IR 05000219/1972013
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U.'S. ATONIC ENERCY.Com!ISSION
DIRECTORATE OF REGULATORY OPERATIONS
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i REGION-I RO. Inspection Report No.:- 50-219/73-13-Docket No.:so_p39
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Licensce:
Jersey Central Poysr & Licht company License No.:DPR-16 Madison Avenue at Punchbowl Rond Priority:
Morristown. New Jersey Category:
C Location:
Oyster Crsek. Forked River.
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t Type of Licensee: 1930 M'4 ( t ) - BWR (G.E. )
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Type of Inspection: Routine. Unannoun.ed-
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Dates of Inspection: August 28-29. 1973
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Dates of Previous Inspection: Austust 3 and 6.1973'
Reporting Inspector:
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Edward <G. Greenman, Reac' tor Inapector Date
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Facility Operations Branch
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Accompanying Inspectors:
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J Donal L. Caph n,Seflof l
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Dak 0 Reae
't Inspeo r (Aug
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AW Q uut it)
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dary Sn r, Redctor Ir[pector
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(Augus, 29, 1973)
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Other Accompanyinr, Personnel:
None e'
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Reviewed by::
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Dona 1d L. dapht n, SMndofReactorfnspector
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I Facility Operat ons Bra e.
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960'4150000 960213
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PDR-FOIA DEKOK95-258 PDR e
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m Summary of Findings
Enforcement Action Violations A.
Technical Specification 4.4. A.2 - Failure to verify Core Spray motor operated valve opernbility on a monthly basis as required.
(Report Details, Paragraph 6.a.2)
3.
Technical Specification 3.6.C - Failure to maintain the maximum amount of radioactivity, excluding tritium noble gases and iso-topes with t % < 3 days contained in outside rad-waste storage tanks less than 10 euries.
(Report Details, Paragraph 7.d)
Safety Items Radiological safety control practices - Failure to routinely calibrate survey instruments used to detect and measure radioactivity for the purpose of personnel protection on a quarterly basis.
(Report Details, Paragraph 7.a)
Licensee Action on Previously Identified En forcement Items A4'd Not inspectad.
Unusual Occurrences A.
Failure of the No. 1 Diesel Generator to start during a routine six month tent.
(JCPL letter to Licensing dated August 17, 1973 (Abnormal Occurrence No. A073-17)
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B.
Fish kill attributed to thermal shock caused by high tempera-tures following a dilution pump trip.
(JCPL letter to Directorate of Regulatory Operations, Region 1 dated August 31, 1973.)
(Report Details, Far,grsph 8)
C.
High activity in outside rnd-weeie storage tanks.
(JCPL lettar to Licensing dated Augant 31, 1973 (Abnormal Occurrence :1o.
A073-18) )* (Management Intervi-w, Paragraph C; Report Detai]r, Paragraph 7.d)
- A ravi-w of r cords and discuaniens with licanmaa representatives indicatad that eventn nel carractiva action was as stated in the licennae's lettar(s).
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-2-Other Signifiesnt Findings A..
Current Findings
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1.
Fuel Densification Core power distribution and power level was adjusted on August 24-25 in accordance with Change No. 16 to the Tech-mical Specifications dated August 24, 1973 (Report Details, Paragraph 3.b)
2.
CRD Accumulator Surveillance Accumulator level and pressura switches were last calibrated in April, 1968.
(Report Details, Paragraph 5.a; Management Interview, Parngraph B)
B.
Status of Previous 1.v Reported Unresolved Itema Not inspected.
Management Interview An exit interview was conducted August 28, 1973 with Messrs. Reeves',
Sullivan and Riggle.
Nr. Caphton and Mr. Snyder were also present rqu representing the Directorate of Regulatory Operations, RO:1.
Items discussed are sumor-d zed below:
A.
General-The inspector summarized the scope of the inspaction, relative to the licensee's setions with respect to Change No. 16 to the Technical Specifiestions, circumstances related to a fish k411 which occurred August 9, 1973, abnormal occurrencen since the last innpection, surveillance records for the Emergency Cooling i
Systems, survey instrument calibrations, and CRD accumulator surveillance.
B.
