IR 05000219/1978033
| ML19263B417 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/13/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19263B414 | List: |
| References | |
| 50-219-78-33, NUDOCS 7901180223 | |
| Download: ML19263B417 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No. 50-219/78-33 Docket No. 50-219 License No.
DPR-16 Priority
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Category C
Licensee:
Jersey Central Power and Licht Comoany Madison Avenue at Punch Bowl Road Morristown, New Jersev 07960 Facility Name:
Ovster Creek Unit 1 Inspection at:
Forked River, New Jersey Inspection conducted:
November 21-22, 1978 and November 28-Dece,tber 1,1978 Inspectors:
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L. E. Briggs // React 6r InspecL6r date signed
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date signed date signed Approved by:
f. O. k M, h w t.l q(3 p E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2, RO&NS Branch Insoection Sumary:
Inspection on Novembar 21-22, 1978 and November 28-December 1,1978 Report No. 50-219/78-33 Areas Inspected:
Routine, unannounced inspection of followup on previous inspection findings; review of plant operations; in office review of licensee event reports and review of routine reports; licensee event followup; and cleanliness. The inspection was started on the 4-12 shift on November 21, 1978, and consisted of 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> on site by one regional based inspector.
Results:
No items of noncompliance were identified.
7901180 D 3 Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- J. Carroll, Station Superintendent E. Growney, Operations Engineer R. Lang, Engineer II - Nuclear
- J. Molnar, Maintenance Engineer
- J. Sullivar., Chief Engineer The inspector also contacted other members of the technical, engineering, and operating staff.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Insoection Findinos (Closed) Unresolved Item (219/78-28-02): Completion of Job Order (J0) No. 0667E, Inspect and Tighten Electrical Connector Bell Housings. The inspector, after reviewing this J0, questioned what actions were actually performed.
Discussions with several licensee personnel and one Mobil Maintenance Foreman indicated that cable strain relief clamps had been tightened but not the connector bell housings. The licensee immediately reopened the JO and held a training session for the electricians selected to perform the task. At the training session a connector, similar in design to the ones in question, was used to explain connector construction and exactly what maintenance action was required. All required actions were completed prior to the completion of this inspection and the inspector had no further questions on this item.
(Closed) Unresolved Item (219/78-31-01):
Incomplete weld penetra-tion of CRD water quality flow control valve nozzel outlet flange.
The licensee removed the nozzel from the valve body and rewelded it to satisfy the requirements of ANSI B31.1-1973.
The inspector reviewed the following documents associated with the repair.
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Manufacturer's Record of Welder or Welding Operator Qualifi-cation Tests; We!d Procedure No. W-309-S;
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Weld Procedure Specification, QW 482;
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Liquid Penetrant Test, J0 No. Rlll, NDE request #3609, and
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Report No. 3609-Pl; and, Procedure No. 759.4.005, Leak Test Procedure, revision 1,
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December 15, 1975.
All documentation was complete and test results acceptable. The inspector had no further questions.
(Closed) Unresolved Item (219/76-28-03): Corrected response to IEB 77-06.
Initial licensee response to IEB 77-06 stated that megger tests of GE Electrical Penetrations would be scheduled and performed.
A subsequent GE document, G-EN-8-37, recommended that megger and hi-pot testing of penetrations not be performed. The licensee stated that GE's recommendation would be followed and a corrected response to IEB 77-06 would be submitted. The licensee later decided to continue performance of megger tests as per previous Preventative Maintenance and Maintenance schedules which were con-ducted during this refueling outage. The inspector had no further questions on this item.
3.
Review c' Plant Ooerations a.
Plant. cur The inspector conducted tours of the accessible plant areas listed below at various times to observe the stat.s of plant systens and conditions and to observe activities 'n progress.
The plant areas inspected included the Control Rcom, Turbine Building, accessible portions of the Reactor Builling, both new security buildings, and a perimeter walk down The following were among the items observed and discus;0d:
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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; Status of preselected locked valves;
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Equipment tagging for compliance with administrative
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requirements; Control Room manning in accordance with Technical Speci-
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fication requirements; Final plant startup tests and preparation; and,
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Reasons for lighted annunciators in the Control Room.
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No items of noncompliance were identified.
b.
Loos and Records The inspector reviewed the following logs and records:
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Lifted Lead and Jumper Log;
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Shift Foreman's Log, August 1, 1978 through October 31, 1978; Control Room Log, October 29, 1978 through November 28, 1978;
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Reactor Log, August 1,1978 through September 15, 1978;
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Equipment Status Log, September 1, 1978 through November 15, 1978; Technical Specification Log Sheet, August 1,1978 through
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November 9, 1978;
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Reactor Auxiliary Logs, August 1,1978 througn September 15, 1978; and,
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Standing Order Book.
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In addition the inspector reviewed several PORC meeting minutes to insure that quarterly review of all Standing Orders in effect was beirg performed as required.
The inspector also witnessed the performance of procedure No. 636.2.002, Revision 1, Diesel Generator Automatic Actuation Test. The first test was performed at noon on November 30, 1978, on Diesel Generator No. 1.
During the first test DG No. 1 failed to fast start.
DG No. 2 was tested satisfactorily on December 1, 1978 at 10:00 a.m.
