IR 05000354/1980018
| ML19345F039 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/05/1980 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345F033 | List: |
| References | |
| 50-354-80-18, 50-355-80-18, NUDOCS 8102060566 | |
| Download: ML19345F039 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-354/80-18 Report No. 50-355/90 19 50-354 Docket No. En 1RR CPPR-120 License No. CPPR-121 Priority
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Category A
Licensee:
.blic Service Electric and Gas Company 80 Park Place
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Newark, New Jersey 07101 Facility Name:
Hope Creek Generating Station, Units 1 and 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted November 12-14. 1980 Inspectors:
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. A. Mdfirearty, Reactor Inspector date signed
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date signed date signed
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/2[,f/fd Approved by:
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ll. E. Tripp', Chief, Engineering Support date signed
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Section No. 1, RC&ES Branch Inspection Summary:
Inspection on November 12-14, 1980 (Combined Report Nos. 50-354/80-18; 50-355/80-18)
Areas Inspected:
Routine, unannounced inspection of procedures for receiving, storage and maintenance of safety-related equipment, observation of equipment storage areas and review of QA records associated with safety-related equipment.
The inspection involved 24 inspector-hours onsite by one NRC regional based inspector.
Results:
No items of noncompliance or deviations were identified.
Region I Form 12 '
(Rev. April 77)
8102060 % Q,
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DETAILS 1.
Persons Contacted Public Service Electric and' Gas Company
- A. Barnabei, Site QA Engineer
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- J. B. Gatewood, QA Supervisor
- G. Moulton, Project QA Engineer
- C. Rogers, Mechanical Field Engineer
- Denotes those present at the exit interview.
2.
Plant Tour (Units 1 and 2)
A tour of the site was made to observe construction activities in progress and the status of the work including control and protection of equipment being stored in warehouse storage and of equipment stored in place.
The inspector examined the items for obvious defects or noncompliance with regulatory requirements and license conditions.
No items of noncompliance were identified.
3.
Safety-Related Components - Review of QA Implementing Procedures (Units 1 and 2)
The inspector reviewed procedures established to control receiving, storage and handling of pressure retaining components which will be part of the-reactor coolant pressure boundary.
The review was done to ascertain whether the procedures were consistent with the reautrements of NRC Regulatory Guide 1.38 and ANSI Standard N45.2.2-1972.
- The following Bechtel procedures were included in the inspector's review:
WP/P-1, Revision'4, " Construction Work Plan / Procedure Program"
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WP/P-2. Revision 4, " Project Implementation and Control of Construction
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Work Plan / Procedure Program"
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WP/P-3, Revision 1, "Housekeepir.g for Nuclear Power Plants"
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WP/P-11. " Records"
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WP/P-14, Revision 3, " Storage and Handling of Materials for Nuclear
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Facilities" WP/P-15, Revision 1, " Maintenance of Materials in Storage"
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WP/P-16, " Rigging"
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SWP/P-13, " Construction Equipment Inspection and Maintenance"
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SWP/P-14, " Material Receipt Storage and Handling"
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The inspector found that the control provided by the above procedures met the applicable storage and maintenance requirements.
As a result of extending the fuel loading date for both units, Bechtel did a study of extended equipment storage and maintenance to outline the effect on quality related (0-listed) equipment.
The inspector reviewed the document entitled " Units 1 and 2 Material Handling and Storage Study of Extended Storage and Maintenance," dated September 15, 1980, and the status of report dated November 5, 1980 of action items resulting from the study.
All equipment vendors have been notified of the new fuel load dates so they can establish storage requirements based on the extended storage interval, or extend the current requirements over a longer interval.
No items of noncompliance were identified.
Safety-Related Components - Review of QA Records (Unit-1)
The inspector reviewed storage maintenance records associated with the following components:
Main Steam Isolation Valve, S/N 01-685.
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Recirculation Pump Case, S/N 711-S-0765.
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Recirculation Pump Motor, S/N 8385420.
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The reviewed records indicated that inspections were made and documented at the established freauency in accordance with applicable procedures and vendor requirements.
No items of noncompliance were identified.
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5.
Licensee Internal Audits (Units 1 and 2)
The inspector reviewed the records of the two most recent licensee QA audits of Bechtel associated with safety-related components.
Records were reviewed for the following audits:
Audit number H-173
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Audit number H-194
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The above two audits covered activities associated with storage, handling, and housekeeping of safety-related equipment and components.
The licensee audit team selected various safety-related components and reviewed records to ascertain whether applicable requirements were met.
The inspector reviewed the aforementioned records with respect to applicable requirements, audit findings and close out of significant findings.
No items in noncompliance were identified.
6.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph.1) at the conclusion of the inspection on November 14, 1980.
The inspector summarized the scope and findings of the inspection.
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