License No. DPR-32
- 4. Corrected Page for Renewed License No. DPR-37
- 5. Corrected Appendix A for Surry Units 1 and 2 Technical Specifications cc w/encls 1 through 4: See next page DISTRIBUTION:
PUBLIC CGratton RLSB R/F (w/encls 1-4)
WBurton (w/encls 1-4)
PDII-1 R/F (w/encls 1-4)
EDunnington (w/encls 1-4)
GHill (4)
Package: ML031150699 Unit 1 Tech Spec: ML031150726, ML031150727 Accession Number: ML031180728 Unit 2 Tech Spec ML031150377, ML031150398 OFFICE PDII-1/PM PDII-2/LA PDII-1/SC NAME CGratton EDunnington JNakoski DATE 4/9/03 4/9/03 4/10/03 OFFICIAL RECORD COPY
ENCLOSURE 1 CORRECTED LICENSE PAGE RENEWED LICENSE NO. NPF-4 (2)
Pursuant to the Act and 10 CFR Part 70, VEPCO to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report; (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or component; and (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level VEPCO is authorized to operate the North Anna Power Station, Unit No. 1, at reactor core power levels not in excess of 2893 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
Renewed License No. NPF-4
ENCLOSURE 2 CORRECTED LICENSE PAGE RENEWED LICENSE NO. NPF-7 (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations as set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level VEPCO is authorized to operate the facility at steady state reactor core power levels not in excess of 2893 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the condition or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission:
a.
If VEPCO plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the Renewed License No. NPF-7
ENCLOSURE 3 CORRECTED LICENSE PAGE RENEWED LICENSE NO. DPR-32 3.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the. rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2546 megawatts (thermal).
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Deleted by Amendment 65 F.
Deleted by Amendment 71 G.
Deleted by Amendment 227 H.
Deleted by Amendment 227 I.
Fire Protection The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19, 1979, (and Supplements dated May 29,
- 1980, October 9,
- 1980, December 18, 1980, February 13, 1981, December 4, 1981, April 27, 1982, November 18, 1982, January 17, 1984, February 25, 1988, and Renewed License No. DPR-32
ENCLOSURE 4 CORRECTED LICENSE PAGE RENEWED LICENSE NO. NPF-37 E.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
3.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2546 megawatts (thermal).
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 232, are hereby incorporated in this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Deleted by Amendment 54 F.
Deleted by Amendment 59 and Amendment 65 G.
Deleted by Amendment 227 H.
Deleted by Amendment 227 Renewed License No. DPR-37
ENCLOSURE 5 CORRECTED APPENDIX A (TECHNICAL SPECIFICATIONS)
FOR SURRY UNITS 1 AND 2
Unit 1 Technical Specifications DPR-32 (this page is not part of Appendix A)
Unit 2 Technical Specifications DPR-37 (this page is not part of Appendix A)
Mr. David A. Christian Virginia Electric and Power Company cc:
Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Millstone Power Station Building 475, 5th Floor Rope Ferry Road Rt. 156 Waterford, Connecticut 06385 Mr. Richard H. Blount, II Site Vice President Surry Power Station Virginia Electric and Power Company 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 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 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Mr. David A. Heacock Site Vice President North Anna Power Station Virginia Electric and Power Company P. O. Box 402 Mineral, Virginia 23117-0402 Mr. C. Lee Lintecum County Administrator Louisa County P.O. Box 160 Louisa, Virginia 23093 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117 Mr. William R. Matthews Vice President - Nuclear Operations Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060-6711