Text

Amend 82 to License DPR-66,revising Tech Specs to Allow Plant Operation W/One Airlock Door Inoperable Under Certain Conditions
	ML20099H694
Person / Time
Site:	Beaver Valley
Issue date:	11/08/1984
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20099H696	List: ML20099H694; ML20099H706;
References
	NUDOCS 8411280262
	Download: ML20099H694 (6)
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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION

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j WASHINGTON. D. C. 20555 y m,/

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DUQUESNE LIGHT COMPANY

.c OHIO EDISON COMPANY pef 4NSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE..

hiendmentNo.82

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License No. DPR-66 1.

The Nuclear Regulatory Comission (the Connission) has found that:

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The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated July 14, 1983 and May 7, 1984 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 -end 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 activit'ies will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as follows:

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4 2-(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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This amendment is effective on issuance, to be implemented no later than 30 days after issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION L!L A,

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Jchi a,1 feven A.'Varg, Ch Operating Reactors h #1 Division of Licensing

Attachment:

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Changes to the Technical Specifications 4

Date of Issuance:

November 8, 1984 ITT

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a ATTACHMENT TO LICENSE AMEN 0 MENT AMEN 0 MENT NO. 82 TO FACILITY OPERATING LICENSE-NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

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

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3/4 6-10 3/4 6-10 e

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CONTAINMEIT SYSTIMS j

l CCNTAINMCIT AI2 LCCIS LIMITTNG CC!:1JI*ICH ?OR CPERATICN 3.6.1.3

,Each conta1z: ment air lock shall be OPERABLE with:

a.

3cch doors closed except when the air lack is being used for normal transit entry and exit through the containment.- then at laast one air lock door shall be closed, and b.

An overall air lock laakage rate of less than or equal to 0.05 L, at P,(38.3 peig).

1 APPLICABILITY: lCDES 1, 2, 3 and 4.

i ACTICN:

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a.

With one conemin= ant air _ lock door inoperable:

1.

Maint the associated OPER&BLE air lock door closed and either restore thrassociated inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the associated CPE2ABIX dit lock door closed.

2.

Operation say then continue until performance of the next required overall air lock leakage test provided that the associated OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SEITIDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4 The provisions of Specification 3.0.4 are not applicable.

b.

With a containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status l

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least ROT STANDBY within the next

6. hours and in COLD 4HUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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SEAVER VALLEY - CIIT 1 3/4 6-5 Amendnent No. 32 l

03FDLDMENT SYSMS SGMEILTANCE REQUIREM!NTS 4.6.1.3 Each cxz?=4W air lock shall be demonstrated CPERABLE:

a.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months folicwing each cxzttainnent entry, except when the. air' lock is being used for multiple entries, than at least cmca per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying no d.wLdde seal leakage when the gap between the door seals is r--9 Mad for at least 2 minutes to:

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Perstenal airlockM8.3 psig 2.

b e i air lock 210.0 psig ar, by=='*4W the total air lock Imakage to insure the

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5 of 3.6.1.3.h are not.

b.

At least once per 6 months by conducting an overall air lock l

overall air lock. iea(kage r. ate is within its limit.. and38.3 psig) and by ve leakage test at P

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c.

At least ax:e per 18 nenths during shutdown by verifying:

1.

Only cne door in each air Icek can in opened at a time, ant 2.

No detectable seal leakage when the voluna betmen the energency air lock shaft seals is pressurized to greater than or equal to 38.3 psig for at least 2 m2.nutes.

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2e pronsions of ymmcicm 4.0.2 are not applicable.

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83NER VALLEY LWIT 1 3/4 6-Sa Amendment No. 82 9

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CONTAINNENT SYSTDis i

CCNTAINMENT STRUCTURAL I:ffECRITY LDfITIiG CONDI IONS FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained, at a level consistent with the acceptanca criteria in Specificatica 4.6.ls6.1.

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APPLICABLI'"T:.TDES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming, to the above requiremmats, restore the structural integrity to within the limits prior to increasing' the Reactor Coolant System temperature above 200*T.

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$UITEIIIANCE iisuuuiisam5 i

4.6.1.6.1 Liner Plate and Concrete Tha-structural integrity of the co=*=+a==at 11anz plate and concreta shall be determined daring the shutdown for each Type A containment lankaga~ rate test. (reference Specification 4.6.1.2) by:

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a visual inspectiion of the, accessihie surfaces and. verifying no

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apparent changes in. appea_rsace or other abnormal degradation.

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b.

a visual inspectica of _agessihie containment liner test channels prior to each Type A containmaat leakage rate test. Any contain-seat Liner test eh===af which is found to be damaged. to the estaat that eh====1 integrity is impaired or which is discovered with a vest plus removed, shall be removed and a protective coating shall be applied to the liner in that area.

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c.

a visual inspectica of the does area prior to each Type A contain-anat leakage rate test to insure the integrity of the protective coating. If a loss of integrity of the protective coating is observed, any vent plug to a test channel which any be in the ares where. the protective c: sting has failed shall. be seal velded and then the protective coating shall be repaired.

C 4.6.1.6.1 Reports An initial report of any abnormal degradation of the

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containmact structure detected during the above required tests and inspecticus shall be ande-within 10 days af ter completica of the surveil-i lance requireuests of this specification, and the detailed report shall l

be submitted pursuant to Specificatica 6.9.1 within 90 days af ter complation. This report shall include a description of the conditica of the liner plate and concrete, the inspection procedure, the tolerances

,7 on cracking and the corrective actions taken.

SEA 7EE VALLET - UNIT 1 3/4 6-10 Amendment No. 82 l

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ML20099H694

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