IR 05000272/1979030
| ML18081A985 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/10/1979 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18081A984 | List: |
| References | |
| 50-272-79-30, NUDOCS 8001310122 | |
| Download: ML18081A985 (4) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION I*
Report N /79-30 Docket N ~272 License N DPR-70 Priority -----
Category ___ c--
Licensee:
Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station - Unit 2 Inspection At:
Hancocks Bridge, New Jersey*
1979 to November 2, 1979 Inspectors:*
r Inspector 1, RC&ES Branch Inspection Summary:
Cf ate date date lt/Jobf date Inspection on October 31, 1979 and November 1-2, 1979 Report No. 50-272/79-30)
Areas Inspected:
Routine, unannounced inspection of inservice inspection data package and licensee action on previous inspection finding The inspection involved 24 inspector-hours on site by one NRC regional based inspecto Results:
No items of noncompliance or deviations were identified.
Region I Form 167 (August 1979)
- ._.*
DETAILS Persons Contacted
- Public Service Electric and Gas Company
- S. La Bruna, Maintenance Engineer L. Lake, ISI Coordinator
- B. W. Leap, Station QA Supervisor
- H. S. Lowe, QA Engineer
- D. W. Lyons, Engineer
- H. J. Midura, Station Manager
- J. L. Stillman, Station QA Engineer
- Denotes those present at the exit intervie.
Inservice Inspection (ISI) Data Review and Evaluation The inspector selected for review records associated with the following components/welds:
No. 11 reactor coolant pump (RCP) flywheel No. 14 RCP support no. 14-PMP-3LG No. 14-RH.;..27 safety injection system valve body Closure head to flange weld no. 1-RPV-6046A (161 11 length examined)
8 inch safety injection system tee to cap weld no. 8-SJ-1162-17 6 inch safety injection system reducer to elbow weld no. 6-SJ-1142-1 10 inch branch connection reactor coolant system weld no. 27.5-RC-1140-1/
10-SJ-1141 14 inch steam generator feed system elbow to pipe weld no. 14-BF-2111-3 14 inch steam generator feed system pipe to elbow weld no. 14-BF-2111-4 14 inch residual heat removal (RHR) system elbow to flange weld n RH"".2114-15 8 inch RHR system elbow to pipe weld no. 8-RH-2126-26
The inspector's review included, but was not limited to, the following parameters:
Examination data sheets, equipment records and indication evaluation sheets are referenced Records on program and procedure deviations are provided or referenced Re-examination data after repair work are referenced (if applicable)
Records on extent of examination are provided The method, extent and technique of examination comply with licensee's ISI program and applicable NOE procedure The examination data are within the acceptance criteria as outlined in applicable NOE procedure and applicable code requirements The recording evaluation and disposition of findings are in compliance with the applicable NOE procedure and applicable code requirements The examination equipment calibration data sheets show no major deviations between initial and final calibrations Evaluation of examination data performed by a Level II or Level III examiner Collected examination data and any recordable indications are properly recorded to permit accurate e.va l uat ion and documentation No items of noncompliance were identifi'e.
Licensee Action on Previous Inspection Findings (Open) Unresolved item (272/79-14-01):
Frequency selector switch function on Sonic MK I instrument The Southwest Research Institute (SwRI) letter dated October 12, 1979, W. T. Flach to H. J. Midura, discusses various aspects of item 79-14-0 The inspector requested clarification of the following points discussed in the letter:
Requirement of SwRI Procedu.re NDT 600-36, Revision 0 for setting fre-quency selector switch of Sonic MK I ultrasonic instrument:
The requirement quoted by W. Flach, SwRI is not found in the !SI data package copy of 600-36, Rev. 0 supplied by SwRI to license Effectiveness of the ultrasonic examination of RHR heat exchanger studs *number 1, 18, 19 and 36:
The inspector stated that examination effectiveness should be demonstrated on studs containing natural defects using examination equipment referenced in the SwRI lette *
4 *
The licensee stated that Southwest Research Institute will be requested to provide the. necessary dat This item remains open pending licensee receipt of the required information and subsequent NRC review..
(Open) Unresolved item. (272/79-14-02): Accuracy of data on ISI data sheets:
Licensee review of the data package has not been complete This item.remains open pending completion of the licensee review and sub-sequent NRC inspectio (Closed) Unresolved item (272/79-14-03):
Disposition of penetrant indica-tions. The inspector reviewed reports and records associated with weld 8-SJ-1162...,17, weld 8-SJ-1152-16-PS and weld 12-RHR-HEX-2V~.
The inspector found that the penetrant indications detected on the welds were removed, re-examination of each.weld was completed and the results were evaluated and properly dispositione The inspector stated that he had no further questions concerning this matte Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on November 2, 197 The inspector summarized the purpose and scope of the inspection and the finding In addition to those denoted in Paragraph l, the NRC resident inspector, Mr~ L. J. Norrholm, attended the exit meeting *.