IR 05000219/1975004
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IE I Foro 12 (Jan 75) (Rev)
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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q 50-219 50-219/75-04 Docket No:
IE Inspection Report No:
t DPR-16 Jersey Central Power and Light Company License No:
Licensee:
Madison Avenue at Punch Bowl Road Priority:
C Morristown, New Jersey 07960 Category:
Location: Oyster Creek, Forked River, New Jersey Safeguards
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Group:
Type of Licensee:
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Routine, Unannounced Type of Inspection:
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January 29-31, 1975 Dates of Inspection:
January 14-15, 17 and 20, 1975 Dates of Previous Inspection:
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Reporting Inspector:
E. G. Greendan, Reactor Inspector Date
NONE Accompanying Inspectors:
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Date Date
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Other Accompanying Personnel:
Date A 4s Reviewed By:
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g/$/76 D. L. Caphton,' Senior Reactor Inspector
/ Date IE:1 Operations Branch
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n 9604230183 960213
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DEKOK95-258 PDR
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SUMMARY OF FINDINGS
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Enforcement Action A.
Violations None B.
Infractions Contrary to Technical Specification Table 3.1.1.H. 2, Isolation condenser high flow line break sensor 1B11A2 actuated in excess of 27 inches water during surveillance.
(JCP&L letter to Division of Reactor Licensing dated December 2,1974, Subject A0 74-60).
C.
Deficiencies Contrary to Technical Specifications 6.1.C.1.g and Administrative Procedure 102.8 " Standard Orders for Operations Personnel", Revision 1 dated August 19, 1969 the status and applicability of all stand-ing orders was not reviewed quarterly by the Plant Operations Review Committee.
(Details 2d)
Licensee Action on Previously Identified Enforcament Items Failure to distribute RWP to job location - Licensee is revising 1.
station procedures to be more explicit.
Item remains unresolved i
pending procedural revision.
2.
Failure to maintain average rate of reactor coolant temperature change with 100 F during a one hour period, during a cooldown -
Licensee has issued data sheets for plotting temperature heatup and cooldown and instructions to operating personnel.
Item remains unresolved pending incorporation of requirements in operating procedures.
Design Changes Not Inspected
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-2-Unusual Occurrences
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.N The following abnormal occurrences and events vere reviewed.
Comments concerning specific creas are noted within this report.
Failure of isolation condenser condensate high flow line break A.
sensor 1B11A2 to actuate within T.S. limits during surveillance.1 Failure of one reactor building to torus vacuum breaker valve to B.
demonstrate operability during quarterly surveillance testing.2 C.
A spent fuel shipment arrived at NFS, West Valley, N.Y. with re-ported cask external contamination levels on one smear of approxi-mately 22,000 dpm.
(Details 7)
Other Significant Findings A.
Current Findings 1.
Acceptable Areas i
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Plant Operations An audit of plant operations was conducted.
(Details 3 U44 and 4)
b.
Organization and Administration An audit of PORC and GORB activities as delineated in Section 6 of the Technical Specifications was conducted.
(Details 2)
2.
Unresolved Items Verification of GORB Committee qualifications.
(Details a.
2c)
B.
Status of Previously Reported Unresolved Items 1.
Development and approval of procedures for relay testing (IE Inspection Report 73-18).
Item is considered resolved.
(Details 6a)
1.
JCP6L Report to IE:I dated November 25, 1974, Subject A0 74-60 2.
JCP6L Report to IE:I dated January 9,1975, Subject A0 75-1
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-3-Management Interview
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{q A management interview was conducted on January 31, 1975 with Mr.'J. T.
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Carroll, Station Superintendent, Mr. D. Reeves, Chief Engineer and Mr.
J. Manning, Staff Engineer.
Mr. D. A. Ross, Manager, Nuclear Generating
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summarized below:
A.
General The _ inspector summarized the scope of the routine unannounced in-spection relative to a review of operating logs and records, PORC-
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meeting minutes, GORB audit results, GORB meeting minutes, verifi-cations of on and of f-site committee memberships versus Technical Specification requirements, a facility tour including observations
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of snubber inspections in progress January 30, 1975 and review of abnormal occurrences since the last inspection. The inspector also noted he had continued a review of ongoing spent fuel ship-ments from the site.