, Control Pod Drive Accumulator Surveil 1<nce The inspactr;r statad hir, understandir.g baned on previous dis-cussians witl licena** raprasentativas that a procedura would
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be prapared, s PC RC review conducted, survaillance fraquency
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- ietirg llant Sup-rintandant l
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o-3-and acceptance criteria entablished, and prensur-and level switch calibrations performed.
A licensee representative ntated that the inspector'n under-standing was correct.
(Report Details, paragraph 5.a)
C.
Ongoing Violatten of th-Technical snecifications Section 3.6.C -
High Activity in outside Rad-Waste Tanks The inspectors stated concern regarding the extended time intarval required to return activity levels in the outside rad-waste surge tank to within Technical Specifiention limits.
An inspector further noted that the bases for the Technical Specification requires action to be taken on a timely basis to avoid exceeding the limit.
A licensee representative stated that decontamination work was going on at this time and that processing would continue as rapidly and effectively as possible.
The licensee represen-tative further stated that Regulatory Operations (RO:1) would be notified when surge tank activity levels were within limits.*
An inspector stated that this viointion further identified the rad-waste problem at the facility and emphasized the necessity for management involvement to recognize the severity of this
,.y problem.
A licaqraa repr-castative neknowledged the inspector's remarks i
and stated that evaluatican conc-rning nodifications to tha rndioactive waste facility were being conducted.
3.
The inspector identifiad the following apparent violations and sa fety itena.
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Viola tion - Failure to conduct monthly operability veri-fication for Core Spray motor operated valves as required by Technical Specification 4.4.A.P.
(Report Details, paragraph 6.m.2)
2.
Safety Item - Failure to parform routine calibrations of survey instrumants on a quarterly basis.
(Report Detniin, Paragraph 7.a)
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' Noti "ie n tion was subs-qu-r.tly provid ad to the assigned inspactor j
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by talephone on 2*ptembar 4, 1973
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-4 E.
De ficiencie s Identified in Health Thysics Instrument Calibration Documentation
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An inspector stated that a review of procedures and calibration records had disclosed certain deficiencies which required resolution.
The inspector further stated he had discussed these deficiencies with a cognizant licemmae representative and obtained commitments regarding resolution.
A licenr.ee representative statei that he was aware of those commitments and that he concurred with them.
(Report Details, Paragraph 7.b)
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Plant Audit System An inspector stated his position based on a limited sampling basis that the internal audit system should be examined to provide assurance that surveillance testing requirements are met.
The inspector further stated that all surveillance records should be examined to assure adequate documentation as required.
A licensee representative acknowledged the inspector's remarks.
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-9-DET AILS
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Persons Contacted Mr. D. L. Reeves, Operations Supervisor
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Hr. J. L. Sullivan, Technical Supervisor Mr. E. I. Ri6gle, Maintenance Supervisor Mr. D. E. Kaulback, Radiation Protection Foreman
Mr. R. Stoudnour, Chemical Engineer (Environmental)
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., M r -. C. Fickiessen, HP Staff. Engineer l
Mr. E. Growney, Technical Engineer Mr. 3. Griffiths, Cadet Engineer.
2.
' Administration and Organization a.
Personnel Changes
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Three associato engineers and two engineering assistants have been added to the sta ff since January, 1973 b.
Operator Complement The operatin6 stnff consists of four shift foremen and
"#"I three management representatives (all licensed senior reactor
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i operators), eight control room
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"B" operators and e1 ht operators in training (all licensed reactor oper-
ators), two non-licensed operating foremen, and fourteem i
mon-licensed equipment operators.
A licensee representative
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stated that jobs had been posted for selection of four operating foremen.
The inspector was informed that personnel selected would be capable of li:emaing as senior reactor
operators.
c.
Status of Certified Health Physicist
Interviews to fill the position of certified Health Phy-sicist at Oyster Creek are continuing.
No selection had been made at the time of this inspection.
Fseility staffing requirements were discussed with a licensee representative.
d.
Plant Cparating Review Committee (PORC)
Minutes of PORC meetings "o.
73-11 through 73-29 held April 11, 12, 14, 20, 24, 26, May 7, 11, 12, 22-25, June 1,
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-6-14,,21 and 25, July 12, 19, 21, 30 and August 6 and 13, 1973 were reviewed on a sampling basis.
Meetings were sonducted within frequency requirements of machnical
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Specification 6.C.b.
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Logs and Records The following logs and records were reviewed without comment except as noted within this report.
a.
