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1 j h.N J. F. O'Reilly, Chief, Reactor Inspection & Enformenoot Br.,
Division of Compliance, Headquarters JERSEE CENTRAL POWER & LIGHI CCHPANY (0YSTER CREEK 1) j-DOCEET NO 50-219 i
j-The attached report of an inspection at the subject facility on October 13-16,
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1970 is forwarded for action. There were no items of safety significance noted.
i Six items of noncampliance were identified. These were processed by means of the 592 procedure. Consideration was given to going the safety letter route, housvar, it was not felt to be warranted in view of the nature of the items j
(mostly related to surveillance testing) and observations made by Nolan, i
Keppler and myself during our recent special inspection with reference to related corrective measures taken or scheduled to be taken in response to our earlier observations. McDermott plans to give the surveillance testing program special consideration during his next inspection. It will be a new ball gene if defleiencies are detected at that time.
i Although not stated in the report, corrective actions specified in JC's response i
to the M C
- 2 9, 1970 safety letter that cans under creas reviewed by f
McDermott during this inspostion were ma=Mn=ed.
2he remaining action itass were confirmed by Nolan, Kappler and/or myself during our special effort.
(Recults to be documented in separate report).
We consider that there may be sensric considerations in the design change made by JC in the initiating logic circuitry for the isolation condenser. JC stated that' the cause for the loss of function, which was identified by the closure of the emeese flow check valve, was a design error. We reca===ad that this l
matter be revimuod at other BWR's as is appropriate.
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We're not at all happy with the operating experience and lack of followup on j
problems relating to the amargency diesel generators. The latter aspect, lack i
of followup, was emphasised as reflecting negatively====gn==nt's conteol on l
their overall surveillance program. These matters will receive additional attention during the next inepection.
l JC was made aware of the carbon-14 issue as per your memorandum dated October i
17, 1970 They indicated that they will assess the magattude of C-14 in their effluents.
i The requirements of PI 3000/1, " Survey of Security Measures for Energency Power l
Systens", were completed. Answers to the questions posed in paragraph B of the subject FI follows l
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We feel that there is reasonable assurance that a person cannot gain j
access to the plaat, and specifically.to the emergency power systen controls, undetected: houwwer, the syetas is not eensidered to be
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knowledgeable person with a aind to it (inteeg on sabotage) could y ably accomplish his mission. This sese statement 2
is probably true for most if not all facilities.
i 2.
Our review disclosed that some key components within the asargency power r
system could be defeated without positive indication in the control room.
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With respect to the emergency diesel generators, could be as long as two weeks (testing frequency). With respect to the DC portion of the energency j
power system, the licensee indicated that the availability of the systen i
is assured (at least in part) on a shift basis. We have aces reservations as to the validity of this position.
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l Other matters of interest spoken to in the report include the followings
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Noticeable improvements were ebeerved in the area of facility staffing.
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(This matter will also be spoken to in the special report on our review l
of management systems).
2.
A problem has been experienced with pluggage of the main circulating water intake screens with sea grass.
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drives that otherwise would have been reinstalled by Gs.
4.
Althoggh some minor increase has been noted in total stall flows, control rod drive operating performance has been trouble free.
5.
An operator error resulted in an instance of an unscheduled scr==dnF of l,
a control rod into the core.
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Main coolant chemistry is being maintained within applicable requirements.
l Salt water leaks are being experienced in the main condenser.
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A faulty packing on a recirculation pump discharge valve resulted,in an increase in unidentified leakage within contaimment to near limits, necessitating a reactor shutdown for investigation and correction.
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Jc has finally inittsted stack monitor correlation measurements. A-pre-liminary review of early results suggests a good correlation, however, we plan additional review. The stack release rate at the time of the inspection l
was'v 7000 uC1/sec.
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E Monitoring of containment air activity and relative lasmidity are being investigated as possible additional means of primary systas led detection.
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( n-R. T. Carlson i
Senior Reactor Inspector
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Attacisment:
CO Report No. 219/70-7 by R. J. McDermott, dated 12/2/70 (21 cys) 4 cc: A. Gimabusso, CO l
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L. Kornblich, Jr., CO
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R. H. Engsiken, CO 1
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November 10, 1970 l.
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J. F. O'Re&1lys Chief, anester Inspectica & Badeseement Dr.,
j Divisten ei Gauptienne Emed ysetese s
,l JERaEf 6 NWR & M OSIhm (WWEB M 1) i l
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The attached report of a speatal inopostles at the subject fasility as
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Septe ket 3>35,1979, la assumedad Saw dietsthesias. This inopostian was made j
for the ei restestes she'ad=====*===== selating to the resent rash of j
mal esperiammed in the testdae imittat peessues seemister system.
Our inspector was satisfied with the par m--
og 14a management regarding a
these events, insludius the regious by the Flaat Operations Revier Cammittes and
'thalGenere! Offise Review Board. Folleuup on the additional planned modifications to the fasility, identified la the summary, will he daa====*d la future inspes-i tion reports. Likewise, with respost to the resmits of the meta 11ertical studies j
on the bruken linkage.
4 with resand to the genaria aspects, it is recommanded that the following he l
included la astian being considered by C0 EQ:
i 1.
Establish that GE does supply modified control linkages, as appropriate.
l for the ENE's of sesumos design. Five such facilities are identified in the i,
report.
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Establish that adequate =ai=*,===am practices and procedures are in affect i
at other ER's for the EPR system to minimise the probability of problemut l
with dirt insluding spesifically in the hydraulia samtrol valve (Hoog valve).
i 3.
Further revious h4 undertaken by C0:Eq and/or DgL, as is appropriate, to confina JC-05 st=*a===*= to the effest that their analysis of possihte i
failues modes of the Im system has ensampassed the most severe transient possible. Alas that W be requested to supply a espiaal report on this' i
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system $5 Shat segaud, j
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3 The a,,us.httar es aeme 1 ama a ahow to man's 1. n gie. I will he acted u,o.,
1 as is appeepstate,by this edites.
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