IR 05000354/1979010
| ML19322E469 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/01/1980 |
| From: | Bateman W, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19322E466 | List: |
| References | |
| 50-354-79-10, 50-355-79-09, 50-355-79-9, NUDOCS 8003280155 | |
| Download: ML19322E469 (2) | |
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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l
Region I 50-354/79-10 Report No. 50-355/79-09 50-354 Docket No. 50-355 CPPR-120 License No. CPPR-121 Priority Category A
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Licensee:
Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Hope Creek Generating Station, Units 1 and 2 Inspection at:
Hancocks Bridge, New Jersey
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Inspection conducte : December 19, 1979 f,/j [$C)
Inspectors:
S W. H. Bateman, Reactor Inspector
'da'te signed date signed date signed Approved by: kMsN
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R' W. McGaughy, GMef/, Projects Section, tfate signed
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RC&ES Branch Inspection Summary:
Inspection on December 19, 1979 (Combincd Report Nos. 50-354/79-10 and 50-355/79-09)
Areas Inspected: Announced inspection by regional and headquarters based personnel to discuss the Resident Inspector's site facilities. Additionally,
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the inspectors observed the condition of the Unit 2 reactor vessel in response to a potential 10 CFR 50.55(e) item regarding a suspected surface defect.
The inspection involved 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> onsite by four NRC personnel.
Resul ts: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
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8003280 tG5
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DETAILS 1.
Persons Contacted Public Service Electric and Gas Company A. E. Giardino, Project QA Engineer G. Owen, Administration Bechtel Power Corporation (Bechtel)
W. Cole, QA Engineer W. Langdon, Mechanical Field Engineer 2.
Inspection of Onsite Facilities for Resident Inspector NRC personnel discussed with licensee representatives the requirements for the Resident Inspector's facilities. The licensee showed the NRC personnel the facility they were in the process of preparing to meet these requirements. The facility was determined to meet or exceed specified requirements. Additiu'111y, short and long term communica-tions requirements were discussed.
In particular three outside lines, as well as an internal circuit tied into the site switchboard to facilitate making ensite calls, was stated as being an immediate need.
The licensee stated that arrangements would be made to meet the communications requirements.
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Observation of Unit 2 Reactor Vessel Surface Defect Previous to this inspection, the licensee had reported a potential 10 CFR 50.55(e) item involving a suspected surface defect on the Unit 2 reactor vessel. The inspectors observed the area of the suspected defect and agreed with the licensee that further investigation would be required before disposition of the concern.
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