Emergency Cooling System surveillance records January -
August 16, 1973 b.
Control Room Log Book - June 2, July 19, August 24-29, 1973
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c.
Technical Specification Log and Work Sheet for T.S. 310 -
August 28-29, 1973 d.
Power Data Results - August 6 - August 29, 1973 e.
HP Survey Instrument Calibration Log - July, 1972 - July, 1973.
f.
Survey r6'sults RS No. 676-73 dated August 28, 1973 and l
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Surge Tank Surveys - August 22-28, 1973 kNE 4.
Operations The reactor was operated at approximately 98% of rated power from August 6 - August 24, 1973 The licencee received an order by the Director of Regulation changing the Technical Specifications of License No. DPR-16, dated August 24, 1973 at approximately 4:45 P.M. on August 24.
Power level was
adjusted from 97 5% (4:45 P.M.) to 931% (6:00 P.M.) to comply
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with Change No. 16 to the Technical Specifications.
During the time period August 25 - August 29, 1973 (conclusion of inspection) power level was varied from 90 5% - 93.68% and records indicated established average planar LHGR and local
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LHGR limits, were not exceeded.
5 Reactivity Control and Core Physics n.
Control Rod Drive (CRD) Accumulator Instrumantation Surveillance
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-7-The inspector conducted a review of surveillance re-quirements regarding aceumulator level and pressure switch
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ealibrations and identified several deficiencies which J,
required resolution.
The apparent deficiencies and the licensee response to these items was a follows:
Deficiencies:
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(1)
A surveillance procedure had not been prepared for calibration of pressure and level switches associated j
with the accumulator units.
(2)
The last calibration of these sensors was performed-i
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November 7, 1968.
Licensee Response A licensee representative stated that a surveillance sal-ibration procedure would be prepared, PORC review completed and frequency and acceptance criteria established.
This item was also discussed at the exit interview.
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Fuel Densification*
Licensee's action was as described in JCpL letter to the Directorate of Licensing dated August 27, 1973 The gg licensee has generated a new procedure (Standing Order No.
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18) dated August 29, 1973 for calculating the local linear heat generation rate and the averaga planar linear hect generation rate.
T.S. 4.10 dated August 24, 1973 requires-a daily check of average planar LHGR and local LHGR.
The inspector reviewed calculations for the period August 25-29.
Results indicated limits for fuel types I, II, III
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and IIIB were not exceeded.
Records indicated the limiting condition for Type III and IIIE fuel.
MApLHGR values j
varieu from 9 042 - 10.17 Local LHGR varied from 11.66 -
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Discussions with licensee representatives and records reviawed indicated that power was reduced on August 24, 1973 and full core power distribution data accumulated.
Tip Traces were completed and power was further reduced
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to 90 5% (582 MWe).
On August 26, 1973, further power distribution data and tip traces were completed.
On August 27, power was incr-ased to 93 25 (600 MWe).
' Letter from Directorate of Licansing to JCpL dated August 24, 1973
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Emergency Core Cooling Systens Surveillance ecords concerning the fol~ ewing systems and
components for the time intervals referenced were reviewed by the inspector in accordance with requirements of the
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Technical Specifications (T.S.).
Deficiencies identified were as noted below:
a.
Core Spray System (1)
Pump Operability Tests - January 1 - August 16. 1973 Surveillance results for testing conducted June 2, 1973 were unavailable for the inspector's review.
Control Room Log entries indicated this test had been conducted as r quired by T.S. h.4.A.l.
Deficiencies in the licensee's record keeping and management audit system were discussed with e licensee representative.
(2)
Valve Operability - January 1 - August 16, 1974 Surveillance results for testing conducted July 19, 1973 were unavailable for the inspector's review.
Control Room Log entries indicated this test had been conducted as required by T.S. 4.4.A.2.
Deficiencies 9* 6 in the licensee's record keeping and management audit system were discussed with a licensee representative.
No documentation was available to indicate a monthly operability test had been performed between April 26 and June 21, 1973.
(The reactor was returned to power following a refueling outage from April 13 - June 4, 1973.)
T.S. 4.4.A.2 specifies a monthly test frequency.
Discussions with a licensee representative indicated testing was not completed as scheduled due to a hydro test in progress.
This item was also discussed at the exit interview.
