IR 05000219/1979003
| ML19263D495 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/09/1979 |
| From: | Briggs L, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19263D484 | List: |
| References | |
| 50-219-79-03, 50-219-79-3, NUDOCS 7903290289 | |
| Download: ML19263D495 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-219/79-03 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 Punch Bowl Road Morristown, New Jersey 07960 Facility Name:
Oyster Creek Unit 1 Inspection at:
Forked River, New Jersey Inspection conducted:
January 23-26, 1979 I
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w Inspectors:
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1.. E. Briggs y' Reactor Inspector date signed date signed date signed Approved by:
O ObOch,30 Q f 9 h3 E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2. RO&NS Branch Inspection Summary:
Inspection on January 23-26, 1979 (Recort No. 50-219/79-03)
Areas Inspected:
Routine, unannounced inspection of followup on previous in-spection findings; organization and administration; review of plant operations; IE Bulletin followup; and, in-office review of routine reports. The inspection involved 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at the corporate office and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> onsite by one regional based inspector.
Results:
No items of noncompliance were identified.
Recion I Form 12
_.90329c>f ff
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(Rev. April 77)
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Jersey Central Power and Light
12 FEB 1979 Company No reply to this letter is required; however, if you should have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, 4fb) %
E don'-J. Brunner, Chief Rhactor Operations and Nuclear Support Branch Enclosure:
Office of Inspection and Investigation Inspection Report Number 50-219/79-03 cc w/ encl:
J. T. Carroll, Station Superintendent A. Z. Roisman, Natural Resources Defense Council (Without Report)
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DETAILS 1.
Persons Contacted
- J. Carroll, Station Superintendent S. DeMerchant, Engineer Associate, ISRG Secretary
- I. Finfrock, Vice President, Power Generation
- E. Growney, Operations Engineer J. Riggar, Security Specialist
- J. Sullivan, Chief Engineer
+T. Tipton, Manager, Environmental Affairs, ISRG Coordinator Other licensee employees were also interviewed, including Group Shift Supervisors, Control Room Operators, Equipment Operators and Engineering Staff Personnel.
Present at the exit interview on January 23, 1979
Present at the exit interview on January 26, 1979
2.
Licensee Action on Previous Inspection Findinas (Closed) Unresolved Item (219/78-35-02):
Housekeeping of Emergency Diesel Fire Pump Building and poor condition of Diesel Fire Pump batteries and voltage regulator.
The inspector toured the Diesel Fire Pump building. The general area was clean and free of fire hazards.
Diesel Fire Pump batteries had been cleaned and terminals lubricated.
The Diesel Fire Pump voltage regulator mounting was repaired and properly mounted.
No unacceptable conditions were identified.
3.
Organization and Administration a.
Offsite Committees The inspector reviewed all resumes of the Independent Safety Review Committee (ISRG) and the General Office Review Board (G0RB) offsite committees to verify that membership and quali-fications were as required by Technical Specifications (TS).
b.
Findings During the review of resumes of assigned GORB members and designated alternates, it was noted that no member's resume specifically stated experience or training in two TS required areas, Radiological Safety and Radiochemistry.
Further examina-tion showed that the problem of Radiochemistry experience was
identified in the minutes of GORB Meeting No. 73, September 12, 1978, and that two memters did have such experience.
Radio-logical Safety experience is also noted as being held by one member in the GORB summary of expertise.
This item is considered unresolved (79-03-01) pending resume updating by the licensee and subsequent review by RI.
4.
Review of Plant Operations a.
plant Tour The inspector conducted tours of the accessible plant areas listed below at various times to observe the status of plant systems and conditions to observe activities in progress. The plant areas inspected included the Control Room, Turbine Building, accessible portions of the Reactor Building, a peri-meter walk down, the new Rad Waste Building and the Emergency Diesel Fire Pump Building.
The following were among the items observed and discussed:
Radiation controls properly established;
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Housekeeping, including attention to the elimination of fire hazards;
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No fluid leaks of significance;
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Pipe vibration, including the condition of hangers and seismic restraints;
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Status of preselected locked valves;
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Equipment tagging for compliance with administrative require-ments;
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Control room manning in accordance with Technical Specifi-cation requirements; and,
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Reasons for lighted annunciators in the Control Room.
During the plant tour the inspector noted several. areas that were previously posted as radioactively contaminated had been cleaned up and the posting removed.
The licensee stated that tnis action was a result of the newly implemented housekeeping control syste.
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The inspector also discussed the general operation and main-tenance practices used to ensure proper operation of portal metal detector equipment with the Site Security Specialist and the Station Superintendent.
No items of noncompliance were identified.
b.
Logs and Records The inspector reviewed the following logs and records:
Lifted Lead and Jumper Log (all active entries);
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Shift Foreman's Log, December 22, 1978 through January 24, 1979;
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Reactor Log, December 1,1978 through January 15, 1979;
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Equipment Status Log, December 1,1978 through January 15, 1979;
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Technical Specification Log Sheet, November 30, 1978 through January 5,1979;
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Reactor Auxiliary Logs, flovember 21, 1978 through January 10, 1979; and, Standing Order Book.
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c.
Findings During the review of the Lifted Lead and Jumper Log, the inspector noted that there were two Jumper Sheets numbered 139 and 140 but only one 139 and 140 entered in the Jumper index.
Further examina-tion revealed that, through administrative oversight, the second sheets numbered 139 and 140 had been numbered incorrectly.
However, all work had been completed, documented and the system returned to normal.
The licensee stated that the Lifted Lead and Jumper Log will be corrected and reviewed on a more frequent basis.
This item will be examined on a subsequent inspection.
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5.
IE Bulletin Review IEB 77-05 and Supplement 77-05A, Electrical Connector As-
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semblies, dated November 8 and November 15, 1977, respectively.
This item was reviewed in detail during inspection 50-219/78-28.
At that time one question concerning acceptability of connector temperature and pressure ramp times during testing was raised by the inspector.
NRC review, documented by memo-randum from E. L. Jordan, AD for Technical Programs, IE:HQ to E. C, McCabe, Chief, Reactor Projects Section No. 2, RI, dated Janua ry 18, 1979, found the connector testing performed by Wyle Labs acceptable in this case.
This item is closed.
6.
In-Office Review NRC:RI in-office review of the following reports has been completed with no unacceptable conditions identified:
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November 1978 Monthly Statistical Report
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December 1978 Monthly Statistical Report 7.
Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items or items of noncompliance.
The unresolved item disclosed during this inspection is discussed in Paragraph 3.b.
8.
Exit Interview The inspector met with licensee representatives (See Detail 1 for attendees) on January 23, 1979, and at the conclusion of the in-spection on January 26, 1979.
The inspector summarized the scope and findings of the inspection at this time.