ML20112B894
| ML20112B894 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20112B895 | List: |
| References | |
| NUDOCS 8501100660 | |
| Download: ML20112B894 (5) | |
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9 UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION c
WASHINGTON, D. C. 20555
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated September 5, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 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; j
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.
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-66 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendnent is effective on issuance, to be implemented within 30 days of issuance.
F0it THE NUCLE REGULATORY COMMISSION k.
St ven
- arga, Operating Reactors anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 31, 1984
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-47 3/4 3-47 B 3/4 3-3 8 3/4 3-3 a
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FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 As a minimum, the fire detection instrumentation for each fire detection zone shown in Tab'e 3.3-10 shall be OPERABLE:
APPLICABILITY: Whenever equipment in that fire detection zone is equired to be OPERABLE.
ACTION With the number of OPERABLE fire detection instruments less than required by Table 3.3-10:
Within I hour establish a fire watch patrol to inspect the zone (s) a.
with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
b.
Restore the inoperable instrument (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l
pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQU'IREMENTS I
4.3.3.6.1 Each of the abov.e required fire detection instruments which are accessible during plant operations shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire i
detectors which are not accessible during plant operation shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.3.3.6.2 The NFPA Code 72D Class A supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
4.3.3.6.3 The non-supervised circuits between the local panels in Specification 4.3.3.6.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.
l BEAVER VALLEY - UNIT 1 3/4 3-47 Amendment No. 88
INSTRUMENTATION BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation insures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is j
consistent with General Design Criteria 19 of 10 CFR 50.
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3/4.3.3.6 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capabiilty is available for the prompt detection of fires.
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capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility i
l In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols or in-containment air l
temperature monitoring in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
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3/4.3.3.7 CHLORINE DETECTION SYSTEMS t
The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective action in i
the event of an accidental chlorine release. This capability is required to protect control t'oom personnel and is consistent with the recommerdations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.
l 3/4.3.3.8 ACCIDENTMONITORjNGINSTRUMENTATION t
l The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability l
is consistent with the recomendations of Regulatory Guide 1.97, l
" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, i
"TMI-2 Lessons Learned Task Force Status Report and Short-Terni Recommendations."
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l BEAVER VALLEY - UNIT 1 B 3/4 3-3 Amendment No'. 88 l
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