ML071350404
| ML071350404 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/29/2007 |
| From: | John Hughey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Christian D Dominion Nuclear Connecticut |
| Miller G, NRR/DORL, 415-2481 | |
| Shared Package | |
| ml071350320 | List: |
| References | |
| TAC MD2244, TAC MD2245, EA-06-037 | |
| Download: ML071350404 (6) | |
Text
REGJI-.,OFFICIAL UCE9&
ONY ECRI;h' RELAT-ED NF6RM*ATI6N UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 29, 2007 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut Innsbrook Technical Center 5000 Dominion Boulevard Glenn Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 1, 2 AND 3 - ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSE IN CONJUNCTION WITH THE COMMISSION ORDER EA-06-037 AND REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NOS. MD2244 AND MD2245)
Dear Mr. Christian:
By letter to the Nuclear Regulatory Commission (NRC) dated May 15, 2006, Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted its revised plans and confirmed the full implementation at the Millstone Power Station (MPS) 1, 2, 3, and ISFSI of Order EA-06-037 regarding an updated adversary characteristic in the design basis threat.
The NRC staff has completed its review of the changes related to implementation of Order EA-06-037. As discussed in the enclosed safeguards evaluation (Enclosure 2), the NRC staff has determined that the licensee's changes to the security plans meet the requirements of the NRC Order and Title 10 of the Code of Federal Regulations (10 CFR) Part 73 requirements and are, therefore, acceptable. The effectiveness of these security provisions will continue to be the subject of NRC review and inspection.
Consistent with the Order, a conforming administrative change to the Facility Operating License is required to ensure implementation of Order EA-06-037 requirements.
NOTICE: Enclosure 2 contains Security-Related Information. Upon separation from Enclosure 2, this letter and Enclosure I are DECONTROLLED.
OFFiCIAL USE OL, -
LEECURIT'-R,,EL;TED.... F.RMAT....
D. Christian OFF2ICAL U"SE "NI" 6E114F R."bffET
,",:RMT.'e '"P"""/'/jf Therefore, an administrative license change to Facility Operating License (FOL) Nos. DPR-65 and NPF-49 is being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan required by the Order.
These changes comply with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the Commission's rules and regulations set forth in 10 CFR Chapter I.
Please replace page 4 of FOL No. DPR-65 (MPS2) and page 6 of FOL No. NPF-49 (MPS3)
(Enclosure 1). Enclosure 2 to this letter is being withheld from public disclosure pursuant to 10 CFR 2.390(d)(1).
If you have any questions, please contact me at (301) 415-3204.
Sincerely, John Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-263 and 50-423
Enclosures:
- 2. Safeguards Evaluation cc w/encls 1 and 2: Jeffrey S. Campbell, Manager Nuclear Protection Services Millstone Power Station Rope Ferry Road (Route 156)
Waterford, CT 06385 Raymond J. Powell, Chief Branch 5, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 cc w/encl 1 only: See next page O)FFICIAL= USE EQI='1
- ZEeWRT'.-REbk-TE5 2FRMvAf gE31
Millstone Power Station, Unit Nos. 2 and 3 cc: wlo encl. 2 Lillian M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
Building 475, 5"' Floor Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Charles Brinkman, Director Washington Operations Nuclear Services Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Mr. Joseph Roy Director of Operations Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. David W. Dodson Licensing Supervisor Dominion Nuclear Connecticut, Inc.
Building 475, 5' Floor Roper Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Building 475, 5= Floor Rope Ferry Road Waterford, CT 06385 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. J. W. UBill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 (3)
Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report and as approved in the SER dated September 19, 1978, and supplements dated October 21, 1980, November 11, 1981, October 31, 1985, April 15, 1986, January 15, 1987, April 29, 1988, July 17, 1990, and November 3, 1995, subject to the following provision:
The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(4).
Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, submitted by letter dated October 15, 2004, as supplemented by letter dated May 15, 2006, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 0" The set contains Safeguards Information protected under 10 CFR 73.21.
(5)
Relocated Technical Specifications The licensee shall relocate certain technical specification requirements to licensee-controlled documents as descried below. The location of these requirements shall be retained by the licensee.
- a.
This license condition approves the relocation of certain technical specification requirements to licensee-controlled documents (Technical Requirements Manual), as described in the licensee's application dated May 20, 1997, as supplemented on September 23, 1997. The approval is documented in the staff's safety evaluation dated November 19, 1997. This license condition is effective as of its date of issuance by Amendment No. 210 and shall be implemented 90 days from the date of issuance.
Implementation shall include the relocation of technical specification requirements to the appropriate licensee-controlled document as identified in the licensee's application dated May 20, 1997, as supplemented on September 23, 1997.
Renewed License No. DPR-65 Revised by letter dated May 29, 2007
revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, submitted by letter dated October 15, 2004, as supplemented by letter dated May 15, 2006, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 0" The set contains Safeguards Information protected under 10 CFR 73.21.
F.
Deleted.
G.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
Fire Protection (Section 9.5.1, SER, SSER 2, SSER 4, SSER 5)
DNC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER (NUREG-1031) issued July 1985 and Supplements Nos. 2, 4, and 5 issued September 1985, November 1985, and January 1986, respectively, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
This renewed operating license is effective as of its date of issuance and shall expire at midnight on November 25, 2045.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Appendix A - Technical Specifications
- 2. Appendix B - Environmental Protection Plan Date of Issuance November 28, 2005 Renewed License No. NPF-49 Revised by letter dated May 29, 2007 Amendment No. 234