ML072140606

Revised Pages of Facility Operating License DPR-16

ML072140606
Person / Time
Site:	Oyster Creek
Issue date:	08/09/2007
From:	Murley T Office of Nuclear Reactor Regulation
To:
Miller, G. Edward, 415-2481
Shared Package
ML072180011	List: ML072140606 ML072180014
References
TAC MD4510
Download: ML072140606 (3)

Text

ENCLOSURE 1 REVISED PAGES OF FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION Replace the following pages of Facility Operating License No. DPR-16 with the attached revised pages. The revised pages are identified by the date of the letter issuing these pages and contain marginal lines indicating the areas of change.

Remove Insert Page 4 Page 4 Page 5 Page 5

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) AmerGen Energy Company, LLC, 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 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: Oyster Creek Nuclear Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5. The set contains Safeguards Information protected under 10 CFR 73.21.

(5) Inspections of core spray spargers, piping and associated components will be performed un accordance with BWRVIP-18, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines, as approved by NRC staffs Final Safety Evaluation Report dated December 2, 1999.

(6) Long Range Planning Program - Deleted (7) Reactor Vessel Integrated Surveillance Program AmerGen Energy Company, LLC, is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel Integrated Surveillance Program as the basis for demonstrating compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50, Reactor Vessel Material Surveillance Program Requirements, as set forth in the licensees application dated December 20, 2002, and as supplemented on May 30, September 10, and November 3, 2003.

(8) Mitigation Strategy License Condition l l

Develop and maintain strategies for addressing large fires and explosions and l that include the following key areas: l l

(a) Fire fighting response strategy with the following elements: l

1. Pre-defined coordinated fire response strategy and guidance l

2. Assessment of mutual aid fire fighting assets l

3. Designated staging areas for equipment and materials l

4. Command and control l

5. Training of response personnel l 1

The Training and Qualification Plan and Safeguards Contingency Plan are Appendicies to the Security Plan.

Amendment No. 173, 217, 242, 244 Revised by letter dated October 28, 2004 Corrected by letter dated 11/19/04 Revised by letter dated February 6, 2007 Revised by letter dated August 9, 2007

l (b) Operations to mitigate fuel damage considering the following: l

1. Protection and use of personnel assets l

2. Communications l

3. Minimizing fire spread l

4. Procedures for implementing integrated fire response strategy l

5. Identification of readily-available pre-staged equipment l

6. Training on integrated fire response strategy l

7. Spent fuel pool mitigation measures l l

(c) Actions to minimize release to include consideration of: l

1. Water spray scrubbing l

2. Dose to onsite responders l l

(9) The licensee shall implement and maintain all Actions required by Attachment 2 l to NRC Order EA-06-137, issued June 20, 2006, except the last action that l requires incorporation of the strategies into the site security plan, contingency l plan, emergency plan and/or guard training and qualification plan, as l appropriate. l D. The facility has been granted certain exemptions from the requirements of Section III.G of Appendix R of 10 CFR Part 50, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979.

This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire damage. These exemptions were granted and sent to the licensee in letters dated March 24, 1986 and June 25, 1990.

The facility has also been granted certain exemptions from the requirements of Section III.J of Appendix R to 10 CFR Part 50, Fire Protection Program for nuclear Power Facilities Operating Prior to January 1, 1979. This section relates to emergency lighting that shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto. This exemption was granted and sent to the licensee in a letter dated February 12, 1990.

In addition, the facility has be granted certain exemptions from Section 55.45(b)(2)(iii) and (iv) of 10 CFR Part 55, Operators Licenses. These sections contain requirements related to site-specific simulator certification and require that operating tests will not be administered on other than a certified or an approved simulation facility after May 26, 1991. These exemptions were granted and sent to the licensee in a letter dated March 25, 1991.

These exemptions granted pursuant to 10 CFR 50.12 are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. Deleted Amendment No. 242, 258 Revised by letter dated August 9, 2007