IR 05000219/1972025
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J. G. Keppler, Chief, Reactor Testing & Operations Branch Directorate of Regulatory Operations, HQ
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RO INQUIRY REPORT NO. 50-219/72-25 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK - BWR EQUIPMENT DEFICIENCY - RELIEF VALVE DISCHARGE PIPING The subject inquiry report is forwarded for your action in that this problan may be generic.
I We do not. know when the licensee became aware of this deficiency.
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The problem at the relief valve end of the pipe was known at least by June 2, 1972. Corrective action was taken during the refueling outage that was in progress at that time. In this case, we did
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not learn of a possible defici,ency until after the plant was shut
down following an unrelated scram on August 9, 1972.
i We plan to follow the resolution of this matter and will keep you late.
informed as is appropriate. We plan to discuss with the licensee the need for timely reporting of deficiencies or changes in accident analysis.. The licensee stated that' this deficiency would be included in
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the report concerning inadequate supports in the vicinity of the
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relief valves. That report is to be submitted by August 25, 1972 per agreement with Licensing.
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R. T. Carlson, Chief Reactor Operations Branch Enclosure:
Subject Inquiry Report (18 cys)
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cc:
P. A. Morris, RO j
11. D. Thornburg, RO j
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R. H. Engelken, RO
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RO Inquiry Report No. 50-219/72-25 Subject: Jersey Central Power & Light Company
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Facility: Oyster Creek - BWR
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License No.:
DFn-16 Title: Equipment Deficiency - Relief Valve Discharge Piping
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Prepared by:
F. S. Cantrell, Reactor Inspector Date A.
Date and Manner AEC was Inforined:
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August 11, 1972, by telephone call from Mr. T. J. McCluskey, Station
Superintendent.
B.
Description of Particular Event or Ciretanstance:
A design evaluation of the reaction forces along the vent piping from the electromatic relief valves (ERV) indicated that the
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j supports-might be overstressed in the vicinity of the ERV (Inquiry Report 219/72-13). The study was extended to include
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the full length of the vent pipes. This evaluation indicated that the supports for the discharge piping in the torus might
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Action by Licensee 2 Temporary supporr.a (cables) were installed while the reactor was
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shut down following a scram that occurred on August 9,1972.
1 No schedule has been established for implanenting a permanent fix.
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. AUG 151972
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J. G. Kappler, Chief, Reactor Testing & Operations Br.
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Directorate of Regulatory Operatiocc, BQ.
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i RO INQUIRY REPORT No. 50-219/72-24 j
' JERSEY CENTRAL POWER & LIGHT COMPANY
orsTER CREER - BwR
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l EQUIPMENT FAILURE - ISOIATION CONDENSER FAILURE
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%e st& ject inquiry report is forwarded for your infonnatica.
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The licensee stated that he pisoned to conduct sufficient testing
of the valves and switches to assure that the isolation condensors i
will operate when required. He stated that the isolation signal
was the first that had been received since the five==ew delay j
was' added to the system.
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% e 1_icensee's' actions appear to be adequate.
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We plan to follow the resolution of this matter during the nart inspection.
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R. T. Carlson, Chief Reactor Operations Branch
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Enclosure:
Subject Inquiry Report
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cc:
R. Minogue, RS (3)
l R. S. Boyd,.L (2)
R. C. DeYoung, L (2)
D. J. Skovbolt, L (3)
H..R...Denton, L (2)
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P. A. Morris, RO H. D. Thornburg, RO R. H. Engelken, RO
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RO Files DR Central Files
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RO Inquiry Report No. 50-219/72-24
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Subjects Jersey Central Power & Li_=ht Comsany
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Facility: Oyster Creek - BWR
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i License No.: DPR-16
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l Title: Equipment Failure - Isolation Cond_enser Failure l
Prepared by:
F. S. Cantrell, Reactor Inspector Date
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A.
Date and Manner AEC was Informed:
l August 10, 1972 by telephone call from Mr. T. J. McCluskey, Station Superintendent, at 6:00 p.m.
B.
Description of Particular Event or Ciretanstance:
Following a reactor scram on August 9, 1972, the reactor was approaching a cold shutdown condition. When the temperature and pressure reached approxh ately 360 F and 150 psig, the'"A" isolation
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condenser was initiated manually per normal procedure. When the
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closed condensate drain valve opened, both flow indicators on the iW:
condensate line surged full scale; however, the needle of one indicator i
hung up.
