ML072190495

Revised Renewed Facility Operating License Pages to Reflect Issue B.5.b

ML072190495
Person / Time
Site:	Monticello
Issue date:	08/23/2007
From:	Tam P NRC/NRR/ADRO/DORL/LPLIII-1
To:
tam P, NRR/ADRO/DORL, 415-1451
References
TAC MD4611
Download: ML072190495 (4)

Text

ENCLOSURE 1 REVISED PAGES OF RENEWED FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NOS. 50-263 MONTICELLO NUCLEAR GENERATING PLANT Replace the following pages of the Renewed Facility Operating Licenses DPR-22. 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 5

5 6

6 7

approval, a program for inspection and/or modification of the recirculation system piping.

8.

Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 110, are hereby incorporated into this license. NMC shall operate the facility in accordance with the Additional Conditions.

9.

Implementation of New and Revised Surveillance Requirements For surveillance requirements that are new in Amendment No. 146, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.

For surveillance requirements that existed prior to Amendment No. 146, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For surveillance requirements that existed prior to amendment No. 146 that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For surveillance requirements that existed prior to Amendment No. 146, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

10.

Removed Details and Requirements Relocated to Other Controlled Documents License Amendment No. 146 authorizes the relocation of certain technical specifications to other licensee-controlled documents.

Implementation of this amendment shall include relocation of these requirements to the specified documents, as described in (1) Section 5.0 of the NRC staffs Safety Evaluation, and (2) Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staffs Safety Evaluation.

11.

Mitigation Strategy License Condition 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 aid fire fighting assets Renewed License No. DPR-22 Revised by letter dated August 23, 2007 3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (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 12.

The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

D.

NMC shall immediately notify the NRC of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.

E.

Northern States Power Company 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.

F.

NMC shall observe such standards and requirements for the protection of the environment as are validly imposed pursuant to authority established under Federal and State law and as determined by the Commission to be applicable to the facility covered by this renewed facility operating license.

G.

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

H.

The Updated Safety Analysis Report supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. NMC shall complete these activities no later than September 8, 2010, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

Renewed License No. DPR-22 Revised by letter dated August 23, 2007 I.

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of the most recent NRC-approved version of the Boiling Water Reactor Vessels and Internals Project (BWRVIP)

Integrated Surveillance Program (ISP) appropriate for the configuration of the specimens in the capsule. 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.

J.

This renewed operating license is effective as of the date of issuance and shall expire at midnight, September 8, 2030.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments: 1. Appendix A - Technical Specifications

2. Appendix B - (Deleted per Amendment 15, 12/17/82)

3. Appendix C - Additional Conditions Date of Issuance: November 08, 2006 Renewed License No. DPR-22 Revised by letter dated August 23, 2007