(Violation)
(3)
Automatic Actuation Test - January 19 - August 15. 1973 Surveillance records indicated tenting was performed as required by T.S. 4.4.A.3
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Pump Compartment Water Tight Door Closure - May 25 -
August 21, 1973
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Verification was provided on a daily basis and following
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entry.
T.S. 4.4.A.4 specifies a weekly frequency.
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(5)
core Spray Header Differential Pressure Instrumen-tation - January - July, 1973 Calibration was completed February 5 April 28, and July 20, 1973 as required by T.S. 4.4.A.5 b.
Automatic Depressurization (ADS) - May 28, 1973 Surveillance records indicated a valve operability and auto actuation test was completed during the last refueling outage as required by T.S. 4.4.B.
Previous testing was conducted flovember 7,1971.
c.
Containment Cooling System - January 12 - August 23, 1973 (1)
Pump Operability Surveillance records indicated testing was performed monthly and on May 30, 1973 prior to startup following the refueling outage as required by T.S. 4.4.C.1.
(2)
Automatic Actuation - January 12 - July 26, 1973 i
A review of surveillance records indicated testing was j
performed as required by T.S. 4.4.C.2.
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(3)
Pump Comnartment Water Tight Door Closure - !!ay 1 -
August 14, 1973 A review of tour checkoff sheets indicated that verification was provided daily and after entry.
T.3. 4.4.C.3 specifies a weekly frequency.
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Emergency Service Water System i
(1)
Pump Operability - January 12 - August 23. 12Z}
A review of surveillance records indicatet
.Ap operability was verified monthly and prior o startup following the refueling outage as required by T.S. 4.4.D.1.
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Automatic Actuation Test - January 12 - July 26. 1973 A review of surveillance records indicated testing was performed as required by T.S. 4.4.D.2.
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Control Rod Drive Hydraulic System - January 22 - August 6. 1973 i
A review of surveillance records indicated testing was performed as required by T.S. 4.4.E.1.
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Fire Protection System - January 23 - August 7. 1973 A review of Pump and Isolation Valve Operability Surveillance indicated testing was performed as required by T.S. 4. 4. F.1.
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Radiation Protection hiS
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a.
Instrument Calibration Procedure The inspector conducted a review of HP Procedure 904.11
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revision dated October 12, 1972.
The procedure specifies all portable monitoring survey meters will be calibrated within a six (6) month interval and/or following main-tenance.
The procedure specifies a monthly review of all l-instrumentation for the last calibration date, removal
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from service of any instrument that had not been calibrated satisfactorily, and further specifies that any instrument satisfactorily calibrated within the last five (5) months shall be left in service.
Records of calibrations are to be maintained on Radiation Protection Record Forms.
A licensee representative was apprised of the inspector's position that generally acceptable practice is a calibration of instruments on a quarterly basis.
(Safety Item)
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b.
Survey Instrument Calibration Log
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The inspector conducted a review of the Survey Instrument Calibration Log for the period July 1972 - July 1973 and identified several apparent deficiencies wnich required resolution.
The apparent de ficiencies which were identified and the licensee's response to those items are as follows:
Deficiencies:'
(1)
Instrument statua cheets were found to be incomplete.
(2)
Radiation Protection Record Forms were not complete and updated.
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(3)
Out of Service Radiation Protection Forms were not properly complete and updated.
(h)
Instruments to be calibrated secticu was inconplete.
Licensee Response:
A licensee representative ntated that corrective action would be taken with respect to record completion and review of log book requirements.
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The inspector informed a licenset representative that deficiencies of this type reflected negatively with respect to a good, well managed program.
c.
Instrument Calibrations The inspector reviewed calibration results for the period July 1972 - July 1973 encompassing 20 portable survey instruments.
Calibrations were performed in accordance with procedure 904.11 frequency requirements.
d.
Gurvey Readings (Outside Rad Waste Storage)
(1)
Perimeter Fence Readings The inspector reviewed survey results (RS No. 676-73
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dated August 28, 1973 Results indicated that readings at the perimeter fence varied from 0.1 - 0.2 mr/ hour.
No readings in excess of 10 CFR 20 limits for an unrestricted area were observed.
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Cutside Waste Surge Tank The inspactor reviewed survey results enneerning activity i
levels in the outside waste surge tank for the period August 22-29, 1973.
The highest observed reading was 2 7 R/ hour at contact.