Shortly thereafter, the "A" isolation condenser isolated.
l The line break sensors are set to initiate condenser isolation after
- I five seconds of "High Flow". An i==adiate attempt was made to initiate l
the "B" isolation condenser; however, the closed condensate drain valve failed to open. An operator was dispatched to the field and valve opening
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was initiated manually.
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Action by Licensee:
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An investigation showed that the isolation signal on unit A resulted
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from the needle of the flow indicator hanging up with a full scale i
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reading. The full scale reading was apparently caused by insufficient j
snubbing action for the flow signal and mechanical interference in
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i the flow indicator. The line snubbers for both systeras were
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I relocated closer to the transmitter in order to provide better
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snubbing action. In addition, strain gauges were installed on the piping and transmitter to determine if shock forces are present that could be affecting the instrumentation.
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2-After the reactor is pressurized with two bypass valves open (next startup), and prior to putting the plant on line, the isolation condensers will be initiated to verify the fix.
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2.. The open and close ifmit switches, the torque switch and the overload
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switch settings on both isolation condenser condensate drain valves vers checked and were found set properly.
The drain valves have been operated several tiraes since without failure.
(The torque switch is bypassed in the opening cycle of the valve.)
The specific cause of the failure has not been determined.
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The licensee stated that he plaanad to submit a ten day wdtten report of these events to Licensing.
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J. G. Keppler, Chief,. Reactor Testing & Operations Branch Directorate of Regulatory Operations, IQ RO INQUIRY PIPORT NO. 50-219/72-23 JERSEY CENTRAL POWER & LIGHT COMPMiY OYSTER CREEK - BWR EQUIPMENT FAILURE - HIGH FIDW SWITCH EMERGENCY CONDENSER The subject !nquiry report is forwarded for your information.
The licensee's antion appears to be responsive. Upon receipt of the licensee's report, we vill make an additional review of the sub-ject.
R. T.
Car'Ison, Chief
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Reactor Operations Branch l
Enclosure:
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Subjeet Inquiry Report ec: R.'Minogue, RS (3)
R. Boyd, L (2)
R. DeYouit'g', L (2)
D. Skovbolt, L (3)
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H. Denton, L (2)
P. 11 orris, RO
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H. Thornourg, RO R. Engelken, RO PD Files DR Central Filca
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RO Inquiry Report No. 50-219/72-23 a
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Subject:
Jersey Central Power & Light Company
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License No.:
DPR-16 C[
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'I Facility: Oyster Creek - BWR Equipment F' ilure - liigh Flow Switch Emergency Condenser
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a Prepared by:
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F.'S Cantrell, Reactor pspector
'Date A.
Date and Manner AEC was Informed:
August 4, 1972, by telephone call from Mr. T. J. McClusky, Station
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Superintendent.
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Description of Particular Event or Circumstance:
During a routine surveillance test on August 4, 1972, one of two steam icg high flow switches for one isolation condenser failed to l
operate.
The switch failure was caused by a leak in the bellows.
The isolation condenser was considered inoperabic while temporary repairs to the switch bellows were completed.
The switch is a
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Barton Model 278 delta pressure switch.
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Action by Licensce:
Temporary repairs to the bellows were made on August 4,1772, and the switch was checked out.
A replacement switch was ordeced.
The licensee is investigating the cause of the problem and the applic-ability to other suitches. The licensee intends to submi'. a 10 day written report to Licensing on this matter.
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J. G. Keppler, Chief, Reactor Testing & Operations Br.
Directorate of Regulatory Operations, HQ
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RO INQUIIY REPORT No. 50-219/72-22 JERSEY CBrfRAL POWER & LIGHT CCHPANY a
OYSTER CREEK - BWR i
BQUIPMENT FAILURE - CotirAINMDrr SPRAY PIMP The subject inquiry report is' forwarded for your information.
The licensee's action appears to be appropriate.
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We plan to follow this investigation and will keep you infonned as is appropriate.
It should be noted that the licensee does not
plan to make a written report if the investigacion shoes the pump was operable in the automatic mode. We concur.
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R. T. Cerissa, Chief, Reactor Operations Branch
Enclosure:
Subject Inquiry Report cc:
R. Minogue, RS (3)
R. S. Boyd, L (2)
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R. C. DeYoung, L (2)
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D. J. Skovhelt, L (3)
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R. Denton, L (2)
P. A. Morris, RO
H. D. Thornburg, RO R. H. Engelken, RO RO Files DR Central Files
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'l RO Inquiry Report No. 50-219/72-22 EulJe't: Jersey Central Power & Light Companv_
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A Facility: Oyster Creek - BWR
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, p License No.: DPR-16
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Title:
Equinmant Failure - Containment Spray Pump
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Prepared by:
I F. S. Centre 11, Reactor Inspector Date
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A.
