ML20003G506

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Amend 59 to License NPF-1,revising Requirements for Containment Air Lock Testing to Conform to Amended Regulations Contained in 10CFR50,App J
ML20003G506
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 04/16/1981
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20003G505 List:
References
NUDOCS 8104290723
Download: ML20003G506 (4)


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NUCLEAR REGULATORY COMMISSION

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAP. PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-1 The Nuclear Regulatory Commission (the Commission) has found that:

1.

The application for amendment by Jortland General Electric Company, A.

the City of Eugene, Oregon, and Pacific Power and Light Conpany (the licensee) dated March 16, 1981, complies with the stendards 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; The facility will operate in confonnity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) chat the activities authorized C.

by this amendment can be conducted withat.t endangering the health and safety of the pubite, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the publi ;

ar.d The issuance of this amendment is in accordance with 10 CFR Part E.

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

810.4290773 l

2-2.

Acccedingly, the license is ar. ended by enanges to the Tecnnical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications Tne Technical Specifications contained in Appendices A and B, as.evised tnrough Amendment No. 59, are hereby incorporf ted in the license. The licensee snall cperate the f acility in accordance with the Technical Specifications, except as noted in paragraphs 2.C.(10) through 2.C.(12) below.

3.

This license amencment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSICN j

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Robert A. Clark, Chief Operating Reactors Branch 43 Division of, Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: April 16, 1981

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 6-5 3/4 6-5 4

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CCNTAINMENT SYSTEMS l

CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION I

3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for nonnal transit entry and exit through the containment, then at

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least cne air lock door shall be closed, and I

b.

An overall air lock leakage rate of <0.05 La at Pa, (60 psig).

APPLICABILITY: MCOES 1, 2, 3 and 4.

ACTION:

With an air lock inoperable, restore the air lock to CPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CCLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REOUIREMENTS I

4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:*

l a.

At least once within 3 days after opening by verifying the l

seal leakage is <0.01 La as detemined by precision flow t

measurement when measured for at least 30 seconds with the volume between the seals at a constant pressure of 10.0 psig.

b.

At least once per 6 months by conducting an overall air lock leakage test at Pa (60 psig) and by verifying that the overall air lock leakage rate is within its limit, and At least once per 6 months by verifying that only one door in c.

each air lock can be opened at a time.

Air locks opened during periods when containment integrity is not required shall be tested at the end of such periods at not less than Pa (60 psig) (10 CFR 50, App. J,Section III.D.2.(b)(ii)).

TROJAN-UNIT 1 3/4 6-5 Amendment tio. 59 l

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