ML20141K897

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Forwards Category B Repts Re Util 710205 & 0317 Ltrs Forwarding Summary Technical Rept of Primary Containment Leakage Rate Test
ML20141K897
Person / Time
Site: Oyster Creek
Issue date: 04/09/1971
From: Mckinley J
Advisory Committee on Reactor Safeguards
To: Stratton W
Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203260078
Download: ML20141K897 (5)


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i April 9, 1971 e.

i W. R. Stratten, Chairman I

Oyster Creek Subcommittee C. P. Stess, Ytte Chairman, ACES I

I CATEGORY B REPORTS OYSTER CRIEE - JE18tY CENTRAL POWER & LIGNY COMPART LETITR$ DATID 2/3/71, 3/3/71, 3/17/71 & 2/s/711 SEMIANNUAL REPOET so. 33 ont u tTras SATED 2/1s/71, 3/18/71 & 3/25/71 Attached is a brief summary of the information presented in the subject serrespondense. No ACKS action appears warranted.

The DEL letter roguesting the QA program f ar eperation may be destroyed when you have completed your evaluation.

The other items should be incorrerated in your set of project documents to maintain an up-to-date description of the plant, organisation, pro-l cedures,ste.

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At taclusenta 1) su==ary

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2) Jersey Central Power & 1.ight Co 1tra 4td 2/3/71, 3/3/71, 3/17/71

& 1/s/71

3) semiannual Repert No. 3 A) sat itrs 4td 2/1s/71, 3/1s/71 &

3/13/71 est Acts Members w/attats 1 & 3

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Fevruari $i 197], forwarda their Summary Teahmical g,

Report = primary Centstament Leakage Este test Fd -b#

dated Jensary 10, 1971. The report deseribes b tutograted primary eestatuneet leakage rate tests i

and leeat tankage rata toeto that were poriarmed pcter to tattial plant operation. N first attempt reevited in ao tavalid test and a seeemd attempt was made with esecessivt reewits. N 35pois integrated test began on Marsh it. LH9 and eestimmed into March 23.

1, wee teend to be 0.47f16,0.01;L N 20 pet integratend test was we4e on Warek 1415 with an L, of 0.4504, 0.01th to Acts estion appears warranted.

Irreev Cutral Femy 1,.kight Consegy,Jgj,1gy datal February 8.1911 reports the teettag and adjmatment of the vacuum breaker valves e-the oestatement terms and their remotely eperated toelatten valves. N vaevum breaker system seems te have been restored te normal operatten aftar the imeleties valves falled es test in December (see Sepplement No.137).

No ACES action required.

Jersey central Power 4, tiaht Canaany semianovel Reeert l

M reports on plant operations from July 1,1970 through December 31, 1970.

During this third semi-amasal report perted for the Oyster Creek Datt No. 1 tha atattom operated at an availability facter of 87.11. One estended ek tdeen was scheduled in Octeher te eeMuct the lategrated primary Containment Leak Rate Test in noeordance with j

the Technical Specif tsaties ragstreasuts.

t. generater inspection was also perfor6md dering this shutdoom.

i in additten 10 shetaevas of short duratten see=rred during the report period taaleding 6 antenatis scrama.

Duries July, 3 senior operator emanimations were given at the plant site tenulting to all 3 receiving eeAtor operator itsenses. Ia esteber, another 5feep of 8 individuals were emendeed with 5 licsased storatest s.

and 1 senter operator being added to the plaat's.*

licensed peroommel. During this reporttaa perled,*$

engineers were also added to the staff to satisfy.f curNLt7pimtw mee8Far ustt7Fra n-ddar-fee omct >

.. anticipated.fdtars Ma..

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Form A EC.316 (I

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p' M8TRE imEEK Om December le 1970, the Atense heergy Causmisek.5 00Wr'D isseed Aenenement he I to the Syster Creek preda6ensi Operettag L& sense teoreastes the seminam itseased -

reactor peser twel from 1600 megawatts thersel te 1690 sesswette thermal. The poser taeroese ses inylemented by toersastag the r ted restrostatten flow from 61 a 106 to 66.1 a 10 lba/hr. The sitewebte peak tneat itus wee iocreased frea 331,000 Wrt/hr per egeere feet to M3,000 WYU/br per egears feet.

