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TOC 3) a UNITED STATES ATOMIC ENERGY COMMISSION s; 7 WASHINGTON. D.C. 20S45 1 (/4)
F June-25, 1973 Docket No. 50-219 Jersey Central Power & Light Company ATTN:
R. H. Sims
.Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Gentlemen:
13, 1972, you informed us that "prio-to June 1, By' letter dated November 1973, Jersey Central will submit to the AEC for approval a dr';ription and analyses of the gaseous and liquid radwaste system alterations which will be designed to assure conformance with the proposed Appendix I to 10 CFR Part 50."
Our letter to you, dated December 12, 1972, requested information within 60 days in regard to plant modifications planned in order to meet low as practicable effluent releases.
In response to this request, you stated in Supplemettt No. 4 to the Application for a Full-Term License dated "An FDSAR amendment describing these changes and the March 5, 1973:
analyses to demonstrate compliance with Appendix 1 will be submitted by You informed our staff that the reason for the additional June 1, 1973,"
four months was to allow you to consider the alternative systems and make a selection of the system you would propose.
By letter dated June 1, 1973, you submitted a report entitled " Proposed Modification to the Gaseous Radioactive Waste Systems for Oyster Creek Station." This report states that you have four systems under consideration for treatment of condenser off-gas. The cover letter to the report states that studies are in progress to select appropriate modifications to the The schedule given in Table 1-3 liquid and solid radioactive waste systems.
of the report shows that your evaluation of modifications began in July 1972.
We have reviewed the report and we acknowleuge that any of the four systems that you presently have under consideration for condenser off-gas treatment could be acceptable for reducing the activity in the total gas ef fluents to a level that is low as practicable. We have accepted similar type systems for other facilities. We recommend that you select the system that 9604i50077 960213 l
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r Jersey Central Power & Light June 25, 1973 Company i
design
.you propose to install and submit a description of the detailed and an analysis of its performance promptly..In addition, a description of the details of the modifications proposed-for the liquid and solid waste treatment systems should.also be submitted promptly.
consider that your report of June 1 fulfills your earlier We do not
-commitments to describe and analyze the systems you propose to use.
Because of the length of time that has elapsed since your evaluation commenced and considering the present status of progress as well as your l
proposed schedule, we presently have under consideration the imposition 7
of interim conditions for operation of Oyster Creek Nuclear Generating These will be intended to assure compliance with Section 50.36a(b' Station.
50,.i.e., that except for unusual operating conditions, i
of 10:CFR Part
/
average annual releases of radioactive material in effluents will be kept at small percentages of the limits specified in Section 20.106 of 10 CFR Part 20.
Sincerely, he,k.[ht A
Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing GPU Service Corporation G. F. Trowbridge, Esquire Mr. Thomas M. Crimmins, Jr.
cc:
Shaw, Pittman, Potts, Trowbridge ATTN:
Safety & Licensing Manager
& Madden
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910 - 17th Street, N. W.
260 Cherry Hill Road Washington, D. C.
20006 Parsippany, New Jersey 07054 1
Mr. Kenneth B. Walton Ocean County Library Brigantine Tutoring 15 Hooper Avenue 309 - 21st Street, South Toms River, New Jersey 08753 l
Brignatine, New Jersey 08203 Miss Dorothy R. Horner i
Township Clerk Township of Ocean Waretown, New Jersey 08753 J. Lester Yoder, Jr., Esquire 206 Horner Street Toms River, New Jersey 08753 1
_. _ _ _ _ _ _ _ _, < _________..__.___________.__.i
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Jersey Central Power & Light Comrntny 3
r M AolSoN AVENUE AT PUNCH Bowt. Ro AD e MoRRISTcWN. N. J. 07960 e 539-6111 June 22, 1973 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing United States Atomic Energy Commission Kashington, D. C. 20545
Dear Mr. Giambusso:
Subject:
Gyster Creek Station Docket No. 50-219 Electromatic Relief Valve Failure This letter is intended to follow up our, April 24, 1973 letter re-porting one electrom". tic relief valve NR-10S-L failed cr operability test.