Date and Mannar AEC was Informed:
August 2,1972, by telephone call from Mr. T. J. McCluskey,
j Station Superintendent.
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Description of Particular Event or Ciremstance:
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While trying to recirculate torus water to obtain a sample on l
i August 1, 1972, the C containment spray pump would not start
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manually.
(The other pmp in the same loop was subsequently
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The breaker position switch associated with the C pay was clesnad 4'
and the pump started without difficulty. If the failure to start was caused by the breaker position switch, the pap would not have
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l started automatically to perform its intended safety function;
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however, if the problem was in the individual control switch, the
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automatic initiation feature would not have been negated. Technical
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Specification 3.4.C permits one pump to be inoperable for 15 days.
t The suspected breaker is a GE supplied breaker,' type AK-2A-59, j-1600 esp, 600 volt. The switch inside that required cleaning
is a GE type SPM-10AB593.
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Action by Licensee:
The investigation is continuing to demonstrate that the breaker
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position switch was the only cause of failure, or if other switches are subject to the same failure. The licensee will make a 10
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day written report as required by Technical Specifications if the problem is determined to be associated with the breaker position
switch or some other mechanism that could have prevented automatic operation.
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J. G. Kappler, Chief, Reactor Testing & Operations Br.
Directorate of Regulatory Operations, HQ RO. INQUIRY REPORT NO. 50-219/72-20 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK - BWR
EETER11AL OVEREXPOSURES - EXPOSURES GREATER TilAN 3 REM / QUARTER The subject inquiry report is forwarded for your information.
'These overexposures are being investigated for the licensee by a committee frcns the Parsippany Office appointed by the Company President. We plan to follow the results of this investigation and will review this matter in more detail during the next
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routine inspection.
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R. T. Carlson, Chief,
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Reactor Operations Branch Md Enclosure Subject Inquiry Report cc:
R. Hinogue, RS (3)
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R. S. Boyd, L (2)
i R. C. DeYoung, L (2)
D. J. Skovholt, L (3)
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H. R. Denton, L (2)
P. A. Morris, RO H. D. Thornburg, RO
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R.11. Engelken, R0 Regional Directors, RO G. W. Roy, RO RO Filsa DR Central Files
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.i RO Inquiry Report No. 50-219/72-20 Subject: Jersey Central Power _& Light Company Facility: Oyster Creek - BWR License No.: DPRr-16 l
Title: External Overexposuras - Exposures Greater than 3 Rem / Quarter
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Prepared by:
F. S. Cantrell, Reactor Inspector Date
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Date and Manner AEC was Informed:
July 14, 1972 by Mr. D. Ross. Technical Supervisor, during a site inspection.
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Description of Particular Event or Circumstance l
The film badge report for the April - June 1972 quaster from i
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Landauer, Inc. showed that during this period, 11 employees j
received whole body exposures in excess of 3.0 Rem (3.010 to i
3.360: Rem). Ten of these. employees were maintenance personnel i
and one man was a health physics technician. All of the men with high exposures were involved in general maintenance work M
during the May - June refueling outage. Personnel were not assigned to radiation work af ter receiving an estimated 2500 mrem until the results of the film badge was received. Additional exposure was then permitted for low radiation work based on ion chamber dosimeters.
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Action by Licensee:
The licensee is investigating the exposure of each person and will submit a written report to the Director of Regulatory
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Operations as required by 10 CFR 20.405.
Each
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employee has been given a whole body count (given to all station
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employees except the clerks). The Chairman of the General Office Review Board and the President of Jersey Central Power
& Light Co. have been notified as required by Technical Speci-fications.
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JUL 2 61972
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J. C. Keppler, Chief, Reactor Testing & Operations Br.
Directorate of Regulatory Operations, HQ _
RO INQUIRY REPORT NO. 50-219/72-19 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK - BWR l
EXCEED TECHNICAL SPECIFICATIONS - HYDRO TEST WITH POTENTIAL l
IACK OF APPROPRIATE PRESSURE RELIEF PROTECTION l
l The subject inquiry report is forverded for your information.
l Technical Specifications give the set point for the safety valves (
(1212 - 1239 1 12 peig) and specify that reactor pressure not l
exceed 1375 pets with irradiated fuel in the reactor. The control rod drive pump develops approntmately 1450 pais pressure.
