ML19241B017
| ML19241B017 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/30/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19241A971 | List: |
| References | |
| TASK-04-01.A, TASK-RR NUDOCS 7907110553 | |
| Download: ML19241B017 (5) | |
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f NUCLEAR REGULATORY COMMISSION UNITED STATES h? ;
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SAFETV EULJAT'CN SY ThE CF :CE CF NUCLEAR REACT:R RE3LLATION SLPPCRT:NG 2MENDPE:4T NO. 35 TO LICENSE ?!0.
PR-16
.'ERSEY CENTRAL JCWER & LIGHT CCMP1Ny av.e'1 :n. eg::(
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s CCCXET NO. 50-219
- ntrocuc*1cn jersey Cen:ral ocwer & Lignt Ccmcany's (JCP&L anc the licensee) acclication w y 2a,1979, as succerted oy letters cated Acril 30, May 15 ana 17, catec a
1979, arrnosec certain recuctions in Maximum Average Planar Linear Hea:
3eneraticn Rate (MAPLnGR ) a::alicaole to continued c;:erations of :ne Oyster Creek :~1cility. Since tnese preocsals mocify the "APL.,GR 1imits in :ne f ac111:y Tecnnical Scecifications, they require NRC autncrization to amenc
- ne Tecnnical Specifica:icns. Sucn mccifications alicw c eratico of :ne ::l ant at :n are ecir.ulation loco cut of service using tre more restrictive Maximum verage lanar Linear -ea: 3eneration Rate ("APLHGR ) li-'i ts ( or1;i nal ly sa:ncrizec cy imencment No. 30, catec Marcn lA, 1973), ai:n values extenced ::
enconcass nt;ner ex;osure fuel.
EisCussion 7 e 11Censee i n *0r"lec :ne NRC Sta f f Oy l e *er cated AOril 30, 1973, :"a*.
"e f 3 c i 1 *.y a a s Ce r 3 *.i n g ai " f0ur (1) Of :ne #ive (5j "eac:Or rec t -: a:1cn ::ci an: loc:s in service anc :na: :ne 3:Cravec E:C5 i a 3 ' / : ' s ( i e n c-e n t '40. 33. ca *eu 1:ver'cer 11, 19 3 ) 01 : nc: :0nsicer l
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-elate :0 3 -ecircul ation system mal function need ta se reviewed. The 1;;ensee accressec :nree such events for One five ;ura acar3? ion: 1) ali reci-cul ation pumos *ri;, 2) single recirculat:en ;ume trio anc,
) cuma sei:ure (locxec -otor). Amenemen: No. To to :ne ::SAR accressec eacn af :nese even s snewing :na: :ne five ;umo trip.as more severec nan :ne single cum; trio cut 30;roximately ecual to a ;ume seizure. The
,censee's analysi s of :ne :nree transients crec:ct a cnange in minimum
- riti:ai ;cwer -3:ic (MCFR ) of
.01 for :ne one-of-five cumo stal i anc 3 3 3 enec...., as One : terence Detoeen cre-or-rour anc ane-or-r:. ve cumo s 3!
s.
ese :nanges in "C;R are -el atively mince anen :0nsiceriag
.crs: :ase transients. A steacy state MCPR of 1.52 nas teen estac!: snec sacs.'i: as a resul t o f tce nors: case transient (i.e.,
continucus roc
,i:ncrana, error; :ne resa,i ant enange in,Ces 41,: 1 10: cecrease ce.icw
- -e transient limit of 1.24 As can :e seen oy the licensee's assessment,
- ne resal tan: MC?R, folicwing a :uma seizure event anile in :ne fcur : ump
- ce-a: Onal mcce, noulc ce 1.44 leaving a suostantial margin of 0.1 frcm
- ne transient MCPR limit. Cn tnis cast s, we find nat the lockec rotor even:. nile coerating *itn four recirculation cumes is acuncec Jy tne crevi;uslj reviewed transient analysi s and is. *neref;re, accectacle.
3y l e*:e-Catec Vay 15, 1979, :ne licensee proviced a new set Of VAFLHGR
- arves.
7nese curves extenc ne creviously accr0vec "A?LMGR curves of amenc. ment No. 20 for ni;ner ex;csures.
e'CF &L 's acclication cated ay 21, 1979, recuestec a license amencment to incor: crate One extenceo u
- urves in :ne Tecnnical 5:ecifications.
We nave reviewec :ne newly crocosec
'APL-GR iimits anc nave conclucec :na they are Dasec on calculational e nc]s crevicusly acce :ac; trey co not cnange AAPLnGR limits previcusly er,e 2
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DCCXET NO. 50-219 JERSEY CENTRAL POWER i LIGHT CCMPANf NOTICE CF ISSUANCE CF AMENDMENT 70 PROVISICNAL GPERATING LICENSE The U. S. Nuclear Regulatory Commission ( ne Ccmmission) has is;ued Aaaencment No. 35 to Provisional Cperating License No. CPR-16, issued to Jersey Central Power & Light Company (the licensee), whicn revised tne Tecnnical Specifications for operation of tne Oyster Creek Nuclear Generating Station (the facility) located in Ccean County, New Jersey.
The amencment is effective as of its date of issuance.
The arencment allows aceration with one recirculation,1 cop :7: of service using the more restrictive Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits (originally authorized by Amendment No. 20, dated March la,1978) with values extended to encoccass higher excosure fuel.
In secarate actions relating to this facility, the Commission is:
(1) Amending License Nc. CFR-15 to extend the acplica-bility of the minimum water level safety limit to all mcces :f coeration, anc adc a new safe y limit in Secticn 2.1,F to require tna two recircu-la:4:n 1:ces -emain 0:en during III m: des of Oceraticn excec wi:n -he 4- =. v~/ =.s.,
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7590-01 anc regulations in 10 CFR Chapter I, whicn are su forth in the license amencment.
Orior public nctice of :nis amencmer was not rcuired since
- ne amencment coes not involve a significant hacards consideration.
The Ccomission has determined that the issuance of this amencment will not result in any significant environmental impact and that pursuant :: 10 CR 551.5(d)(4) an environmental impact statement er negative declaration and environmental impact appraisal need not be precared in connection with issuance of tnis amencment.
For furtner de: ails with escect to this action, see (1) the acclication for amend ent dated May 24, 1979, and th licensee's sucait als dated Acril 30, May 15 and 17,1979, (2) Amendment No. 35 to License No. :P -15, anc (3) the Ccmission's related Safety Evaluaticn.
All of :nese items and the Ccmaission's secarate actions described above are availacle for cublic inspection at tne Ccm.isticn's Public Cccuren: Occm, 1717 H Street, N.
W., Washing:ci., D. C.,
and at ne Ccean Scun y Library, Erick Tcwnshio Eranch, '01 Charnbers Bridge Roac, Eri ck ~;wn, New Jersey 03722.
A cocy of items (2) and (3) in acciti:n
- : e sera-ne acticns, may be :c ained =cn recuest ac:ressed :: :. e
- 1. tcI sar Esgul a #y C0f"~i ss on, Wasning! n, 3. C.
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7590-01 Dated at Bethesda, Maryland, this 3Cth day of May, 1979.
FCR THE NUCLEAR RESULAT:RY CCMMISSION
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.x.,, s,,,, 3 Dennis L. Ziemann, Chief Coerating P.eac ces 3rancn =2 Division of Ccerating Reac Ors 478 P-
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