As a result of additional investi;;ation into this problem, the reason for the fail-ure of the "B" electrouatic relief valve to open during the test was traced to the faijurn of the solenoid core guide pin as previously reported.
The solenoi.
core is guided by tee 1/2" pins sily'.:r soldered te t mr rupport phtes. The i
soldered juiat failed partiaily because of marginai soidering.
The guide pin:,
were cocked to one side and prevented the solenoid core from moving in the trip direction as required.
- io prevent this type failure from 2coccurring, the folleving repair was made to the pins support plate assembly of all fivc c1cetro: atic relief valves at Oyster Creek.
(Please refer to the attached drawing.) New 304SS guida pins vere machined to the dimensions shown on the attached dr;n ing.
'the new pins were welded to the underside of the support plates using 308L wire.
Ner 1/S" spacers vere installed between the solenoid core frame and the guidt support to clear the undersida weld.
Upon completion of the repair, the valvec wer e tested satisf.:ctorily with the reactor at ratcJ pressure dur2ng our restart follcuing our letent re-fueling out ni;e.
1:ncloscd are forty (40) copies of this report.
Very truly yours,.
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b Jersey Central Power & Ligitt Company M ADISON AVENUE AT PUNCH DoWL. Ro Ao e McRHi! TOWN. N.J. 07960 e SM 6 tQ June 22, 1973 Mr. A. Gl as.h tn s t.
Deputy 04. rector for Reactor Projects Directorate of Licensing United States Atomic linergy Comiiiission Washington, D. C. 20545 Dahr !-:r. Gi ambtoc c o :
Subj e ct : Oyster Creek Staticn Docket No. 50-219 Diesel Generator 1-1 The purpose of this letter is to report a failure of diesel gener-ator 1-1 to assa.:.e load during a r ecent surveillnace test.
Thi.' cvent is cm.-
sidere.1 to be an abnor:wi occurrence as defined in the Ter!.nicel Specifications,
a ice 1 "nrcl
'm 1,1F.5 Mett f catien of this event es recurred
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S ce! fi cationr, Paracraph 6.6.1), vcs made to AFC Region I, Directerate of Reg-i Ulat ory O Claciens on June 11, 19'75.
f As a part of the normal solveillance nrogram, an atter'p wi.s r.ade to stait *he L., I 'it cci..eneratur wid load it tu p cente r t hna 201 po'ec r
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qui re:i Py the L ehn.i cal Specifi cati ons, Perarrep:.1. 7. A. I.
Nuerer, bef re tha unit ct.ald autu..mtically s,.
- chionize ont o the IC bus, a scauence fault" ini tiatca, and tSc generator 5:ut: 0 0.
.i Investi r.ti,n into this, event showed that folicwing a f;.st st r.rt t er.,
cnd viti. th ciase1 ccnerat oc in peat.iag ceatro!, the genernicr t ri.ps ir.wdi-aicly w.on rect lp el a i.orn a1 stop signal ratl.cr t haa rtuning bach thc irc.d as eight h..
c.x p ;- cel.
As. result. the en3 nc ",o/vrnors a*e not set up fc: 6G Hr i
u*il e mic d op n... :.c.
J n at".':/yt in;; to pe rior.n the norra l s u rveil.1: 6.cc test, the t n s.0..e c ove ra e-could not resec at a fast enord r,ne to r. m h up fregnency.
Alla. ole tir toterval iw 60 secenJs, Consc3ncnc!v, the "r.equence Dult"
- cunditic, nc.,-
v cud LSe generator shut down.
The %. I d c:,c! generator was 1:. hen out ol autcmat ic, start ed letally, i.as plaperlv syachioni ed..anually and lot.AJ to rated ion. (2750 Ki: c c :.h. a:,..
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,Mr. $i abusso June 22, 1973 The diesel generatcr units are required to perform their safety function during a loss of power condition; thus, under such circunstances, synchronization is not required.
Since both engines' started and both generators excited, their safety function would have been pe rformed.