Section III of the Boiler and Pressure Vessel Code requires the vessel to be protected by a self actuated relief device against the consequences of steady state and transient condi-
tions of pressure and temperature in excess of design condi-
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l tions. Our view is that the intent of both the Technical
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Specifications and the applicable code was violated in the h
instance noted.
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I The licensee stated that a self actuating relief device will be provided in the future if the safety valves are gagged during future hydro tests; however, the licensee does not consider this matter a violation or reportable under the Technical Specifications.We concure in their view on reporting. We also agree with their proposal to have a self actuating relief device operable during future Bydro tests.
R. T. Carlson, Chief Reactor Operations Br.
Enclosure :
Subject Inquiry Report ec:
R. Minogue, RS (3)
P. A. Horris, RO R. S. Boyd, L (2)
H. D. Thornburg, RO R. C. DeYoung, L (2)
R. H. Engelken, RO
]h D. J. Skovholt, L (3)
Regional Directors, RO U
H. R. Denton, L (2)
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RO Inquiry Report No. 50-219/72-19 l-sub, lect: Jersey Central Power & Linh_t Company Facility: Oyster Creek - BWR l
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f License No.: DPR-16 Title: Exceed Technical foecifications - Hydro Test with Potential
Lack of Appropriate Pressure Relief Protection Prepared by:
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F. S. Centre 11, Reactor Inspector Date A.
Date and Manner AEC was Infomed:
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l July 12, 1972, as a result of a review of the Foreman's Log during
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l a routine inspection at the site. Additional information was provided by Mr. T. J. McCluskey, Station superintendent.
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B.
Description of Particular Event or Circumstance:
The safety valve vendor (Dresser) rec h ed to the licensee that all safety valves on the reactor vessel be gagged at 80% of set pressure during syhydro test (operating pressure leak test)
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conducted on June 16, 1972 following the recent refueling. The reason given was to avoid collecting water on the outside of the seat bushing if the valve leaked.' The previously reported problem with cracks in seat bushings (Inquiry Report 50-219/72-09) was partially attributed to water being held up in this region as the l
l result of safety valve leakage. Pressure for the hydro was supplied
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by throttling the control rod drive psanp and bleeding off through the clean up systen. Pressure was administrative 1y limited to 1060 psi.
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The electromatic relief valves were operable during this period; I
however, they are not self actuating. The relief valves on the clean
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up system were also operable; however, their availability would be negated in the event of contairunent isolation.
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Action by Licensee:
The licensee stated that gagging safety valves had been reviewed, that the hydro procedure had been changed to carefully control the pressure administrative 1y and that the pressure was maintained well j
below the set point of the safety valves (1212 psi). As a result, the licensee did not consider this a violation of the Technical
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i Specifications; however, in the future the safety valves will not i
be gagged unless a self actuating relief valve is provided in the
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systen.
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JUL 2 51972
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J. G. Kappler, Otief, Reacter Testing & Operations Brmch Directorate of Regulatory Operations. HQ
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i RO DQUIEr REPGtT NO. 50-219/72-21
l JERSEY CDrIRAL POWER & LIGHT CCHPANY I
OYSTER CREEK - BWK PUBLIC INTEREST - ATTE'ED FISH KILL DUE TO HOT WATER
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The subject inquiry report is forwarded for your information.
We infomation obtained was relayed to John Russo, New Jersey Department of Eadiological Protection by Dr. Gallina of our staff.
j Hr. Russe infar=ad Dr. Gallina that he had a tem of paraan=al
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working in the vistaity of Oyster Creek at the present time, and
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j that he had not had any reports from the to substantiate these j
allegations; hausser, he would direct than to investigate.
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l The above information and the information obt=4aad from the Oyster Creek facility was relayed to Mr. Russett by telephone on July 24,
i 1972. At that time be implied that if the condition did not i
improve, he and his neighbors would try other means to obtain a solution to the problem.
