IR 05000219/1979012
| ML19249E569 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/06/1979 |
| From: | Briggs L, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19249E568 | List: |
| References | |
| 50-219-79-12, NUDOCS 7910010782 | |
| Download: ML19249E569 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-219/79-12 Docket No. 50-219 License No. DPR-16 Priority:
Category:
C Licensee:
Jersey Central Power and Light Company Madison Avenue at Punch Bowl Road Morristown, New Jarsey 07960 Facility Name: Oyster C eek, Unit 1 Inspection at:
Forked River, New Jersey Inspection conducted: June 6, 1977 Inspector:
[
oM e:9[g/79 L. 2. Brigggf;R6 actor Inspector date sigrfed Approved by:
C C BOA.h-Bl 6 hi E. C. McCabe, Jr., Chief, Reactor date signed Projects Section No. 2, R0 & NS Branch Inspection Sumary:
June 6, 1979 (Report No. 50-219/79-12)
Routine, onsite, unannounced inspection by one regional based inspector (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) of two inspection areas:
followup on previous inspection findings; independent effort.
Noncompliances:
None.
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DETAILS 1.
Persons Contacted
- J. Carroll, Station Superintendent K. Fickeissen, Technical Engineer D. Jones, Staff Engineer J. Pelrine, Chemical Supervisor
'J. Sullivan, Chief Engineer The inspector also contacted other members of the technical, engineering and operating staff.
- Denotes those present at exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved (219/79-11-26) Procedural rerisions required due to Technical Specification (TS) changes.
The licensee, due to the May 2, 1979 event and IEB 79-05, made several procedure changes which were reviewed during IE inspection No. 50-219/79-11 and found acceptable.
During the 79-11 inspection, a TS change was pending which would affect several of the revised procedures.
Subsequent to the 79-U inspection, the inspector via telephone confirmed that all changes required were incorporated.
This was verified by a procedure review during this inspection. A listing of affected procedures is in IE Inspection report 79-11. The inspector had no further questions in this area.
(Closed) Unresolved (219/79-11-27) Degraded ECCS Bus Voltage. The inspector verified chat the degraded ECCS bus voltage condition, discussed in detail in IE report 50-213/7s ll, has been mitigated by the licensee. The licensee has issued a standing order (S0) to main-tain the 34.5 KV bus, by a remotely adjustable tap transformer, within a narrow band which will assure ECCS actuation.
The S0 also gives instruction to the operator to manually place the diesel generators on the emergency buses if 4160 VAC bus voltage decreases to a sustainea 3700 VAC which is above the minimum value to assure ECCS compc,nent operation.
The inspector also verified that 480 VAC transformer manual taps had been changed to tap 3 to give a nigher voltage profile.
The above methods are interim measures established by the licensee until a second level undervoltage trip can be installed during the 1979 refueling outage.
This aspect will remain open pending installation of the additional undervoltage trip (79-12-02).
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(Closed) Follow Item.
Review of Interim Valve Control Program.
The inspector verified by review of instrument loop diagrams and completed valve line-up verification sheets that the program implemented is as stated in IE inspection report No.
50-219/79-11.
The inspector found no unacceptabi. conditions.
(0 pen) Unresolved (219/79-10-11) Review of Chemistry and Stack Release Analysis Programs During Start-up.
The inspector reviewed the results of the coolant chemistry and stack release analysis and found that all results to 90% power correlate with previously known valves and a licensee derived Least Squares Fit Curve.
Although all data to date are acceptable, the program will not be complete until the above parameters are monitored for 14 days at 100% power.
Program results will be reviewed on a subsequent NRC:RI inspection.
3.
Independent Effort The inspector questioned the licensee concerning the 125VDC distribution system in the area of being able to detect an open circuit between the battery and the D.C. bus.
It was determined that the 'C' (new) battery had adequate indication by an annunciator in the control room if the battery breaker should open.
The 'A'
& 'B' (old) battery does not have such indication.
The problem as discussed with the licensee was that the battery breaker could be open without the operator being aware of the condition.
Should such a condition exist when an event occurred with a loss of off-site power, the battery changers would be lost and the battery would be disconnected from the bus.
At Oyster Creek, this would result in the loss of one-half of the 125VDC distribution.
The 'C'
battery is sufficient to supply necessary loads and insure ECCS operation, but redundancy is lost, should further complication occur. The licensee stated that battery rooms are checked each shift and that the abnormal breaker position would probably be noted. The licensee further stated that operations personnel would be instructed to specifically inspect the 'A'
'B'
battery breaker to insure it is correctly positioned. A design change will also be evaluated to annunciate the breaker in the Control Room. This area will be re-inspected during a future NRC:RI inspection (79-12-01).
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4.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 6, 1979. The inspector sumarized the findings, the purpose, and scope of the inspection.
The licensee acknowledged the inspector s findings.
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