IR 05000219/1979014
| ML19209C113 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/22/1979 |
| From: | Briggs L, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19209C112 | List: |
| References | |
| 50-219-79-14, NUDOCS 7910110557 | |
| Download: ML19209C113 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Rcport No. 50-219/79-14 Docket No. 50-219 License No. DPR-16 Priority:
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Category:
C Licensee:
Jersey Central Power and Light Company Madison Avenue at Puncn Bowl Road Morristown, New Jersey 07960 Facility Name:
Oyster Creek Unit 1 Inspection at:
Forked River, New Jersey Inspection conducted:
June 26-29, 1979 Inspectors:
f O b O)k, b Trl2t hct L. E. Briggs, Reactor Inspector cate signed Approved by:
f C #k.C4 L pln p,9 E. C. McCabe, Jr., Chief, Reactor cate signed Projects, Section No. 2, R0&NS Branch Inspection Summary:
Inspection on June 26-29, 1979 (Report No. 50-219/79-14)
Areas Inspected:
Routine, onsite, unannounced inspection by a regional based inspector (21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />).
Inspection Areas:
(4):
followup on previous inspection findings; in office review of facility event and periodic reports; event report followup; and I&E Bulletin followup.
Noncompliances:
None.
7910110 6 8 /
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DETAILS 1.
Persons Contacted T. Johnson, Instrument and Electrical Maintenance Supervisor D. Jones, Assistant Staff Engineer J. Maloney, Operations Supervisor
- D. Ross, Manager Nuclear Generation
- J. Sullivan, Chief Engineer The inspector also talked with and interviewed other members of the technical, engineering, and operating staff.
- Present at exit interview.
- Participated at exit interview via phone.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (219/79-06-03): Failure to follow Lifted Lead and Jumper procedure.
The inspector verified that corrective action as stated in the licensee's letter of June 4, 1979 had been completed by a sampling of lifted leads and jumpers compared to the Lifted Lead and Jumper Log.
In addition the Lifted Lead and Jumper verification per-formed by the licensee was reviewed and compared to the Lifted Lead and Jumper Log.
The physical verification was completed by the licensee on April 18, 1979.
The inspector did not identify any unacceptable conditions.
3.
In Office Review a.
NRC:RI in office review of the following LERs has been completed with no unacceptable conditions identified:
LER Dated Subject 79-07-3L 5/8/79 Failure of one torus to drywell vacuum breaker alarm.
79-08/3L 5/8/79 Trip of 'C' Recirculation pump while 'D'
loop was idle.
79-17/3L 6/15/79 Motor breaker trip on one parallel Core Spray Isolation Valve 1128 542
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LER Dated Subject 79-18/3L 6/15/79 Failure of one hydraulic snubber to
" Lock-Up" during testing.
79-19/3L 6/21/79 One Isolation Condenser high pressure actuation switch found set 3 psi above desired setpoint.
b.
NRC:RI in office review of the following reports was completed with no unacceptable conditions identified:
March 1979 Monthly Statistical Report
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April 1979 Monthly Statistical Report
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May 1979 Monthly Statistical Report 4.
Onsite Review The inspector performed an onsite review of selected Licensee Event Reports (LER) to verify the following:
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The report satisfies the reporting requirements of Technical Specifications; Events are accurately reported as to safety significance and
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actual occurrence of events;
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That corrective action taken was as stated in the report; and,
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That operations subsequent to the event were not in violation of regulatory or license requirements.
The following LERs were reviewed:
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LER 78-01/3L, Diesel Generator Trip due to High Engire Tempera-ture.
As a permanent corrective measure the licensee has performed a louver modification to both diesel generators.
The modifications were completed under Job Orders numbered 1173E and 1174E and satisfactorily tested by Special Procedure number 79-2, Louver Modification, Revision 0, March 9, 1979.
No unacceptable conditions were identified.
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LER 78-10/1T, Breaker Permissive Switch for 41600 Breaker S1B (startup bus breaker) Lift in the Trip Position.
The switch 1128 543
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was left in the trip position after Start-up Bus 1B cables were inspected by the J.C.P. and L. Company's Systems Operations Department.
The inspector verified that corrective actions stated in the report were implemented by a review of tne following:
Memo to W. Vierbuchen, Manager, J.C.P. and L. Systems
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Operations Department, June 23, 1978.
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Memo, Operations Supervisor to all Group Shift Super-visors, June 23, 1978.