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Any additional infomation obtained from the State of New Jersey
will be relayed to Mr. Russett as is appropriate. Your office j
will be kept infomed of substantive developments. At present,
the licensee does not plan to make a written report on this matter.
j We concurein this position based on the information currently
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R. T. Carlson, Chief, Raactor Operations Brench i
Enclosure:
Subject Inquiry Report I
cc: R. Minogue, RS (3)
R. S. Boyd, L (2)
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R. C. DeYoung, L (2)
D. J. Skovbolt, L (3)
l H. R. Denton, L (2)
j P. A. Morris, RO A
H. D, h ornburg, RO V
R. H. 5'anelkan.10
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10 Inquiry Report No. 50-219/72-21 Subject: Jersey Central Power and Light Company i
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Facility: Oyster Creek - BWR
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License No.: DPR-16
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Title: Public Interest - Alleged Fish Kill due to Hot Water
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Prepared by:
F. S. Cantrell, Reactor Inspector Date
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A.
Date and Manner AEC was Informed:
l July 24, 1972, by telephone call from Mr. James J. Russett, at 10:00 a.m.,
j who stated that he owned a house on the first lagoon up the discharge canal from the bay.
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Description of Particular Event or Ciretsastance:
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Mr. Russett stated that fish were coming to the top and dying in the discharge canal because of the hot water discharged by the nuclear j
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plant, In addition, he stated here was desweed and scum on top of the water the full length of the discharge canal. He stated that he
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measured the water temperature at teveral locations using a calibrated _
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l thermometer with the following results:
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At the Route 9 bridge over the discharge canal - 98* F.
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In the lagoon opposite his house (approximately 3/4 mile downstream)--
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Mr. Russett's estimate) - 95 F.
3.
About 1 mile further downstrem (out in the bay) - 940 F.
I 4.
Near the entrance to Barnegat Bay from the Ocean - 820 F.
i Mr. Russett stated that he thought the situation was deplorable and thought he should contact some other enviromental or wildlife agency.
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i He was told the inspector would forward this information to the appropriate state agency.
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Action by Licensee:
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Mr. Ross, Technical Supervisor at the Oyster Creek Nuclear Generating Station, who was contacted by telephone on July 24, 1972, supplied the following information:
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We inlet cooling water temperature at the plant is 90 i 18 F
and has been steady at this temperature for several days.
j 2.
S e 980 F. in the discharge canal at the Route 9 bridge is probably correct.
3.
The power level has been approntmately 1890 HWt (approximately
635 Hwe gross).
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4.
The cooling water flow through the condensers is 460,000 gym.
One additional dilution pump is operating adding approximately
290.000 gym flow to the canal. Two other dilution pumps are j
available which could increase the dilution flow to approximately
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l 780,000 gym. These two punps are not being used because the increased flow would increase the -=t of grass and seaweed j
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drawn into the inlet canal. At present, the grass and seaweed is directed to the dilution ptanp where it is pumped to the discharge
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l canal.
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Mr. Ross stated that the water that enters the bay from swanpa,
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bogs, oyster Creek, etc., can be described as " cedar water" and
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l contains fapurities that cause foaning when areated as passing f*_.
over rocks, or through pumps. he water then has a brownish foamy look. He stated this matter had been reviewed with Mr.
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Charles Amato of the State of New Jersey.
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6.
Oyster Creek has a discharge temperature limit of 95 F (state i
imposed) at a bouy located in the bay between the inlet and the outlet canal. We tanparature 'is normally recorded on a chart
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at the bosy; however, due to equipment malfunctions, no data l
i has been collected for the past two weeks.
(Ross is not sure OC has collected any good data this stammer). The recorder was
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picked up 7/13/72 and brought back to the plant for repairs.
It was being re-installed today (7/24/72). The instrument people i
were instructed to take a portable temperature indicator with
l then and obtain water temperature in the vicinity of the bouy.
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3944 JUL 6 M72
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J. G. Keppler, Chief, Reactor Testing & Operations Branch Directorate of Regulatory Operations, HQ RO INQUIRY REPORT No. 50-219/72-18 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK - BWR EXCEED TECHNICAL SPECIFICATION LIMITS - RAD WASTE STORAGE TANK INVENIORY The subject inquiry report is forwarded for your information.
In spite of raising the Technical Specification limit for the content of the tank farm from 0.7 Ci to 10.0 Ci (Change No.10), rad waste managenent following an extended shutdown continues to be a problem.
At present, the waste concentrator is plugged requiring a shut down of this waste processing stream. According to Mr. McCluskey, money has been budgeted to install a second waste concentrator.
M3 n is matter will be reviewed during an inspection beginning July 5, 1972. Mr. McCluskey stated that a written report would be submitted in 10 days as required by Technical Specifications.