At the completion of this inspection on December.1,1978, the licensee had not successfully completed testing of the No. 1 Diesel. A subsequent telephone call to the licensee on December 5 indicated that a problem was found in the DG No.1 governor and that testing was continuing satisfactorily.
No items of noncompliance were identified.
4.
In Office Review a.
NRC:RI in office review of the following LERs has been completed with no unacceptable conditions identified:
LER Dated Subject 78-14/03L 9/22/78 Loss of 230 KV supply to the auxiliary electrical power system.
78-22/03L 11/15/78 Failure of SBGTS II discharge valve to open.
78-23/03L 11/15/78 IRM 12 inoperable.
78-25/03L 12/1/78 Unmonitored release of radioactive water due to Condensate Storage Tank leak.
78-02/03L 2/17/78 Isolation Condenser 'B' outlet valve failed to open during routine testin.
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b.
NRC:RI in office review of the following report has been completed with no unacceptable conditions identified:
October 1978 Monthly Statistical Report.
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5.
Onsite Review The inspector performed an onsite review of selected Licensee Event Reports (LER) to verify the following:
The report satisfies the reporting requi, nts of Technical
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Specifications; Events are accurately reported as to safety significance and
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actual occurrence of events; That corrective action taken was as stated in the report; and,
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That aperations subsequent to the event were not in violation
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of regulatory or license requirements.
The following LERs were reviewed:
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LER 78-19/3L, Failure of reactor building to suppression chamber vacuum breakers. The inspector reviewed the events and corrective action taken through discussion with the licensee and a review of associated documents. The licensee has rebuilt both vacuum breakers during this outage using procedure No. 704.1.010 revision 0, performed under J0 1645M, completed October 23, 1978.
Data reviewed indicated that major components were replaced, valves were lubricated, adjusted, and extensively cycled to insure free movement and correct cycling times.
No unacceptable conditions were identifie.
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LER 78-21/lT, Core Spray System II Sparger Crack.
This event
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has been reviewed during three previous RI inspections (78-26, 78-28, and 78-31) covering the time of its discovery through completion of repairs.
During this inspection the inspector viewed a video tape of the installed clamp to verify correct installation. The film showed several aspects of the install-ation which satisfied procedural requirements
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The clamp installation levelness was verified by the use of a bubble level attached to the handling mechanism and clearly visible on the video tape.
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All locking caps were crimped sufficiently to prevent loosening of clamp retaining bolts.
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The clamp did not touch any nozzle weldments or sparger brackets.
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Clearance was available between the clamp and sparger brackets to allow for thermal expansion of sparger.
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Clearance of clamp halves to insure correct clamp bite on sparger was proper.
No unacceptable conditions were identified.
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LER 78-18/lT, Excessive Leakage through MSIV's.
Review of documents and discussions with the licensee identified the MSIV failure mechanism and repairs effected.
MSIV NS-03A was
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misaligned during previous maintenance causing excessive wear of poppet guide pads. This item was corrected by weld buildup Stellite 21 on the guide pads, with two independent installation alignment checks on reassembly.
The MSIV NS-04A seat crack was caused by Stellite 21 welded on the Stellite 6 valve seat during a previouc repair.
Dissimilar weld characteristics caused the seat to crack.
This was corrected by completely replacing the valve seat.
All MSIVs have since passed the containment Integrated Leak Rate Test satisfactoril.
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In addition, to preclude future failures of MSIVs NS-038 and NS-04B, the licensee intends to perform a complete inspection during the next refueling outage.
The inspector had no further questions on this item.
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LER 78-01/3L, Diesel Generator No. 1 trip due to high engine temperature.
The trip was caused by erratic operation of the louver control switch which caused the engine to trip on high temperature. The defective switch was replaced and the engine retested. To prevent recurrence the licensee has submitted an Engineering Design Request (EDR) which will incorporate a modified louver control system. The EDR has been approved and the licensee is waiting on parts to perform this modification.
In the interim period a Standing Order has been provided to give the operator positive steps to take if a similar failure should occur.
This LER remains open pending completion of the louver modi-fication and subsequent review by RI.
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LER 78-16/lT, Failure to inspect two Core Spray System hydraulic snubbers. On discovery of the missed snubber inspection the licensee performed the required inspection and found conditions acceptable. A possible corrective action is to replace these hydraulic snubbers with mechanical snubbers. An Engineering Request No. EA-11 has been implemented to consider this action.
If such replacement is not practical the licensee intends to submit a Technical Specification change to reduce the inspection frequency because of the high radiation levels in the areas.
This LER remains open pending licensee's action and subsequent review by RI.
6.
Cleanliness a.
The inspector reviewed the basic administrative procedures used to control plant cleanliness, AP 119, Housekeeping.
This review indicated that it is an effective procedure to ensure that the facility will be maintained in a clean, safe conditio.
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b.
The inspector discussed plant housekeeping with several personnel and determined that all persoras contacted were aware of the emphasis on housekeeping and of their responsibility in this area.
c.
As discussed in paragraph 3 above, based on a tour of the facility housekeeping at Oyster Creek Nuclear Generating Station is acceptable.
7.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on December 1,1978.
The inspector summarized the scope and findings of the inspection as described in this report.