ML20134L134
| ML20134L134 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  (NPF-003) |
| Issue date: | 08/22/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20134L137 | List: |
| References | |
| NPF-03-A-087 NUDOCS 8509030077 | |
| Download: ML20134L134 (5) | |
Text
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UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION 3
y WASHINGTOid, D. C. 20555 e
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TOLED0 EDISON COMPANY
- AND, THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No. 87 License No. NPF-3 The N' clear Regulatory Comission (the Comission) has found that:
1.
u A.
The application for amendment by the Toledo Edison Company)and The Cleveland Electric Illuminating Company (the licensees dated September 17, 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 (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 Comission's regulations; 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 Comission's regulations and all applicable requirements have 4
been satisfied.
2.
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. NPF-3 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. 87, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g -~
o F. Stolz, Chie 0 rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 22, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
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ACMINISTRATIVE CONTROLS power coeration), supplementary reports shall be submitted at least every three months until all three events have been completed.
E AtmUAL OPEF.ATING REPORT 6.9.1.4 Annual reports covering the activities of the unit during the revious calendar year shall be submitted prior to March 31 of each year.
The initial recort shall be submitted prior to March 1 of the year following initial criticality.
5.9.1.5 Re: rts recuired on an annual basis shall include:
a.
. A tabulation on an annual basis of the number of sta:ien, utility and c:her personnel (including c:ntract:rs) receiving rem ex::sure acc:rding to work and job functicns,fjated man ex::sures creater than 100 mrem /yr and their assoc e.g.,
reac:Or operations and surveillance, inservice inspection, reutine maintenance, special maintenance (describe main:enance),
waste processing, and refueling.
The dose assienment Oc varicus duty functions may be estimates based on cocke desimeter, TLD, or film badge measurements.
Small ex::sures
- alling less than 200 cf the individual total d:se need ne: be ace unted for.
In the ag:regate, at leas: 500 cf the t::al whole bcdy dese received fr = external sources shall be assigned to specific major werk functions.
b.
The ccm:lete results of steam generator tube inservice inspections (50,ecification 4'.4'.5.'5.b).
MCNTHLY GPEF.; TING REFORT 6.9.1.6 Routine reports of operating statistics, shutdown experience and chal-lenges to the Pressurizer Power Operated Relief Valve (PORV) and the Pressurizer Code Safety Valves shall be submitted on a monthly basis to the Director, Office of tianagement and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.
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A s ngie submittal may be made for a multiple unit statien.
The submit:a1 shculd ccmbine those sections that are c:m:n to all units at the station, li
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This tabulation supplements the recuirements of.120.a07 of 10 CFR Part 20.
l DAVIS-5E55E, UNIT 1. -
6-15 Amendment ?!o..AW,/Q2,7f, 87
ADMINISTRATIVE CONTROLS
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5. 9.1. 7 including c:rrective acticns and measures to prevent rec be reported c the NRC.
Sup'plemental re describe final resolutien of occurrence. ports may be required t: fully In case of corrected :r su:;iemental reports, a licensee event report shall be cc ple:ed and reference shall be =ade to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 5.9.1.3 The types of events listed below shall be reported within 2a hours by telephcne and c:nfirmed by telegraph, mailgram, or facsimile transmissi:n :: the Direc cr of the Regional Office, or his desi nz:e latar than the first working day felicwing the event, with a Eritten
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fellowup rep:r within two weeks.
The written follewup racert shall include, as a minimum, a c:=pleted copy.cf a licensee event rep:rt f:nn.
Inicrmatica provided on the licensee event report f:rm shall be sup:le-i mer.:ed, as needed, by additional narrative material to provide ::: pie:e expianati:n ci the circumstances surr:unding the even:.
Failure of the react:r protectica syste er ::her systars a.
subjec: to limiting safety system settings :: initia:a tne required protective fun:tien by the time a :: nit: red : ara-meter reaches the se:p;in: specified as the limiting safe y system se::ing in the technical specifica icns er failure c: piete the required pr:tective fun: tion.
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5.
0: era icn cf the unit or affected systems when any parameter er ::erati n subje:: :
a limiting ::ndi:icn fer c:eratien is less c:nservative than the least c:nservative aspect of the limiting c:nditien fer Operatien established in the technical s peci fi cations.
Abner:a1 degradatien dis::vered in fuel cladding, reac::r c.
c::lant pressure b:undary, er primary c:ntainment.
d.
Reactivity ane alies inve*1ving disagreement with the predicted value of reactivity balance under steady state conditions du' ring p:wer operation greater than er equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifica-tiens; short.-ten reactivity increases that correspond to a reae::r period of less than 5 sec:nds cr, if suberitical, an unplanned reactivity insertion of =cre than 0.5t Ak/k; er occurrence of any unplanned criticality.
DAVIS-$ ESSE, UNIT 1 6-16 Amendment No. f,12l
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