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R. T. Carlson, Chief,
,
Reactor Operations oranch Enclosure:
Subject Inquiry Report cc:
R. Minogue, RS (3)
'
R. S. Boyd, L (2)
R. C. DeYoung, L (21 D. J. Skovholt, L (3)
'
H. R. Denton, L (2)
P. A. Morris, RO II. ' D. Thornburg, R0 R. H. Enge1Len, RO
RO Files a%l DR Central Files-Q J
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RO Inquiry Report No. 50-219/72-18 Subject: Jersey Central Power & Light t'm any Facility _ Oyster Creek - BWR
[
License No.: DPR.16 Title:
Exceed Technical Specification Limits - Rad Waste Storage Tank Inventory Prepared by:
F. S. Cantrell, Reactor Inspector Date A.
Date and Manner AEC was Informed:
June 30,.1972, by telephone call fran Mr. T. J. McCluskey, Station Superintendent.
B.
Description of Particular Event or Circumstance:
The inventory of the outside rad wasta " tank farm" was 12.78 Ci when the contents were analyzed at 2:00 pm on June 28, 1972. Technical i
Specificatimts paragraph 3.6.C limits inventory to 10.0 Ci and directs that the contents.be recycled if the inventory exceeds 5.0 C1.
By 3:30 pm en June 28, the contents had been recycled back to the rad waste building and the inventory of the tank fem was 3.87 C1.
Analysis of the tank farm cantents is performed on Hondays, Wednesdays and Fridays in
comparison to Technical Specifications required once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C.
Action by Licensee:
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The investigation showed that waste neutralizer tanks A and B overflowed i
l during the re8eneration d a condensate domineraliser. The overflow went to the floor drain sump and was pumped te the floor drains sample
'
tank via the floor drain collector tank and a process fittar on June 27,
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1972.
The A floor drain sanple tank contained 10.45 Ci and the B sample
tank 1.0 C1.
The Plant Operating Review Comittee will review this i l violation.
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3944 JUN 2 91972 P
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J. G. l'eppler, Chief, Reactor Testing & Operations Branch Directorate of. Regulatory Operations EQ RO INQUIRY REPORT No. 50 219/72-17 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK - BWR SURVEILIANCE TEST OF EMERGENCY DIESEL GENERATOR The subject inquiry report is forwarded for your action in that the problem may be generic.
The failure of the cooling radiator shutters to open may be a " weak link" in the emergency power supply. The engine high temperature cutout is supposed to be bypassed in the fast start mode, but not in the test mode. If the shutters failed to open under emergency conditions, the diesel would rapidly overheat. Fast operator action would be require'd to prevent damage to the enginerand the consequent loss of that source of emergency power. U der these conditions, we question whether the l
%4-operator would be acting correctly if he shutdown the diesel. OC's
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Technical Specifications permit one of the two EDGs to be out of service for seven days in a thirty day period.
The licensee's actions appear to be responsive; however, we picn to review this matter during the next inspection scheduled for July 5 - 7,
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1972. Also, we plan to review this failure at other operating power reactors in Region I to determine if there are any generic problems. '1he licensee
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will submit a 10 day written report on this matter.
R. T. Carlsea, Chief Reactor Operations Bratch Enclosure:
j Subject Inquiry Report (18 cys)
]
cc:
P. A. Morris, RO li. D. Thornburg, R0 R.11. Engelken, RO
/
RO Files
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RO Inquiry Report No. 50-219/72-17 s
Subject: Jersey Central Power & Light Company _
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License No.: DPR-16
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Facility: Oyster Creek :.R1R
Equipment Failure - Surveillance Test Emergency Diesel Generator (EDG)
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Title:__
Prepared by:
Date F. S. Cantrell, Reactor Inspector A.
Date & Manner AEC was Informed:
June 26, 1972, by telephone call from Mr. T. J. McCluskey, station Superin-tendent.
'
Description of Particular Event or Circumstance:
B.
26, 1972, during a routine surveillance test with the No.1 EDG On June loaded, the generator tripped off line due to high engine temperature.
'Its preliminary The diesel throttled back to idle speed automatically.
investigation showed that the cooling radiator shutters (damper) failed
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These shutters are scheduled to open in steps in order to allow to open.
the engine to reach operating temperature in a minimum amount of time.
C.
Action by Licensee:
An investigation is being conducted to detemine the specific cause of Mr. McCluskey stated that the PORC would the shutters failing to opea.
review the findings and that a 10 day written report would be submitted to L.
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3944
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JUN 2 21972
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J. C. Kappler, Chief, Reactor Testing & Operations Br.
