ML20079G717
| ML20079G717 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/12/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20079G719 | List: |
| References | |
| NPF-03-A-065 NUDOCS 8401230040 | |
| Download: ML20079G717 (6) | |
Text
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THE TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY
_ DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT N0.1 AMENDMENT TO FACILITY OPERATING LICENSE Amndment No.65 License No. NPF.3
- 1. The Nuclear Regulatory Cosmission (the Cosmission) has found that A.
The application for amendment by The Toledo. Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated July 10,1981, 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; 3.
The facility will operate in conformity with the application, the pmvisions of the Act, and the rules and regulations of the Ccanission; C.
There is reasonable assurance (i) that the activities authorized by this aandment tan be condQcted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cocaliance with the Comission's regulations; D.
The issuance of this amendment will not ba inimical to the comon defense and. security or to the health and safety of the public; and-E. 'The issuance of this amndment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8401230040 840112 PDR ADOCK 05000 P
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'.es 2.
Accordingly, Facility Operating License No. NPF '3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachrent to this license amendment:
Revise paragraph 2.C.(2) to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 65. are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION 1
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John >F.
St Iz, Chief 0 'erating Reactors ch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of issuance: January 12, 1984 h
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, e, ATTACHMENT TO LICENSE AENDMENT NO. 65 FACILITY OPERATING LICENSE NO. HPF-3 DOCKET NO. 50-346 Replace the following pages of. the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also'provided to mair.tain document completeness.
Page 3/4 7-47 6-18
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PLANT'SYSTEF.5 3/4.7.10 FIRE BARRIER PENETRATIONS
, v, LIMITING CONDITION FOR OPERATION 3.7.}o All fire barrier panetrations (including cable penetration barrieri,,
fife'onors and fire dampers) in. fire zone boundaries protecting safety related areas shall be functional.
I APPLICABILITY: At all times.
ACTION:
With one or more of the above required fire barrier penetrations a.
non-functional,.within one hour either, est:blish a continuous fire watch on at least one side of the.affected penetration, or verify the OPERABILITY of fire detect.::rs on at least one side of the non-functional. fire. barrier and esta:iTish an ' hourly fire watch patrol.,
Restore the non-functional fire barrier. penetration (s) to functional status within 7 days cc, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Co::::::i.sion pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional pene-tration and pians and scheduie for restoring the fire barrier penetration (s) to functional status.
The p.ovisions of SpeciYications 3.0.3 and 3.0.4 are not applicable.
b.
!5t!RVEILLANCE REOUIP.EMENTS I,'4.7.10 The above required penetration fire barriers shall be verified
- o ce functional:
a.
. At least once per 18 months by a visual inspection.
- b.
- Prior to. returning a penetration fire barrier to functional' status foliowing repairs or maintentace by performance of a visual inspection,of tne arrected pen.=tration fire barrier (s).
.l CAYIS-5E55E, UNIT 1 ~
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3/4 7-47 Amendnent No, h65-l
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'ADMfNISTRATIVE CONTR0!.S Failure or. malfunction of one or more components which prevents e.
or could prevent. by itself,'the fulfillment of the functional requirements o' system (s) used to cope with accidents analyzed in the SAR.
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- f.. Personne1 error or'procedura14nadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems required to 'copeswith-accidents analyzed in the SAR.
g.
Condittoris arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systams, or other protactive measures required by technical specifications.
h.
Errors discovered in.the transient-or accident analyses or in the methods used for such anilyses.as describsd in-the safety analysis report or in the bases for the technical specifications that have or could have pemitted reactor operation in a manner 1ess conservative:than assumed in the ana1yses.
1.
Pirfomance of structures, systems or components that requiras remedial action or corrective measures to prevent opera:1cn in :a canner less conservative than assumed in tae accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during plant life of conditions not scecifically considerod in the safety analysis report or recnnical specifications tnat require remedial action or cor-rective measures to prevent the existence or development of an unsafe condition.
THIRTY DAY WEITTEN rep 0RTS
- 5. 5.1.9 The tyres of events 11sted below shall be the subject of written re;crts to the Director of the Regional Office within thirty days of oc:urrence of inc event. The written report shall include, as a minimum, a completed copy of a licensee event report fem. Infor=ation provided on the licensee event re:: ort fem shall be supplemented, as needed, by additional narrative material to provide complete explanation of tne circumstances surrounding the event.
a.
Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent -the fulfillment of the fun:tional requirements of affected systems.
Amendment No.XJP, 54 DAVIS-3 ESSE, UNIT 1 6-17
' Routine surveillance testing, instrument colibration, or preventive l
maintenance which require system configurations as described in Section c.9.1.9.a and 6.9.1.9.b need not be reported except where test results tnemselves reveal a degraded condition requiring corrective action.
l ADefiNISTRATIVE CDhTROLS
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h.
Conditions leading to operation.in a degraded mde pemitted by a limiting condition for operation or plant shutdown n-quired by a limiting condttion'for op' ration.
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- c. ' Observed inadequa:izt in the imp 1meritation of assinistrative or procedural controls which threaten to cause redu: tion of degree of redundancy provided in rea: tor protection systems cr engineend safety feature.systas.
d.
Abnomal degradation of systes other than those spe:ffied in 6.9.1.B.c above d= signed to contain r:dioactive material resulting frm-the' fission yrm.-
. SPECIAL REPORTS-6.9.2 Special nport:.shall be submitted to the Director of Se Office of Inspection.and Enforement Regional Office within :the time period spe:1fied 1or each r_ port. These reports shall be subaf tted cover:ing the activities identified.below pursuant to the requiremer.ts.cf the.ap -
plicable reference specification:
a.
ECCS A:tuation, Spe:tfications 3.5.2 and 3 3.3.
b.
I=cerable Seismi: P.: niter 1ng In :rw.:stien, spe:1fi=tien 3.3.3.3.
Incperable Mete:rological P.:nt aring Inst =:entati:n, spe:tff.
cation 3.3.3.4.
Seis=iceventanalysis,5pe:1fic:ti:n 4.3.2.3.2.
d.
e.
Fire.Dete: tion Ins. antation, Spe:1fi::stion.3.3.3.3.
f.
Fire Sup;iression Sys--s, Specificaticas 3.7.B.1 and 3.7.3.2.
g.
Fire Barrier Penetrations, Scecification 3.7.10 E.10 EECORD RETINTION 5.10.1 The following re::rds shall be retained f:r at least five year::
a.
Re=rds and legs of Ta:flity operation covering time interval at es:h. power level.
h.
Re=rds and legs.of principal maintenance.activtties, insce: tion:,
repair and replacment of. prin:1 pal.ite=s cf equi;r.ent related to nuclear. safety.
c.
ALL'REFORTABLE CC:URFSICES suinttted to the Ca=issicn.
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d.
Records of surveillance activities, insce:tions and calibrations re= sired by these' Technical.3,ce:fficati=ns.
. DAY U-E e, UNIT 1 6-13 heerimnt.No. 9.JZ. 65 I
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