ML071980002

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Revised Pages of Renewed Facility Operating License No. DPR-65 and No. NPF-49
ML071980002
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 07/18/2007
From:
NRC/NRR/ADRO/DORL/LPLI-2
To:
Nelson D NSSP 415-2720
Shared Package
ML071970004 List:
References
EA-02-026, TAC MD4544, TAC MD4545
Download: ML071980002 (6)
v • d • e


Text

ENCLOSURE 1 REVISED PAGES OF RENEWED FACILITY OPERATING LICENSE NOS. DPR-65 AND NPF-49 DOCKET NOS. 50-336 AND 50-423 MILLSTONE POWER STATION, UNIT NOS. 2 AN[) 3 Replace the following pages of the Facility Operating Licenses. 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 License DPR-65 License DPR-65 Page 6 Page 6 Page 7 License NPF-49 License NPF-49 Page 5 Page 5 Page 6 Page 6 Page 7

(9) DNC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the MPS Unit No. 2 license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

(10) The Final Safety Analysis Report (FSAR) supplement, as revised, submitted pursuant to 10 CFR 54.21 (d), shall be included in the next scheduled update to the FSAR required by 10 CFR 50.71 (e)(4) following the issuance of this renewed operating license. Until that update is complete, DNC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that DNC evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(11) The FSAR supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. DNC shall complete these activities no later than July 31, 2015, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(12) All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) 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. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.

(13) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

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

1. Pre-defined coordinated fire response strategy and guidance
2. Assessment of mutual aide fire fighting assets
3. Designated staging areas for equipment and materials
4. Command and control
5. Training of response personnel Renewed License No. DPR-65 Revised by letter dated July 18, 2007

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

1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders D. This renewed operating license is effective as of its date of issuance and shall expire at midnight July 31, 2035.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

J. E. Dyer, Director Office of Nuclear Reactor Regulation

Attachment:

1. Appendix A - Technical Specifications Date of Issuance: November 28, 2005 Renewed License No. DPR-65 Revised by letter dated July 18, 2007

(e) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trusts shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.

(6) DNC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the MPS Unit No. 3 license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

(7) The Final Safety Analysis Report (FSAR) supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be included in the next scheduled update to the FSAR required by 10 CFR 50.71 (e)(4) following the issuance of this renewed operating license. Until that update is complete, DNC may, make changes to the programs and activities described in the supplement without prior Commission approval, provided that DNC evaluates such changes pursuant to the crileria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(8) The FSAR supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. DNC shall complete these activities no later than November 25, 2025, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(9) All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) 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. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.

(10) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

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

1. Pre-defined coordinated fire response strategy and guidance
2. Assessment of mutual aide fire fighting assets
3. Designated staging areas for equipment and materials
4. Command and control
5. Training of response personnel Renewed License No. NPF-49 Revised by letter dated July 18, 2007

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

1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders D. Exemptions from certain requirements of Appendix J to 10 CFR Part 50 (Section 6.2.6, SSER 4) and from a portion of the requirements of General Design Criterion 4 (Section 3.9.3.1, SSER 4) of Appendix A to 10 CFR Part 50 have previously been granted. See Safety Evaluation Report Supplement 4, November 1985. 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. 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 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 suppliemented 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.

Renewed License No. NPF-49 Revised by letter dated July 18, 2007

H. Fire Protection (Section 9.5.1, SER, SSER 2, SSER 4, SSEIR 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.

I. 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 Amendment No. 234 Renewed License No. NPF-49
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