Therefore, no werc unusual safety signficance is associated with this event.
To prevent a recurrence of this kind, the Diesel Fast Start Surveil-lance Proced. Arc (601) will be revised to include a manual unloading of the l
diesel generator before tripping the unit.
This will run back the governor to
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normal unloaded position corresponding to 60 !!::.
Enclosed are forty (40) copies of this report.
Very truly yours,
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't Donald A. Ross Manager, Nuclear Cencrating Stations DAll: cs Enclosures (40) cc:
Mr. J. P. O'Reilly,11i rector
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Docket No. 50-219 Date:
Jyrn. LL19.73_
Tir:c:
12 30 j
ABNCRXAL OCCUMENCE
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REPORT NO. 7311 4.6 C-SUBJKg! Violation of the Teclutical Specification, para.
. A sattple of reactor coolant sh:til 1:e analyGed at least ewry 72 lcuns to 'detemIra the total mdloactivo icdine content.
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Failure of This event is considered to be an abnorml occurrence as defined in.
Notification of this-the Techrdest Specifications, para.
1.150 event as required by the Techttical Specifications, para, 6.6.3 was made to AEC Region I Directorate of Regulatory Operations on
,1unc __18, 1973 SITUATIGHf A smple of reactor ecolant was not amlyzed for total mdicactiva icdino content l:etween 0020 Juro 9,1973 ard 0830 June 13,1973 (104 hea.,10 nina.)
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.s-l CAUSE:
FAIT,UFE TO CfRAIll f.: AffAIXZS (CAC'lDR CCCIA?N SN@tE FCR 'lOTAf, FADt0A i
'Ib? truitichannel analy2:er is tb! irutrtront uwl to crea,suty total icdirn twlicactivity. 'Ihis buttecut beco:re Inoperattve on June 9,1 ar'.d was not repaired urttil June la,1973. 'Rn titre lapse was roc bro <
to the attention of the Cheatcal Supervisce by the Ciwettstry Techtticia
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s, RDfEDI AL ACTION:
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fletredial action was rot applicable in this case, since at tha tiro tb event ',nu discovere4 we were on the prcper saTpling fro.tuency. 'Ov2 i
httn2dInto action taken to correct the problem was to repair tra trulti-I channel, analyser so that the icdirn could be determirext, i
l SAFETY SIGNIFICA!'CEt NCW, Gmsn heta-gera countirg of rusctor water was perfortmd during t'.
pericd at the conral ditly CNquercy. GEC33 9tara doutttirg of filter?
reactor water was perrottrad dut>trg this pericd at ttu rntrul dally rtv:-
Doth of these ccuntitu techniques incluIo total f.cdine tudioactivity 1 the total. !fone of the resulta obtalrad frcta these arnlyses shcNel a e lation frcra rottral ducirg the perted of Jure 9th to Juno 13th, 000 Gas, witleh h, a ditvet ar.d eensitive irdication of Ciasion p i
duct activity, did rot show any stigstricant or unexphtined deviatica r.
nonral dut> leg thlu perled.
'Otf.s U13 shchn by cporacing Stack G03 cc;m i
instru.contacten ani Tvt ried by Orr Gu win? e arn1l/sta en Jur.: 11, l')
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J. T. Carroll i
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-l Licensec: Jersey Central Power & Light Co.
('i oa't Docket No.:
50-219 II.
D,. Thornburg, i
Chief' FS6EB j
Abnormal Occu*rence: TWX dated 6/18/73 (/* h #
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-]I DR Central Files (1) en The attached report from the subject licensee is Regulatory Standards
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R0 Files The ' action taken by the licensco is considered
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Followup will be performed during the next inspection a's nooronriate.
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f ROM (Name.nd un.t; REMAAAS the report have been forwarded to the PDR, Local n
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PDR, NSIC, DTIE and State representativos.
The
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'li/20/73 Licensing.
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ABllGUiAL OCCUldtEllCE
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REPOR7 ):0. 73 - 31.
