ML20045F874
| ML20045F874 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/29/1993 |
| From: | Bill Dean Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045F875 | List: |
| References | |
| NUDOCS 9307090119 | |
| Download: ML20045F874 (4) | |
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UNITED STATES j
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Ij NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 gv f NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACllITY OPERATING LICENSE Amendment No. 85 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated December 31, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of i
the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows 9307090119 930629 PDR ADOCK 05000263 P
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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 85 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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[L William M. Dean, Acting Director Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications g
Date of Issuance: June 29, 1993 f
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I ATTACHMENT TO LICENSE AMENDMENT NO. 85 i
FACILITY OPERATING LICENSE NQ, DPR-22 DOCKET N0. 50-263 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 225 225 t
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 2.
It is permissible to have one of the pumps Every three months verify that a sample e.
required by Specification 3.13.B.1.a of fuel from the diesel oil storage inoperable provided that the redundant pumps tank, obtained in accordance with ASTM are operable.
Restore the inoperabic pump to D4057-88, is within the acceptable operable status within seven days or provide a limits specified in Table 1 of ASTM special report to the Commission within 30 D975-91 when checked for viscosity, days outlining the plans and procedures to be water, and sediment, used to provide for the loss of redundancy in the Fire Suppression Water system.
f.
Every 18 months subject the diesel-driven fire pump engine to an inspection 3.
With the fire suppression water system other-in accordance with procedures prepared wise inoperable.
in conjunction with the manufacturer's recommendations for this class of a.
Establish a backup fire Suppression Water standby service.
System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
g.
A simulated automatic actuation of each b.
Provide a special report to the fire pump and the screen wash / fire pump, Commission within 14 days outlining the including verification of pump actions taken and the plans and schedule capability, shall be conducted every 18 for restoring the system to operable months.
- status, h.
The yard main and the reactor building and turbine building headers shall be flushed every 12 months.
1.
System flow tests shall be performed every three years.
J.
Valves in flow paths supplying fire suppression water to safety related 2
structures, systems, and component shall
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be cycled every 12 months.
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