B.
Status of Previously Identified Enforcement Action 1.
RWP Distribution Requirements (IE Inspection 50-219/74-16 dated November 22, 1974)-
The inspector stated that he had reviewed the Radiation Safety Manual, and had no further questions regarding-this matter at this time.
The inspector further stated that the subject of RRP posting was considered unresolved pending formal pro-cedural revision.
2.
Cooldown Limits (IE Inspection 50-219/74-18 dated December 26,
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1974)
The inspector stated that he had reviewed data sheets prepared by the licensee for plotting reactor coolant temperature heat-up and cooldown and instructions and had no further questions regarding this matter at this time. The inspector further stated that this item was considered unresolved pending incor-poration of instructions into applicable operating procedures.
A licensee representative acknowledged the inspector's statements.
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Control Room and Shift Foreman-Logs
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- The inspector stated that his review of the referenced logs indi-r{:4l}
cated that more emphasis needed to be placed on entry completeness.
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--Shif t entries regarding assumption of duties and Shift Foreman entries were used as specific examples.
I A licensee representative concurred with the inspector's comments and stated that appropriate emphasis would be provided to the operating staff.
(Details 3)
D.
Administrative Procedures
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The inepector stated his position that the revised administrative procedures already written should be issued in a timely fashion
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to preclude procedural violations of the type identified during this inspection and enhance document control.
A licensee representative acknowledged the inspector's position and referenced the interface between the Administrative Procedures and Operating Procedures undergoing revision.
(Details 2f)
E.
GORB Qualifications
'NN The inspector stated that resumes of GORB members were not avail-able for on-site review to verify compliance with Technical Specification requirements.
A licensee representative stated that this information would be made available for on-site review.
(Details 2c)
F.
Enforcement Action The item listed under enforcement action above was identified as an apparent deficiency.
(Details 2a)
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e DETAILS j vJ cP'r
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Persons Contacted
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Mr. D. A. Ross, Manager, Nuclear Generating Stations Mr. J. T. Carroll, Station Superinteadent Mt. D. L. Reeves, Chief Engineer Mr. E. I. Riggle, Maintenance Supervisor Mr. J. P. Maloney, Operations Supervisor Mr. K. O. Fickeissen, Technical Supervisor Nt. E. D. Skalsky, Radiation Protection Supervisor
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Mt. J. Menning, Staf f Engineer
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2.
Administration and Organization Plant Operations Review Committee Meetings a.
The PORC met on the following dates and the minutes were re-viewed by the inspector. The inspector verified that committee meetings and actions were consistent with Technical Specifica-tion requirements except as noted.
Meeting No.
Date nP4 79-74 October 25, 1974 80-74 October 28, 1974 81-74 October 31, 1974 82-74 November 12, 1974 83-74 November 14, 1974 84-74 November 18, 1974 85-74 November 25-26, 1974 86-74 November 27, 1974 87-74 December 4, 1974 88-74 December 12, 1974 89-74 December 20, 1974 90-74 December 23, 1974 91-74 December 29, 1974 The inspectors review indicated that PORC had not reviewed the status and applicability of standing orders as stated in Administrative Procedure No. 102.8, Revision 1 dated August 19, 1969.
(DEFICIENCY)
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b.
General Office Review Board Meetings l *h The GORB met on the following dates and the minutes were if a reviewed by the inspector.
The inspector verified that committee meetings and actions were consistent with Technical Specification requirements.
l Meeting No.
Date 48A January 18, 1974
April 17, 1974
March 19, 1974
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March 20, 1974 50A March 29, 1974
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','u, 50B April 26, 1974
May 16, 1974
May 17, 1974
June 13, 1974
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August 6, 1974 53A August 19, 1974 c.
CORB Membership Qualifications
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Data was not available on site to demonstrate that members qgy of GORB, with regard to combined experience and technical specialties met requirements of the Technical Specifications.
e The inspector advised a cognizant licensee representative that this information should be provided on site. This item i
is considered outstanding and was discussed at the exit
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interview.