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Directorate of Regulatory (:perations, HO l
RO IIIQUIKY REPORT NO. 50-219/72-16 JERSEY CENTRAL POWER & LIGHT CCHPANY
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OY3TER CREEK - BWR
EQUIPMENT FAILURE - REACTOR PROTECTICH SYSTDi REIAY The subject inquiry report is forwarded for your information.
At the time of the communication, the licensee had no explanation as
j to the cause of failure. We plan to review this matter during the next inspection, currently scheduled for the mek of June 26, 1972.
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R. T. Carlson WQ Chief, Reactor Operations Br.
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Enclosure:
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Subject Inquiry Report i
i cc:
R. Minogue, RS (3)
R. S. Boyd, L (2)
R. C. DeYoung, L (2)
D. J. Skovholt, L (3)
H. R. Denton, L (2)
P. A. Morris, RO H. D. Thornburg, RO R. H. Engelken, R0 RO Files DR Central Files 43 &s % % L-Lp.
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RO Inquiry Report No. 50-219/72-16 Subject: Jersey Central Power & Light Company
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License No.: DPR-16
Facility: Oyster Creek Title:___ Equipment Failure - Reactor Protection Systen Relay Prepared by:
F. S. Cantrell, Reactor Inspector Date A.
Date and Manner AEC was Informed:
June 16, 1972, by telephe a call from Mr. T. J. McClwkey, Station
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Superintendent.
B.
Description of Particular Event or Ciretanstance:
An odor of burning insulation noted on June 15, 1972 was traced to
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the 6K28 relay in the reactor protection system. This relay
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operatte the " seal in" contacts for the main steam isolation
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valves outside containment and trips the recirculation loop
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i sample valves on an isolation signal.
NW C.
Action by Licens u:
The 6K28 relay was replaced and checked to assure proper opetation.
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The licensee stated that a 10 day written report would be submitted to the Directorate of Licensing.
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J. G., Keppler, Chief, Reactor Testing & OperationsBr.
Directorate of Regulatory Operations, HQ RO INQUIRT REPORT NO. 50-219/72-15 JERSEY CENTRAL POWER & LIGHT CCHPANY 0YSTER CREEK - BWR
'PJQUIPMENT FAILURE - ISOIATION VALVE LEAKING EXCESSIVELY The subject. inquiry report is forwarded for your action. The frequency of failure of these falves during surveillance testing continues to cause concern about the ability of the valves to perform the required function. We have observed failures to close and failures to close in the required time as well as failures to meet specifications on leak tightness. In each specific instance, the
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licensee's action appears to have been responsive to the problan encountered; however, the overall performance of these valves still leaves a lot to be desiref. It is reca=nanded that Licensing be informed of our concern and requested to.<teview the specific testing
requ6tements for adequacy.
We plan to review this latest problem during the next routine inspec-tion. The licensee will submit a 10 day report to Licensing.
l:
R. T. Carlson
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l Chief, Reactor Operations Br.
Enclosure:
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Subject Inquiry Report (18 cys)
.
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cc:
P. A. Morris, RO i
H. D. Thornburg, RO R. H. Engelken, RO
RO Files
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RO Inquiry Report No. 50-219/72-15 Subject: Jersey Central Power & Light Company License No.: DPR-16
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Facility: Oyster Creek - BWR Title: Equipment Failure - Isolation Valve Leaking Excessively
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Prepared by:
Date F. S. Cantrell, Reactor Inspector
A.
Date and Manner AEC was Informed:
.
June 16, 1972, by telephone call from Mr. T. J. McCluskey, Station
!
Superintendent.
B.
Description of Particular Event or Ciressastance:
.
While performing a surveillsace check en June 16, 1972, main steam i
isolation valve (MSIV) NS03B was found leaking 100 efm. The maxisman
permitted leakage is 9.9 cim. This valve held during the systen j
hydro test conducted during the previous week.
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C.
Action by Licensee:
Jersey Central is investigating the cause of the leakage and plans,to
- 4 4 make the necessary repairs to correct the leakage prior to resetor
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startup. The licensee plans to submit a 10 day written report.
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JUN 2 21972
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J. G. Keppler, Chief, Reactor Testing & Operations Br.
Directorate of Regulatory ON=tions, HQ
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RO INQUIH REPORT NO. 50-219/72-14-JERSEY CENIRAL POWER & LIGHT C(MFANY
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OTSTER CREEK - BWR BQUIPMENT FAILURE - EXPANSION JOINT IN IMERGENCY SERVICE WATER LINE J
The subject inquiry report is forwarded for your information..