During a subsequent tour of the area the inspector observed that the area around this tank had Lsen~ posted and a barricade installed (rope barrier).
The inspector waa informed by a licensee
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representative that this area is permamently posted as a high radiation area.
8.
Miscellaneous Fish Mortalities - August 9. 1973 a.
Pump Trip and Restart The fish kill which occurred on the afternoon of August 9, 1973 was attributed to high temperature in the discharge 4gj eanal resultin7 from a dilution pump trip.'
The inspector's review of circu.. stances surrounding this occurrence indi-cated the following:
(1)
The licensee was unable to restart the tripped pump due to a low water level switch actuation.
(Float switch)
(2)
Grating was partially lifted at the No. 2 dilution pump and no attempt was made to start this camp.
(3)
The No. 3 dilution pump was not started immediately in that seal water had been valved out to the pump.
This event apparently resulted in a 29 minute delay between the No. 1 pump trip and a subsequent startup of No. 3 (4)
Records reviewed and discussions with plant personnel indiented the bridge temparature reached approximately 99* F.
'JCPL letter to the Directorate of Regulatory Operations,. Region
dated August 31, 1973
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Pump Capabilities The inspector was advised by a cognizant licensee rep-sentative that it is not unusual to experience pump trips.
,,,f f; Plant records indicated a pump trip occurred August 10, 1973 t
and a pump was restarted in about 5 minutes.
Discussions with a licensee representative indicated that dilution pumps have no automatic starting capabilities.
Licensee's Corrective Action to Prevent Recurrence c.
The licennee has taken the following steps to prevent similar occurrences:
(1)
Bypasses have been installed around low level switches to permit a startup sequence.
(2)
Seal water is now continuously provided to the pumps.
(3)
An alarm has been installed in the control room to annunciate a bridge temperature of 93* F.
(4)
A memorandum has been issued to shift formen dated August 10, 1973 requiring utilization of a second dilution pump if temperature increases to 95* F.
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Tempora ry Temperature Monitoring in Canal The inspector was accompanied by a licensee representative
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tour of the dilution pump and canal area.
The inspector on a
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was in formed tha t temporary temperature monitoring about 75 feet out into the discharge canal had been installed on August 10, 1973.
The inspector observed a reading of 100* F. on August 28, 1973 obtained from this equipment.
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- UNITED STATES
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ATOMIC ENERGY COMMISSION
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WASmNGToN. D.C. 20545
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H. D. Thornburg, Chief, Field Support and Enforcement Branch, R0 0YSTER CREEK - DOCKET NO. 50-219 - MALFUNCTION OF BOTH DIESEL CENERATORS'
FOLLOUIWG A LOSS OF POWER l forfrevieu of This. memo is in. response to H. D. Thornburg's request the above incident and our assessment of the related generic and safety
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implications. The licensee reported that both diesel generatora (DG)
failed to restart after a power loss to the essential 4160 V buses following a "faststart" and subsequently a DG unit "stop" signal from the control room.
Investigation into the problem disclosed a design
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deficiency in the interlocking of the failure-to-start and auto-start
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circuitry of both DG units.
During our discussions with the DG manufacture (General Motors) another design deficiency was noted in the licensee's planned modification to the logic circuitry.
Accordingly, General Motors informed the licensee of this latest development and the work effort touard implementing the circuit changes uere subsequently terminated.
Further efforts are new underway by the manufacture to correct the restart problem.
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We recommend that Region I follow up on this matter to ascertain the
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specific corrective measures that. are taken to resolve the problem.
In order to complete our review of the fix, we will need a copy of the electrical drawing which show the circuit modifications. Please arrange with Region I to forward a copy to us.
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With regard to the related generic implications, General Motors stated that OC f1 is the only nuclear station utilizing this make and model
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diesel generator. On this basis, we do not believe the problem concerns r
other licensees.
Picase advise, when we can be of further assistance on this matter.
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'G 1. Reinmuth, Chief y Technical Assistance Branch, R0 cc: B. H. Grier J. G.' Davis D. Caphton, RO:I
/,J.P.O'Reilly,RO:I
Action Control Form FO-175, Thornburg to Reinmuth, dated 9/27/73.
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2 Lice.nsee's letter'to Licensing dated 9/18/73 Concerning Events Related'to'the' Subject Power Failure.
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