ML20029E681

Amend 153 to License DPR-35 Changing TS by Revising Wording for License

ML20029E681
Person / Time
Site:	Pilgrim
Issue date:	05/16/1994
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20029E682	List: ML20029E681 ML20029E690
References
NUDOCS 9405190312
Download: ML20029E681 (6)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001

.....f BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.153 License No. DPR-35 l

1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) dated February 9, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as_ amended (the Act),

and the Commission's rules and regulations; 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; l

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 the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:

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Technical Specifications i

The Technical Specifications contained-in Appendix A, as revised by NRC approved and docketed Amendments, are hereby incorporated in the license.

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The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION E

s Walter R. Butler, Director Project Directorate I-3 j

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l-i

Attachment:

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Changes to the Technical i

Specifications Date of Issuance: fiay 16, 1994 i

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i ATTACHMENT TO LICENSE AMENDMENT N0.153 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technic 11 Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert License Page 3 License Page 3 Appendix A Page 123 Appendix A Page 123 Appendix A Page 137c Appendix A page 137c l

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l B.

. Technical Soecifications The Technical Specifications contained in Appendix A, as revised by NRC approved and docketed Amendments, are hereby incorporated in l j

the license.

The licensee shall. operate the facility in accordance with the Technical Specifications.

i C.

Records i

Boston Edison shall keep facility operating records in accordance with the requirements of.the Technical Specifications.

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D.

Eoualizer Valve Restriction - DELETED E.

Recirculation Looo Inocerable

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The reactor shall not be operated with one recirculation loop out of service for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor operating, if one i

recirculation loop.is out of service, the plant shall be placed in a i

hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is sooner.

l returned to service.

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i Amendment No--148-153 j.

LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.6 PRIMARY SYSTEM B0UNDARY 4.6. PRIMARY SYSTEM B0UNDARY i

ADolicability:

ADDlicabilitV:

i Applies to the operating status of Applies to the periodic examination j

the reactor coolant system.

and testing requirements for the j

reactor cooling system.

Obiective:

Ob.iect ive:

To assure the integrity and safe To determine the condition of the operation of the reactor coolant reactor coolant system and the l

system operation of the safety devices related to it.

Specification:

Specification:

A.

Thermal and Pressurization A.

Thermal and Pressurization Limitations Limitations I

1.

The average rate of reactor 1.

During heatups and cooldowns, i

coolant temperature change with the reactor vessel during normal heatup or temperature less than or equal cooldown shall not exceed to 450 F, the. temperatures at j

100 F/hr when averaged over a the following locations shall one-hour period except when the be permanently logged at least 2

vessel temperatures are above every 15 minutes until the 450 F.

The reactor vessel difference between any two j

flange to adjacent reactor readings at individual vessel shell temperature locations taken over a 45 differential shall not exceed minute period is less than 5 F:

145 F.

a. Reactor vessel shell adjacent to reactor vessel j

flange i

b. Reactor vessel shell flange j

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c. Recirculation loops A and B I

2.

The reactor vessel shall not be 2.

Reactor vessel shell i

pressurized for hydrostatic temperatures, including reactor j

and/or leakage tests, and vessel bottom head, and reactor subcritical or critical core coolant pressure shall be operation shall not be permanently logged at least conducted unless the reactor every 15 minutes whenever the l

vessel temperatures are above shell temperature is below those defined by the 220*F and the reactor vessel is i

appropriate curves on Figures not vented.

3.6.1, 3.6.2, and 3.6.3.

1 (Linear interpolation between Test specimens of the reactor curves is permitted). At vessel base, weld and heat stated pressure, the reactor affected zone metal subjected i

vessel bottom head may be to the highest fluence of maintained at temperatures greater than 1 Mev neutrons

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below those temperatures shall be installed in the corresponding to the adjacent reactor. vessel adjacent to the reactor vessel shell as shown vessel wall at the core in Figures 3.6.1 and 3.6.2.

midplane level. -The specimens and sample program shall j

conform to the Amendment No. 281-825-140, 153 123

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p LIMITING CONDITIONS FOR OPERATION 4.6.I Shock Suporessors (Snuobers)

Specification 4.6.1.2.B or 4.6.1.2.C, as applicable, an additional 10% of-that-type of snubber shall be functionally tested, i

B. General Snubber Functional Test Acceptance Criteria (Hydraulic and Mechanical)

The general snubber functional test shall' verify that:

1. Activation (restraining action) is achieved within l

the specified range of I

velocity or acceleration in both tension and compression.

2. Snubber release, or bleedrate, as applicable, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace.

under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

C. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.

3.

Snubber Service Life Monitorina A. A record of the service life i

l Amendment No.-60T 153 137c

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