We consider the licensee's action responsive; however, this matter will be reviewed during the next inspection. The licenses will submit a 10 day report to the Directorate of Licensing.
i R. T. Carlson
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Chief Reactor Operations Br.
LJ, Enclosures Subject Inquiry Report l
cc:
R. Minogue, RS (3)
R. S. Boyd, L (2)
,
R. C. DeYoung, L (2)
D. J. Skovholt, L (3)
l H. R. Denton, L (2),
,
'
P. A. Morris, RO H. D. Thornburg, 30 R. H. Engelken, RO RO Files
.
DR Central Files
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RO Inquiry Report No. 50-219/72-14 Subject: Jersey Central Power f Light Company License No.: DPR-16
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Facility: Oyster Creek - BWR
Title: Epipment Failure - Expansion Joint in Emergency Service Water Line
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Prepared byt.
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F. S. Cantrell, Reactor Inspector Date i
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Date and Manner AEC was Informed:
/
A.
i June 16, 1972, by telephone call from Mr. T. J. McCluskey, Station Superintendent.
B.
' Description of Particular Event or Ciretanstance l
While conducting a routine surveillance test to verify the operability of the contaitument cooling system in conjunction with a loss of outside power, the expansion joint in the discharge of the A b rgency service water ptamp ruptured. The containment emergency i
cooling is provided by two separate loops. Each loop has redundant
. heat exchargers with one emergency service water pump supplying each heat exchanger. Any one of the heat exchangers with its emergency service water pump is capable of removing the fission 546 process decay heat from containment.
C.
Action by Licensee:
The ruptured expansion joint was replaced and tested satisfactorily.
A visual inspection 6f the other three expansion joints did not show any problems.
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i 3944 JtiM 5 1972
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J. G. Kappler, (2itef, Reactor Testing & Operations Sr.
Directorate of Regulatory Operations, BQ
i RO INQUIRY REPORT No. 50-219/72-13
JERsEr CEwrRAL POWER & LISET COMPANY
OfSTER CREEK - BWR EQUIPMENT b8FICIENCY - RELIEF VALVE DISCHARGE PIPING
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The sehjeet inquiry report is forwarded for your information.
,
This is the first ooourrense at a BWR facility that we are erste of, and
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it provides additional statistics to substantiate oir concern regarding
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the generie espects of the problem. We, as well as JCP&L, were surprised l
st MPR's findings in that the relief valves have operated frequently without problems. According to JC76L, conservative calculations were
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medes however, they intend to affect the necessary modifications prior
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to startup. We consider this action to be responsive to the problent i
howevn, the adequacy of the fix has not been ascertained. A rel Fort
by t'as 11eensee will be submitted to the Directorate of Licensing.
We will stay abreast of this matter and keep you informed as appropriate.
Our inspector will also review this matter during the next routine inspection.
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R. T. Carlson
,
Chief, Reactor Operations Br.
.
Enclosures j
Subject Inquiry Report 1!
ect R. Hinogue, RS (3)
R. 5. Boyd, L (2)
i R. C. DeYoung, L (2)
D. J. Skovholt, L (3)
i H. R. Denton, L (2)
Office of Operations Evaluation, RO Asst. Director for Procedures, RO R. H. Engelken, RO g}
Regional Directors, RO V
RO Files DR Central Files
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RO Inquiry Report No. 50-219/12-13 i
Subject: Jersey Central Power & Light C y any License No.1_ DPR _16
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Facility: Oyster Creek - BWR Title: Equipment Deficiency - Relief Valve Discharge Piping
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j Prepared by:
F. S. Centre 11. Reactor Inspector Date
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A.
Date and Manner AEC was Informed:
!
June 2,1972, by telephone call from Mr. T. J. McCluskey, Station Superintendent.
)
B.
Description of Particular Event or Circumstance:
l Mr. McCluskey stated that a design evaluation has been made art the reaction j
i load in the discharge piping from the reactor safety valv,
- the pressure relief valves. This study, which was conducted by JCP6L's sultant, HPR Associates, indicated the supports might be over stressed when the relief valves are actuated. Additional supports were rar - dad for
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the relieY valve piping in the vicinity of the relief valves.
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Action by Licenseet
The licenses has been in contact with Licensing concerning their findings and stated suitable modifications would be made prior to reactor startup.
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