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Standing Orders and Required Reading Files *
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The inspector reviewed Standing Orders and Required Reading.
Updating had been completed and no obsolete material was maintained. Facility changes and revised procedures were current.
This item is considered resolved.
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Shift Turnover Procedures **
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The inspector reviewed Administrative Procedure Section 103, Revision 3 dated April 11, 1974.
Section 103.12.4-2 has been revised to include planned and or continuing maintenance
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activities that directly affect plant operation. This item is considered resolved.
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- IE Inspection Report 50-219/74-02, Detailo 7.b
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- IE Inspection Report 50-219/74-03, Details 4, dated April' 26,1974
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Administrative Procedures The licensee is rewriting facility procedures to achieve
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conformance with ANSI 18.7 and Regulatory Guide 1.33.
New Administrative Procedures have been written.
Implementation has not been completed.
This item was discussed at the exit interview and remains outstanding.
3.
Iogs and Records The following logs and records were reviewed without comment except as noted within'this report.
PORC meeting minutes - October 25 - December 29, 1974 a.
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GORB meeting minutes - January 18 - August 18, 1974 CORB audits - March - June 26, 1974 c.
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Shif t Foremans Log - November 8,1974 - January 26, 1975 Control Room Log - November 8, 1974 - January 26, 1975 e.
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Standing Orders Log - No. 1-20
Daily TS Logs - November 1,1974 - January 26, 1975 h.
Reactor Building Tour Check Sheets - November 1,1974 -
January 26, 1975 1.
Turbine Building Tour Check Sheets - November 1,1974 -
January 26, 1975
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Rod Waste Building Tour Check Sheets - November 1,1974 -
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January 26, 1975 The inspector's review of Control Room and Shif t Foreman Logs
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indicated non-uniformity in entries of different shifts.
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inconsistencies were discussed at the exit interview. This area remains outstanding.
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4.
Operations The inspector reviewed operating logs and records (Details 3) and held discussicas with operating personnel.
A tour of the facility was conducted and the inspector also observed ongoing seismic shock suppressor inspections in the reactor building. Logs and licensee actions appeared consistent with Technical Specification requirements.
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Primary Coolant System
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Disparity Between Recirculation Loop and Multipoint Recorder s
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Temperature Indications *
The licensee has issued instructions regarding log book entries to require an entry accompanying start of a recirculation pump and including differential temperature between the reactor coolant and the idle recirculation loop. The differential temperature is determined by subtracting the temperature.of the idle loop from the temperature of operating loops, as
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determined from the recirculation pump suction temperature recorder. This item is considered resovled.
6.
Emergency Power
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Relay Procedure Development **
a.
The inspector reviewed the licensee's Relay Check List and Test Procedure dated May 23, 1974, and procedural specifica-j tions concerning testing of differential monitoring relays.
Procedural requirements-included a return of all taps to position as indicated on relay setting sheets and requests This for relay testing through the cognizant Shif t Foreman.
A"d item is considered resolved.
b.
Standby Diesel Generator Fuel Tank Level
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The inspector verified from daily TS logs for the period
November 1, 1974 - January 26, 1975 that minimum levels established by the TS were maintained. The minimum level r
recorded was 14,878 gallons of diesel fuel.
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Fuel Handling
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Spent Fuel Shioment
The inspector reviewed the licensee's radioactive materials shipment record for shipment No. OC-30-75 dated January 28, 1975, and associated smear survey results involving approxi-mately.100 smears and 3 decontaminations of the NFS.4 cask.
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- IE Inspection Report 50-219/74-02, Details 5,. dated March 27, 1974
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- IE Inspection Report 50-219/73-15, Details 5, dated Getober 23, 1973
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The maximum contamination on the outer surface of the NFS-4 container was measured by the licensee to be 1,480 dpm-beta.
Cask arrival was reported by NFS with one smear indicating-l i
22,000 dpm.
Location had not been determined during the inspector's review.
The licensee was developing test data for a shipment scheduled for January 31, 1975 to provide data comparisons.
The inspector identified no unresolved or noncompliance items as a result of review of the licensees data or techniques. This item will be reviewed further during subsequent shipments.
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