IR 05000354/1980015
| ML19345B258 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/30/1980 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345B256 | List: |
| References | |
| 50-354-80-15, 50-355-80-15, NUDOCS 8011260428 | |
| Download: ML19345B258 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
50-354/80-15 Report No. 50-355/80-15
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50-354
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Docket-No. 50-355 CPPR-120 License No. CPPR-121 Priority Category A
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Licensee:
Public Service Electric and Gas Company 80 Park Place Newark New Jersey 07101.
Facility Name:
Hoce Creek Generating Station, Units 1 and 2
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Inspection at:
Hancocks Bridge, New Jersey
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Inspection conducted:
September 9,1980
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Inspectors:
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e/.2 9_ / f f"0 R. J. Pajlino, Reactor Inspector date signed
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date signed date signed Approved by:
L R.i-Y d Y
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S. D. Ebneter, Chief, Engineering Support date' signed Section 2. RC&ES Branch Insoection Summary:
Ccmbined Insoection Of Units 1 and 2 on September 9,1980 (Report No. 50-354/80-15 and 50-355/80-15)
Areas inspected: Routine, unannounced inspection by one regional based inspector of the licensee's QA program pertaining to procedures and the imolementation of these procedures; work activities pertaining to the installation _of safety related cable trays. The inspection involved 7 inspection hours on site by one regional based inspector.
Results: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
80112 00fM
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DETAILS 1.
Persons Contacted Public Service Electric and Gas
- R. Douces, QA Engineer
- A. Giardino, Project QA Engineer
- A. Smith, Project Construction Manager Bechtel Power Corporation
- M. Macendray, Assistant Project Field Engineer
- F. Morsy, Resident Engineer
- denotes personnel present at the exit interview.
2.
Plant Tour The inspector toured the Unit 1 facility in the company of a licensee representative to examine specific work areas for obvious defects or noncompliance with NRC requirements or licensee SAR commitments.
Par-ticular note was taken regarding the presence of quality control inspectors and indications of quality control activities through visual evidence such as inspection records, material identification, nonconformance and/or acceptance tag.
During this tour through Unit 1, the inspector observed cable trays stored in the south corridor of the reactor building.
There were no tags on the trays other than one manufacturer's identification tag.
Five of twelve trays examined contained one or more weld burn-through in the tray side-rail facing the passageway at the junction of the tray rung and the side rail.
The licensee wac unable to determine tray status and has agreed to investigate.
This item is unresolved pending NRC review of licensee determination and corrective action.
(50-354/80-15-01)
In addition, the inspector observed that all vertical trays were installed backwards.
However this item was identified by the licensee and is listed as item 6 in the June 30, 1980 electrical punch list no.
PQCIR 16-1-1-L-20 for outstanding items. The irispector hau no further questions on this item.
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3.
Electrical (Components / Systems) Implementing Procedure Review The inspector reviewed select portions of the cable tray installation procedure number E-1406, revision 24, to determine whether this docu-ment conforms to the QA program described in the facility SAR.
Section 3.3.1, sheet 20a, E-1406, revision 4, stated in part, that
connection of cable trays to supports shall be per tray manufacturer's detail.
Bolts shall be installed snug tight using full effort of a man with an ordinary wrench."
The inspector expressed his concern in that the above instructions do not provide adequate control for fastening safety-related cable trays to seismic category 1 supports to ensure conformance with seismic design requirements.
The inspector cited 10 CFR 50, Appendix B, Criterion V which states in part, that "... Instructions, procedures...shall include appropriate qualitative and qualitative acceptan:e criteria for determining that important activities have been satisfactorily accomplished."
The inspector requested that licensee provide acceptance criteria and methods of control for work activities using " snug tight, full effort of a man and an ordinary wrench."
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This item is unresolved pending NRC review of licensee evaluation and corrective action.
(50-354/80-15-04 4.
Electrical (Components / Systems) Work Observations The inspector examined work performance, partially completed work and completed work pertaining to safety related cable trays to determine whether the requirements of applicable specifications, work procedures, drawings and instructions have been met.
For this determination the inspector examined the following:
Cable tray installations in the Cable Spreading Room and Core
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Spray Pump Room 4104, 4108.
Cable Tray Load / Deflection Test Report No. PWE-1015.
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Orawing Nos. E-1531-1, revision 7, sheet 1 and 2, E-1631-1,
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revir, ion 6, sheet 1 and 2, E-1662-1, revision 8, sheet 1 and 2.
Static Test Results of Cable Trays Report No. PWE-1010.
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The inspector observed that trays numbered 12DTVB05 and 12BTEB43 at elevation 54-O', area 22 are not continuous tray sections.
These trays and other similar trays encircling the cortainment have been modified to incorporate a standard hardware hinge joining two tray sections on the inside side rail of cable tray and a flat stainless steel sheet fasten to the two outside rail sections to accommodate the containment radius.
The cable tray qualification test reports do no address the adequacy of the hinged cable tray configuration.
In addition, the inspector observed that the unsupported length of tray section, measuring from the hinge, varied from 6 inches to 7 feet.
The licensee's stated design requirement for hinged tray overhang is a maximum of 3 feet.
This item is unresolved pending NRC review of licensee justification and qualification of the hinged tray installation.
(50-354/80-15-031 5.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance. Unresolved item (s) identified during this inspection are discussed in Details, paragraphs 2, 3 ard 4.
6.
Exit Interview The inspector met with licensee and construction representatives (denoted in Details, paragraph 1) at the conclusion of the inspection on September 9, 1980.
The inspector summarized the purpose and scope of the inspection and identified the inspection findings.
The NRC Senior Resident Inspector, Mr. R. Bateman, was present at this meeting.
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