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Revised procedures No. 337, 4160 Volt Electrical System, Revision 5, February 9,1979 and No. 338, 480 Volt Electrical System, Revision 5, February 1, 1979.
The licensee has also submitted Engineering Task No. 325-78 to incorporate control room alarms for automatically operated safeguards breakers.
At present alarms have been installed on eight (8) of the ten (10) breakers that will be modified.
The remaining bre:..s
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will be modified during the next scheduled shutdown. Reinspection will be accomplished at that time (79-14-01).
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LER 79-05/1T, Trip of 'C' Rec.irculation Pump with 'D' Recir-culation Loop Idle.
The inspector verified that corrective action was taken as stated by a review of Job Order No. 1073E and QASL No. 2301.
In addition, the vendor concurred with the licenee's finding that the failure was a variable potentiometer in the voltage regulator.
The inspector had no further questions on this item.
LER 79-12/3L, Oxygen Level Greater Than Five (5) Percent in the
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Suppression Chamber (torus).
The inspector verified that the Oxygen level in the torus was being maintained at three (3)
percent or less, as stated, by a review of Control Room Logs (Form 12-23, 1979) and procedure No. 312, Reactor Containment Integrity and Atmosphere Control.
No unacceptable conditions were identified.
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LER 79-14/1T, Closure of all Recirculation Loop Discharge Valves and Resultant LOW-LOW-LOW Level Alarm.
This LER was followed casite immediately after occurrence.
The inspector verified that action as stated in the report had been completed.
Details of the event and licensee corrective action are contained in inspector reports 50-219/79-10 and 50-219/79-11.
The inspector had no further questions on this item.
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LER 79-15/1T, Recirculation Pump Start With Greater Than 50
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degrees Differential Temperature between the Loop and Bulk Coolant Temperature.
The inspector verified that operator training and procedure revisione had been completed concerning this item.
Full details are contained in inspection reports 50-219/79-10 and 50-219/79-11.
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LER 79-09/3L, Failure of Reactor Building to Torus Vacuum Breaker to Operate due to Faulty Solenoid.
The inspector verified that the faulty solenoid valve had been replaced but further discussion with the licensee indicated that all solenoids would be replaced with a different type solenoid. The replacment solenoids will be ASCO, Nuclear Grade 4, way valves which appear to be more suitable to the service conditions.
The valves are on order (P.O. #52085) with a requested delivery date of August 1979.
They are scheduled to be installed during the next refueling outage.
This item (79-14-02) will be reinspected after component replace-ment.
LER 79-11/3L, Failure to Core Spray Pump N201A to Start due to
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a failed fuse in the Control Circuit.
The inspector verified that the defective fuse was replaced and that pump surveillance was successfully completed.
The licensee is sending the defective fuse to the vendor for analysis because of the odd method of failure (open to one end).
All circuit breaker control fuses are scheduled to be replaced during the next refueling outage.
In addition, analysis results will be factored into the circuit breaker preventive maintenance program.
This item (79-14-03) will be reinspected after completion.
5.
IE Bulletins Licensee actions concerning the following IE Bulletins were reviewed by the inspector to verify that the Bulletin was forwarded to appropriate onsite management, that a review for applicability was performed, infor-mation discussed in and licensee's reply was accurate, corrective action taken was as described in the reply, and that the reply was within the time period described in the Bulletin.
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IEB 79-09, Failure of Type AK-2, Circuit Breaker in Safety Related Systems, dated April 17, 1979.
The inspector reviewed the Preventive Maintenance Check Sheets for safety related systems and verified that trip bar bearings had been cleaned and lubricated.
This was 1128 345
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completed by the licensee on May 8, 1979.
The inspector reviewed procedure No. 761.2.003, Revision 1, April 10, 1979, 480 V Breaker Preventative Maintenance to insure adequate instructions were con-tained to prevent future failings of a similar nature and for agree-ment with GE SAL No. 175.
The inspector found no unacceptable conditions.
IEB 78-01, Flammable Contact - Arm Retainers in GE CR120A relays.
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The licensee has decided to replace all flammable retainers.
Re-placement was partially implemented during the last shutdown; however, several suspect retainers remain in control room safety panels 1F/2F, 3F and SF/6F.
The remaining retainers will be replaced during the next refueling outage.
This item (79-14-04) will be inspected after licensee action is complete.
6.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 29, 1979. The inspector summarized the scope and findings of '.he inspection as described in this report.
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