IR 05000298/1980015
| ML19345B088 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/21/1980 |
| From: | Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19345B087 | List: |
| References | |
| 50-298-80-15, NUDOCS 8011260106 | |
| Download: ML19345B088 (5) | |
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U. S. NUCI. EAR REGULATORY CO!2 FISSION
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0FFICE OF INSPECTIO.V AND ENFORCEME.VI*
REGION IV
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Report No.
50-298/80-15 Docket No.
50-298 License No. DPR-46 Licensee:
Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection conducted:
September 29 - October 2, 1980
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. G. Spangler,eReactor Inspector Date
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Reactor Projects Section No. 1 t/Ah fo/Jr)38 Approved by:
i T. F. Westerman, Chief 4) ate Reactor Projects Section No. 1 Inspection Summary Inspection on September 29 - October 2, 1980 (Report No. 50-298/80-15)
Areas Inspected: Routine, unannounced inspection of followup to previously identified items, audit program, audit program implementation, and followup on LER's.
This inspection involved 24 inspector hours on site by one NRC inspector.
Results:
No items of noncompliance or deviation were identified.
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i DETAILS 1.
Persons Contacted Nebraska Public Power District L. F. Bednar, Electrical Engineer P. F. Doan, Mechanical Engineer
- L. C. Lessor, Station Superintendent C. R. Noyes, Technical Assistant to Station Superintendent J. Scheer, Electrical Engineer G. Smith, QA Specialist F. Williams, QA Manager V. L. Wolstenholm, Quality Assurance Supervisor
- Indicates presence at exit meeting.
2.
Followup on Previously Identified Items (Closed) N-8009-5 (Item of Noncompliance, Inspection Report 80-09, paragraph 7c): Open pails of oil stored in the HPCI pump room.
The training sessions conducted in reponse to this item of noncompliance have been completed.
(Closed) N-3011-2 (Item of Noncompliance, Inspection Report 80-11, para-graph Sa): Fire door to HPCI pump room left propped open.
This item was addressed in the training sessions conducted in response
to the item of noncompliance noted above.
3.
Audit Program The objective of this portion of the inspection was to verify that the scope of licensee's Quality Assurance (QA) audit plan had been defined and that it was consistent with the commitments of MPPD's Quality Assurance Plan for Operations. The QA program document and implementing Quality Assurance Instructions where reviewed by the inspector to deter-mine that responsibilities had been assigned in writing for the overall management 'and conduct of the QA audit program in accordance with the ANSI standard N45.2.12 - 1974, Requirements for Auditing of Quality Assurant.e Programs for Nuclear Power Plants.
The inspector found that the responsibilities for the QA audit program
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had been assigned by position and with the exceptions noted below the requirements of ANSI N45.2.12 have been implemented in the following l
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QAI-5 General Guidelines - QA Audits QAI-6 Personnel Qualification and Training for QA Assignments QAI-12 Guidelines for Audit Frequency and Scheduling During this review the inspector noted that QAI-6 contains requirements for the selection of personnel for the positions of Quality Assurance Specialist and Quality Assurance Engineer. However, no formalized training program is established and the area of retaining or maintenance of proficiency is not addressed.
In addition, QAI-6 does not delineate
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the method for the qualifiestion of auditors and lead auditors.
The licensee's current practices are such that the station QA personnel meet or will meet the requirements of paragraphs 2.3, Training; 2.4, Maintenance of Proficiency in ANSI N45.2.12.
Furthermore, the QA Manager in an internal memorandum has directed that qualification of lead auditors is to be done in accordance with paragraph 2.3 of ANSI N45.2.23, Qualification of QA Program Audit Personnel for Nuclear Power Plants.
In discussions with the QA Manager, the inspector indicated that QAI-6 could be strengthened by including the current practices in the instruction to formally implement the requirements delineated in ANSI N45.2.23, para-graphs 2.2, Qualification of Auditors, and 2.3, Qualification of Lead Auditors and paragraphs 2.3 and 2.4 of ANSI N45.2.12.
This item will remain as an open item (80-15-1).
The inspector also noted that Quality Assurance Instructions to formally implement the QA Surveillance function described in paragraph 4.1.3.(a)
of the NPPD QA program document do not exist; although, the site QA staff is performing and documenting this function.
This item will remain as an open item (80-15-2).
No further items were identified in this area.
Audit Program - Implementation The purpose of this portion of the inspection is to ascertain that the licensee is conducting routine -audits by qualified personnel in accordance with the commitments of the NPPD QA Program for Operations.
The inspector reviewed selected audit reports to determine:
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That they were scheduled in accordance with the instructions of QAI-12, Guidelines for Audit Frequency and Schedule, b.
That they were conducted in accordance with written procedures or checklists,
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That they were conducted by impartial and trained personnel,
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That the results were documented in a report and reviewed by the audited responsible management and that they responded in writing to the findings of the audit, and That followup actions were scheduled as necessary.
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The inspector reviewed the following audit packages:
Audit No.
Date Area 80-02 QAP-300 1/11/79 - 2/1/80 New Fuel Inspection 80-05 QAP-300 3/7/80 - 6/12/80 Refueling 80-10 QAP-201 6/4/80 Setpoint Changes 80-10 QAP-201 6/6/80 Jumper Log 80-03 QAP-202 2/80 T aining 80-04 QAP-1700 2/4-15/80 Design Change 30-12 QAP-900 6/13/80 Chemistry 80-06 QAP-700 4/15-16/80 Nonroutine Main-tenance - Torus
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Modifications Followup audit packages for audits 80-04, 80-06, and 80-12 were also reviewed. No deviations from the acceptance criteria noted above were identified. However, the inspector did note that there appeared to be no formal mechanism to track completion of actions for audit findings corrected during the audit and when as a consequence of this no followup audit is scheduled. This item will remain as an open item (80-15-3).
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Fellowup on LER's LER's 80-06 and 80-32 were briefly discussed with the appropriate plant staff and the corrective actions as reported appear to be appropriate.
Inspection followup for these LER's is completed.
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The following LER's were discussed in more detail with the appropriate members of the plant staff.
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80-22 Failure of the Reactor Building Inboard Throttle Isolation j
S0-22-1 Valve RHR-M0-57 to close.
(Closed)
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The licensee found upon disassembly of the valve that the seat had unthreaded from the valve body and lodged itself between the disc and the valve body. A new valve seat was installed and tack welded into place.
After conferring with the valve manufacturer it appears that the in-stalled valve is not designed for throttling purposes.
When used in a throttling mode the design of the valve disc is such that excessive chatter occurs. This was apparently the root cause of the failure. A replacement valve has been ordered and will be installed.
This appears to be a problem peculiar only to this particular vlave.
80-30 Failure of RER-MO-34B, The 'B' Loop Suppression 80-30-1 Pool Cooling Throttle Valve, to Operate.
(Closed)
The cause of this malfunction was the failure of the key on the motor shaft pinion gear. The key was replaced and the failed key was sent to the vendor for analysis. The vendor determined that this failure was due to the use of the wrong key stock. All sizes of Limitorque operators use standard key stock except for sizes SMB-3, 4 and 5 '<hich required a hardened stock. This operator is a Limitorque SMB-4.
The operator was again disassembled and a key from the proper type of stock was installed. A review of maintenance records for all SMB-3, 4 and 5 operators installed indicates that no work had been done on any other operator that would require replacement of this key.
The plant main-tenance procedure addressing Limitorque valve repair has been modified to include this information.
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Exit Interview An exit interview was conducted at the conclusion of this inspection. The above findings were identified and discussed with the Station Superintendent.
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