. SUNECT: Violation of the Technical Specification, para.
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Failure of Opcirrrent Forttr &fstms 2, to autcnaticaDy reset to the oieratue node upon returrt'ae tic node witch to auto"atic duc to a tcmed re)ay,16):22B. Add $t5cem31y, faihu'e of Contrdment Spray h 7p fi10 to start upon actuat$rc tie key lock and centrol r. witch in tia Cmtrol Boan dae to h disecanected wire on the key lock witch.
Th'in event is considered to be an abnomal occurrence as defined in
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)!otification of this the Technical Specifications, para. ),:159 event ca required by the Tecludcal 5pecifications, pnra. 6.6.B was made to AEC hegion I Directorate of Hegulatory Operations on
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Juna 18, 3(#7'4 W
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Fo11cndJg succcctful rerforxince of the Ocotairnent Spray System aktcratic irdtSut$co tent, t)* Eynte:n wan returned to nonnD ntandby rqadinocc. Ikwtever, abDut an bo.u' and a hMf later, an odor of bumed i>pulation was detected $n the 4603KiB Eoan, in which $s located Con-Tne odor van traced to re)ay 1G;22B talment Spray log.ic pane) ER&B.
Wich Terfoms the l'unctico of Butenaticialy reseting the s.ystm to h andby condition when the rode switch is returned to "auttn6 tic".
Tne strdlay was fcnnd in the de-enernized state w)en $t nomd3y dould have tten enerr,1 zed.
Dpon replacirg the coi3 tzr3 serico resistor on the N1Dy, the s,Nstm was r cced in the "4/nsde 'h'ot" rode hrd an coerabDity check u
afwipted on Coniniment Spraf Tw p 530. Huaever, th pmp did not stprt, hxp tu1>, $n thtr F.rtt e syntm, was c)ceked u2G found to start eqt$sfactorily. Volthge 03:ccht wca'c nnde acron the hey lo::k DWitch ICI the prcb)cm was detembed to exist at that p:>3nt. Further checking, Wycaled a 2003c wire broken 01T cm of the key lock temdrain.
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Tne prenature failu're of relig 16);22T'. $n troacht to have been caused by an internn't breakdom of the cod Snsuht$ca resu3t$rg $n to).
"cten" An tie cod wjrdbira. - Tne pu.'rp start $rar, fad 3ure was-traced to 4
- a wire which had boccue discornacted frcm tie key loch r. witch.
' RD4EDI AL ACTIOff t.
7he-circuitry and ccrrponents assoc $nted w$th re)ay 16Y.2PB werc
. checked to clininate c4y extennl cause for t)e faDmv. 'ne cod and cer$co rer.$stor en IfiX22B were 2eplaced. Tne syste:n ro$c switch was then placed in "TynwAc" test, a muweD3ance test ran mu'$ng, which t$ra tic loose w$re on the key 300h rw$tch was found and t$phtened, and 11e node switch returned to "autmat$c". The system returned to a standby cond$t$on and tic reJay was checked to le enerc,ized. Further voltac.c
' checks were nade co tle relay and found to Ixt satisfactory.
i-SAFETT SIGHITICAl'CE:
In each of the two above cases, the Ocntairm?nt Spray System wu.Qd have functioned nomnDy had it bcen caned upon for serv 3ce. FDDow$ nc, the faDure of relay Er2EB,-the sybtem would not have " reset" autctnaticidly if tJe rode sw$tch had teen noved out of "autonatic" to scnc other mde, tren -
bach to "autcyratic". Tne operator, however, would have been sware of thin failure due to the presence of tJe " disabled" n}am, and could lave rczet the systw; ranualAv.
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- 11. D. Thornburg,
- 'r Docket No.:
50-219 Chief' FS6EB i
Abnormal Occurrence:
TUX dated 6/18/73 mm^u ai=^aas t o i..........o RO:ltQ (5)
The attached report from the subject licensee is_
DR Central Files (1) caic Regulatory Standards- '3)
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forwarded in accordance with RO Manual chsnter lor
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the next inspection a's aporontiate.
