ML20114F221
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t UNITED STATES -
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ATOMIC ENERGY COMMISSION
[ $) la l WASHINGTON o,C. 20$45 O
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me Peter A. Morris, Director, Division of Reactor Licensing g -Q/f JERSEY CENTRAL POWER AND LIGHT COMPANY (0YSTER CREEK) - DOCKET NO. N The enclored TWX report from our Region I (Newark) office is forwarded for information and for action.
Based on the information presented in previous-inspection reports, and the enclosed TWX report,-it is - recommended that-a limited Provisional' Operating License be issued for the Oyster Creek facility. The limiting
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condition should~ prohibit reactor operation at significant power and should remain in effect until the acceptability for nuclear service of important pipes, fittings, and valves has been substantiated.
.O e-R.
. Engelken, Ao istant Director (d L M Inspectiol "nforcement
& Divisica of. Compliance E1 closure:
': 'X report ecv/ encl:
C. K. Beck, DR M. M. Mar 4n, DR
,R. L. Doan, DR E. G. Case, DRS R. S. Boyd, DEL S. Levine, DRL' D. J. Skovholt, DRL-L. Kornblith, Jr., CO '
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R. L. Tedesco, DRL R.W. Kirkman,CO:I,v/oenel J. G. Davis, CO:II B. H. Grier, 00:III D. I. Valker, CO:IV R. W. Smith, CO:V REG Central File 9210120407 920520 PDR ORG NRCHIST PDR l
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l-COFI OF TWX FROM CARLSON TO O'FIILLY 6
ISSUED 4/o/ 9 -
i This TWX summarizes information' to be containec in CO Report No. 50-219.59-2.
The prelicensing inspection proCram for the Jersey Central Oyster Creek facility, Docket No. 50-219, was completed on, a/69, l-The current status of items previously listea as being' outstancing in i
the Satze.ry section of CO Report 50-219/69-1 has been reviewed and determined to le as follows:
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Ite 1 - Satisf actorily completed with exception of ascertaining the j
acequacy of the JC/GE prograt for reviewing vendor radio-l graphs of all stainless steel Anchor valves in ' systems that communicate with the primary system.
(Not considered te te 3
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an ite affecting issuance of license.)
t Ite: 2 - Satisfactorily completed with the exception that JC/GE'is to provide CO with a program for monitoring cable temperatures j
curing plant operation.
(Not considered to tc an item -
affectirig issuance of license. )
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Ite: 3 - JC/GE have been informed by CO that the location of filters in
-the stack sampling line raises sericus doubts that these filters S
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will "see" concentrations of halogens and particulates that art representat.ive of those being reles. mea from the stsel JC/GE
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have agreed cn a calibration program that vill include stapling cf particulates and halcgens at the probe sampling point to 1
demonstrate the adequacy of this system. Should the-1 4
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-d syste::. prove inadequate, appropriate modificatiens will.
be made. On this basis, this catter is considered adequately renolved.
(Not considend to be an ites effecting issuence cf license.)
l Ite 4 - Patter under review by 2 1 (Amendment 51).
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Ite: 5 - JC/GE are neveloping a proposal v:.ich we understand is 3
i responsive to regulatory concerns.
(Not considered to be an i
ite affecting issuance of license. )
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Ite: 6 - Satisfactorily completed with following excepciens:
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% operational Test "Drywell and sesorption System a.
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Leak Rate Feasurement" Completed with wpticu of f
de::.onstrating the capability of the system to conform to a statement in the application -(Amendment 11,Section III, f
Question 10 - Page. III-10-12, Paragreph T 7) that "no 4
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valve leakage rate is to exceed li of the allowable con-i tainment leakaEe volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." This lfmit Is exceeded for the "B" set of tain steam icolation valves, W
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-(Matter currently under review by LRL. )
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Preoperational Tect '" Standby Gas Treatment System and Reactor Bailding Leak Rate Test" -- Not'cc pleted due to inability a
to meet Technical Specification requirement of 0.25 inch vacuu: at 1200 cfm air flow. Fatter currently under reviev 3
l by DRL ( Amendment 52).
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Ite 7 - Patter considerea to be adequately resclved.
CO vill verify
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i I a'X t thet tr.e program descriced in tLe application is satisfactoril;,
implee.e nte d.
5 - The intent cf tne application is r.ot clear with reEard to the l
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inside presence of check volves in tne containment spray syste l
the dryvell. Following discussions with DRL, CO censiders tne I
j zatter resolved.
1 Ise 9 - Satisfactorily cccpleteu.
IwL 1^ - Satisfactorily co:pleteo.
Ite 11 - Satisfactorily completed with the exception of JC/GE formally approving specific test precedures relating to the pcst-loncind test phase of the startup program. Scheduled to be ec pleteu curing loading phase.
(Not considered to be an ite: aff ectind issuance of license. )
Ite: 12 - Satisfactorily completed.
Ite: 13 - Matter under review by DRL ( Amendment 52).
Ite: 11 - Satisfactorily completed, f
Ite: 15 - Satisfactorily completed.
As indicated above, all outstanding items identified in CO Re crt No. 50-219/69-1 have either teen satisfactorily resolved or are under continuing review by DRL or CO.
Items k, 6.a., 6.b., and 13 are being
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1 evaluatea by DRL.
Items 1, d, 3, 5, 7, a: i 11 are under review by
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- CO ani vC.',. te continued to be review after tne initial fuel loading.
Items c, 9, 10, 12, lh, and 15 have oeen satisfactorily completed or 4
I resc1ve..
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i In adciti:n to the outstanding items discussed above, one additional l
proble eeds further resolution.
This' relates to the Compliance investi-A i
3atien 1.:o the allegations conceraing the adequacy of certain pipes, i
fittings an: valves sed in inportantsysters in the. Oyster Creek plant.
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All cf ::.e cutstanding items retaining to' be reviewed cy Compliance,.
4 includi ; Itets 1, 2, 3, 5, 7 and 11 above and the piping investigaticn J
are cf zu:: a nature that tney are not impcrta: t tc the safety cf initirf.
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fuel loe:ing and Icy pcVer testing operaticns.
It is recettended, tnerefcre, that e ^.icited Provisional Operating License be issued. The limiting l
conditic 3 srculd prchibit reactor cperaticn at significann pcver until 4
the acceptacility for nuclear service of imper' ant pipes, fittinge en:
valves nas been substantiatec.
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