N eestree fins serem set pelat ses redeeed from 120% to 11H st rated flow, sed the APRM flev sometter reprogrammed eseerdtagly. A turbine trip and toed rejeetten screen (operettenal above 45% steen fles) was installed prior to tecreaatag remeter power.

I on December 10, 1970, the reseter power was tecreased I

from 1600 megewetta thermat to 1690 megewetts thermal.

A series of tests were pertermed prior to and following power tecrease to verify satisf actory operattee at the higher power level. All test resulto preyed to be satisfactory.

No ACAS estion appears warranted.

1 DEL letter to Jarsey Central dated February it. 1971 advises the licensee of the prertotone of the Rattenal j

tartrommental policy Act and t.he Federal Water Pe11stten Control Act and edytses that appropriate certitteatten F

must be obtaleed by April 3, 1973. Det regweets a status report en ef forts te obtate er waive oesk earttiteatten.

-l No ACKs action required.

Jareer Central Power & Liabt Coneaar letter dated March 3.1971 forwards Change Regeest Ee. 6 to the i

Technical Specifiesttees to estabitab taterte asseures to provide core fluu monitoring espaht11ty if the taatalled detectors are set ovattable. N preposal is to:

1.

Estabitab the sentimeour mee of a Trave 11 tag In-sere probe (TIp) chamber as em APRM taput At 411 leeal rewer range menitors 1a a partisalar re41al sore posittoa here fatted.

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Permit operattee at a reAmeed power level, b i StmT's neutron flus red bleek is met meseesary, it M.

red bleek preteettes seemet be estatained. 30.K'.

MALT 4 3.

If only one APRM okenne1 ie opwable is a gaaerast, penstt it to be removed from ewvise fee a ebert perted of time for tests and saltbration, provided that en ahiststrative red bleek it maintatmod.

Durtag the eeerse of reeater operatics,14eal Power Range Meetters (LPRM's) are empoeted to fall at a regular rats. Werma11y renden f attures will esear in a seattc?ed pattors wktsk weeld met scene ear parttevlar dif fievity between refueltog estages uben replecoment is possible (reaeter veneel head remeval

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to r m tred for LPRM replacement). At protest, at Oyster Creek only 12 of 124 LFRM chambers have fatted, which is well within destga expoetattoms. Bewever, three of the twelve fatted ehembers are in one radial locetten (12-17) in the sore (See Figure 1) and this results in the following:

1.

Two of the f atted LPEM's are in the same APRM ekennel and. in accordance with Technical Speet-ficattens, Section 3.1.3.2, this APRM skammel (#7) is "imoperable."

i 2.

Fallere of the tematutas LFEM La this radial location would render the other APEM skasmal (#3)

I to that pedrant "Looperable" (Technteel Speet-fleatten 3.1.5.1).

3.

Operatten eeu14 not he eestimmed if both APRM channels in a cadrant are (noperable or bypassed I

(Techntest Spectiteatten, Soetten 3.1. Table 3.1.1, i

set i e).

WOTT t The LP5M and APEM eyatems ere daeeribed La Section Y11-4.1.4 of the FNAAE.

At present, there is no esisting criterion that wmid permit the selectica of other LPEN's for use in the A. M shonnels even theesh many other LPRM's are availabis.

4 A study has commenced to determins mesas of provietas the some preteetten metag other operable LFEN's la meerby Leeatione.

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OTSTER CattK REL let ter to Jarser tantral dated '.*a LA.1971 00ert's approves proposed chante Se. 4 (above).

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Eo ACLB actien appeera warramted.

. 9 Jer u v Central Power 3,t.t ht t N la t tar ' ^ -' ' ' -

Marsh 17.1971 reports the reeutta of leak rete teste seedveted on February 16 17, 1971 en tbs main steam line isoistion valves. Leak rates et 4.3 ScrN and less were sneemrod. One valve abound a tendeocy to restre greater esating forse to ehtate the mesessary leak tightness.

No Acts aetten reptrod.

l Dit letter to Jerser_ Central dated March 25. 1971 requeste a esserLption of the pality assuranes program essed to povers operation, maint===e, repair, refueling, med plant modificattoms.

No ACES action re p tred.

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