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the report have been forvarded to the PDR, Local r !-
'fs-hiO (7Y PDR, NSIC, DTIE and State representatives. The D. L. Caphton, RO:I licensee will submit a 10 day written report to Pnce.I pick DATE 6/20/73 Licensing.
Ust 01MER SsDE TOA ADO 8710* SAL REM AaK5 GPo s 89:4 0
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M ADISON AVENUE AT PUNCH BOWL RoADD MoRRISToWN. N. J. e7960 e s39 61t l June 5, 1973 A
A Mr. A. Giambusso t////j g
Deputy Director for Reactor Projects Es, T%c jk Directorate of Licensing g
United States Atomic Energy Commission c
Washington, D. C. 20545 f*.
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Dear Mr. Giambusso:
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Subject:
Oyster Creek Station Docket No. 50-219 Drywell Head Manhole Cover The purpose of this letter is to report a failure of the drywell
. head manhole cover-double gasket seal to meet' acceptable leakage as specified in Technical Specifications 4.5.F.1.D.
This event is considered to be an abnormal occurrence as defined in the Technical Specifications.
Paragraph 1.15.E.
Notification of this event as required by the Tech-nical Specifications, Paragraph 6.6.B, was made to AEC Region I, Direc-torate of Regulatory Operations, on May 27, 1973.
While attempting to pressuri:e the double gasket seal on the dry-well head manhole cover, significant pressure decay was observed between the gaskets.
A check of the manhole cover plate with leak teck showed that there was a significant amount of leakage through the outer gasket.
No attempt was made to determine whether the inside gasket was Icak tight.
The allowable leakage for a penetration is 10% of L (20) or 19.9 SCFH.
t Visual inspection of the gaskets showed that the outer gasket was brittle and would crack when pulled, but the inner gasket was less brittic and still had some resilience left when it was pulled.
Both gaskets on the manhole cover were replaced.
The test showed the outer gasket was leaking and the visual inspection indicate ! that the ir.ner gasket was scund m.)
-i St E. c been leak tight.
(Note this point wcs not verified by any measurebent.)
If the inner gasket t.a c ti '+
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1 The failure of both gaskets could result in prira.y containnent 1Cakage (into secoadary containment) in e.scers of technical specification
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'tI' Mr. Giambusso (h
- ' June 5,1973 limits and'in excess of the leakage assumed for off-site dose calcula-
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tions described in the basis for Technical Specification 4.5.
- Ilowever, there is a possibility that. the inside gasket was tight and that primary containment 1cakage would be less than ; allowable.
To prevent recurrence of this type inilure, a schedule for gasket replacement needs to be developed.
This particular gasket is estimated to have been in service 4 or 5 years.
In the future, it will be replaced every 3 years since it is located in a. higher temperature region of the containment.
As - future experience dictates.the need for_ gasket replace-ment in other areas of *.no containment, it will be factored into our replacement schedule.
Very truly yours,
'Wh Donald A. Ross Manager, Nuclear Generating Stations DAR:cs Enclosures (40) cc: Mr. J. P.'O'Reilly, Director Directorate of Regulatory Operations, Region I 4
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DIRECTORATE OF REGULA7"tY. OPERATIONS y
Memo Routo S16 e
OB:AR:162 R. T. Cirlson X
DR WELL HEAL MANHOLE COVER Region I The enclosed report from the Jersey _C_entral Power and Light Con
-to the Directorate E. J. Brunner X
or Licensing, pertain ng to deterioration of Redon I the gaskets associated with the drywell head "I
manhole cover at the Oyster Creek facility, S die X
Region II cc:
H. D. Thornburg, R0 C. E. Murphy X
I'#I " II
Enclosure:
Jersey Central ltr.
G. Fiore111 X
dtd 6/5/73 Region III D. H. Hunnicutt X
Region III W. E. Vetter Region III G. L. Madsen X
Region IV G. S. Spencer X
Region V 4
t Ca2 al
. H. Sniezek 6/20/73
-