ML063530368
| ML063530368 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/18/2006 |
| From: | Milano P Plant Licensing Branch III-2 |
| To: | Korsnick M Ginna |
| References | |
| TAC MD2229 | |
| Download: ML063530368 (5) | |
Text
- Letter and Enclosure 1: ML063470077 ADAMS Accession No. - Enclosure 2:
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I IIJ 11 t REGO Il UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
.**4 10December 18, 2006 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSE IN CONJUNCTION WITH COMMISSION ORDER EA-06-037 AND REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MD2229)
Dear Mrs. Korsnick:
By letter to the Nuclear Regulatory Commission (NRC) dated May 15, 2006, R.E. Ginna Nuclear Power Plant, LLC (the licensee), submitted its revised security plans and confirmed the full implementation of Order EA-06-037 at R.E. Ginna Nuclear Power Plant (Ginna). Order EA-06-037 provided an update to an 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 Part 73 of Title 10 of the Code of Federal Regulations (10 CFR) 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 Renewed Facility Operating License is required to ensure implementation of the Order EA-06-037 requirements.
Therefore, an administrative license change to Renewed Facility Operating License No.
DPR-18 for Ginna is being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan. The change complies with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the NOTICE: Enclosure 2 contains Security-Related Information. Upon separation from Enclosure 2, this letter and Enclosure I are DECONTROLLED.
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Commission's rules and regulations set forth in 10 CFR Chapter 1. Please replace Page 5 of the Renewed Facility Operating License with the enclosed page (Enclosure 1). Enclosure 2 to this letter is designated exempt from public disclosure under 10 CFR 2.390(d)(1).
If you have any questions, please contact me at (301) 415-1457.
Sincerely, Patrick D. Milano, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
- 1. Revised Page 5 of License
- 2. Safeguards Evaluation cc w/encls 1 and 2: R. Teed, Director, Nuclear Security B. McDermott, Region I Peter R. Smith, President New York State Energy, Research, and Development Authority cc w/encl 1 only: See next page
-. r,.IIAL USE ONLY - SECURi':'
RELATED INFORIIATI--N W4,
R.E. Ginna Nuclear Power Plant cc:
Mr. Michael J. Wallace President R.E. Ginna Nuclear Power Plant, LLC c/o Constellation Energy 750 East Pratt Street Baltimore, MD 21202 Mr. John M. Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401 Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna Nuclear Power Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Carey W. Fleming, Esquire Senior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Defense and security and is otherwise in the public interest. Therefore, the exemption is hereby granted pursuant to 10 CFR 50.12.
E.
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 provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27827 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "R.E. Ginna Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," submitted by letter dated May 15, 2006.
F.
The Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Ginna LLC shall complete these activities no later than September 18, 2009, and shall notify the NRC in writing when implementyation of these ac5tivities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed license. Until that update is complete, Ginna LLC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Ginna LLC evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
G.
All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASME E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.
Amendment No. 84 R"evised by letter dated tober 29, 2004 Revised by letter dated December 18, 2006