IR 05000272/1979004
| ML18078B013 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 01/17/1979 |
| From: | Durr J, Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18078B012 | List: |
| References | |
| 50-272-79-04, 50-272-79-4, 50-311-79-02, 50-311-79-2, NUDOCS 7903140624 | |
| Download: ML18078B013 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-272/79-04 50-311/79-02 50-272 Region I Report N Docket N License N Licensee:
---a-p~R---70---
CPPR-53
Priority ------
Public Service Electric and Gas Company 80 Park Place*
Newark, New Jersey 07101 Category __
B ____,__
Facility Name:
Inspection at:
Salem Nuclear Generating Station, Unit 1 and 2 Hancocks Bridge, New Jersey
- Inspection conducied:
January 4-5, 1979 Approved by:
Inspector 1%1. -L a:a.?µz./
tfe-t:;,, f S. D. Ebneter, Acting Chief,~Engineering Support Section N~. 1, RC&ES ~ranch *
Inspection Summary:
date signed date signed 1- /-/ -7t date signed Unit No. 1 Ins ection on Januar 4-5, 1979 (Re ort No. 50-272/79-04 Areas Inspecte : A routine, announce inspection was performed by a regional based inspector of the licensees corrective actions concerning the pcist weld heat treatment practices during the construction phas The inspection involved 8 inspector-hours onsite by one *NRC inspecto *
.
Results:
No items of noncompliance were identified in the one area inspected.*
Unit No. 2 Ins ection on Januar.4-5, 1979 (Re art No. 50-311 79-02 reas Inspecte :
routine, announce inspection was performed by a regional based inspector of the licensee's corrective actions concerning the post weld heat treatment item of noncompliance (311/77-26-07).
The inspection involved 7 inspector-hours onsite
~~~:_NRC inspecto ~:
No items of noncompliance were identified in the one area inspecte Region I Form 12 (Rev. April 77)
79031.4. D' i_ 1
.
,.
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DETAILS Persons Contacted Public Service Electric and Gas Company R~ Dierkes, Lead Engineer
..
- S. Chawaga, Project Q. C. *Engineer
- R. J. Griffith, Senior Staff Engineer-Q. R. Kirk, Senior Engineer K. Kraska, Engineer
- D. L. Mclaughlin, Senior Construction Engineer
- E. Mey~r, Project Q. A. Engineer M. Nanjappa, Lead Engineer
- J. E. Rogozenski, Principle Engineer
- M. Rosenzweig, Q. A. Coordinator United Engineers and Constructors, In J. Lark, Q. C. Engineer
- R. J. Phelps, S~perintendent, F. Q. * D. C. Snyder, Project Engineer
- denotes those present at the exit intervie.
Licensees Actions on Previous Inspection Findings (Open)
Noncompliance (311/77-26-07)
(Open)
Unresolved Items (311/77-26-08, 09 and 10)
(Open)
Unresolved Item (272/78-31-01)
(References: 311/77-27, 78-31 and 78-51; 272/78-31)
Exceeding the heating/cooling rates and maximum temperature for local post weld heat treated (PWHT) pipe weld The licensee completed his review of the Salem Unit No. l PWHT charts for safety related piping to identify any welds which did not meet the USAS 831.7 Nuclear Power Piping Code during the construction phase. *
Those welds that do not meet the code requirements will receive further evaluation regarding their acceptability for service con-current with the Unit No. 2 stud L
The NRC inspector reviewed 20 of the 98 Unit No. 1 PWHT Charts identified by the licensee as safety relate The review was made to verify that the PWHT received by the test pipe exceeded the 11worst case 11 encountered in field practic The review included the 8 charts identified by the licensee as un-acceptable, 6 charts jdentified a~ questionable, and 6 charts reported as-acceptabl The following PWHT charts were examined:
1MS-6A-198 lMS-7-63 lMS-14-74 lMS-27-1-213 lMS-27-30 lMS-13-1-205 lMS-13-1-206 lMS-13-1-207 l MS-13-1-208 1 MS-14-15 lMS-14-16 lMS-2-2 1 MS-21-24A lMS-17-19 lMS-7-8 lSGF-30-168 lSGF-PEN-5-588 lSGF-PEN-5-568 lSGF-13-58 lAGF-45-248 The review did not disclose any conditions which exceeded the test pipe PWHT envelop The licensee presented portions of the information requested by the NRC in the December 19, J 978 meet i_ng?" Specif i ca 11 y, he presented the hardness test values.for the field welds, the basis for compar-ison of the hardness values, and the number and identity of the weld joints with questionable PWH The inspector had no further questions'concerning this information at this tim The licensee stated that the following additional information would be made available on or about February 5, 1979, except as noted:
Summary statement of the report fi ndi_ng Hardness tests of selected "worst case 11 PWHT's of Salem Unit No. l safety related pipe weld This will be performed during the first scheduled outag Further analysis to confirm that if the reduced tensile values, observed in the test pipe, are employed in the stress analysis, the stress value limits described in the FSAR are not exceede See IE Inspection Report Nos. 50-272/78-51 and 50-311/78-5 *
The test pipe material certifications or chemical analysi A copy of the stress analysis performed to verify the affected welds comply with the FSA The basis used to define the limits of the post weld heat treat-ment test conditions and the analysis of the test. result These items remain open pending completion of the l i censee*s actions and review by the NR.
Exit Interview At the conclusion of the inspection, on January 5, 1979, the inspector met with representatives of the licensee (denoted in Paragraph l) to discuss the scope of the inspection and the inspector's finding The licensee acknowledged the inspector's findings and statements as presented in the body of this report.