IR 05000311/1979022
| ML18079A523 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/04/1979 |
| From: | Caphton D, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A521 | List: |
| References | |
| 50-311-79-22, NUDOCS 7907110494 | |
| Download: ML18079A523 (6) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-311/?g-22 Docket No. _5_0 __..,,.3_1 _, __ _
License No * _....,c.... P...
PR""'-::.;,5i.w3...... *_
Priority ---=---
Category --"'Bu..1 ____ _
Licensee:
Public Service Electric and Gas Company 8Q Park Place Newark. New Jersey 07101 Facility Name:
Salem Nuclear Generatjng Station Unit 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted: M~,
1979 Inspectors: ~
JI... *
H. H. Nicholas, Reactor Inspector Approved by:
Inspection Summary:
Ins ection on Match*29 ~A til *g~ 1979.(Ra Ort No. 50-311/79-22)
date signed date signed S:?-79 date signed Areas In~petted: Routine; unannounce inspection y: a regiona based inspector of the overall preoperational test program including: test procedure review and verification; test results review and evaluation; vibration assessment program for reactor internals results review; and, plant tour of containment, diesel gene'rator rooms, battery rooms, relay room; and equipment stor)1ge, *protection and cleanline$s. The inspection involved 46.5 inspector-hours on site by one NRC regional based inspector..
Results:
No items of noncompliance were identifie Region I Form 12 (Rev. April 77)
.. DETAILS Persons*cantacted Public*service:Electric and.Gas Company Mr. S. Chawaga, Principal Staff Engineer - QA Mr. J. Ciccone, Construction Startup Engineer Mr. R. Griffit~i Site QA Engineer Mr. C. Johnson, Startup Engineer
- Mr. A. Meyer, Site QA Engineer
- Mr. E. Meyer, Site QA Head Westinghouse.Electric Corporation Mr. R. Powell, Site Manager Mr. N. Skorich, Mecharii~al Engineer USN RC Mr. L. Norrholm,- Resident Reactor Inspector The inspector also interviewed other licensee personnel during the course ~f the inspectio *Denotes presence at the exit intervie.
Preoperatianal *rest Program a. Preoperational Test Procedure Review and Verification The following procedure was reviewed for techni~al and*
administrative adequacy, and to verify that adequate testing is planned to satisfy regulatory guidance and licensee commit-ments:*
SUP 47 Revision O, Approved March 30, 197 Fresh Water Pretreatmen The procedure was reviewed for the following:
Management approval, Appropriate committee review, Test objectives, Prereq.ui sites, Environmental conditions,
*--
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Acceptance criteria, References, Initial conditions,
Test objectives are met, Performance verification, Recording conduct of test, Restoration of system to normal after test, Evaluation of' test data, and, Quality control verificatio Findings:
-- ---*-- --.-*--**---~-*- ------- ----*
The inspector ascertained by review of the above that the procedure was consistent with regulatory requirements, guidance and licensee commitment No discrepancies were noted in the review of this procedure and the inspector had no further questions at this tim Preoperational *rest.Results Evaluation The following procedures were reviewed to ascertain whether uniform criteriawer.ebeing applied for evaluating complete preoperational tests to assure technical and administrative adequacy:
SUP 19.~ Re~ision O, Approved March*22, 197 Contain-ment Iodine Remova SUP 17.5 Revision O, Approved March 26, 197 Fuel Transfer Syste SUP 51 Revision 0, Approved March 22, 197 Integrated test of Engineered Safeguards and Emergency Power Syste SUP 20.2 Revision O, Approved March 23, 197 Reactor Protection System Operational Tes SUP 9, Revision 0, Approved March 27, 197 Fire Prot-ection System Detection and Alarm Operational Syste SUP 49 Revision 0, Approved March 22, 197 Emergency Lightin SUP 50.13 Revision 0, Approved March 27, 1979. Initial Turbine Ro 1 *
SUP *10.1 Revision 0, Approved March 28, 1979. Contain-ment Spray Syste SUP 23 Revision 0, Approved March 29, 197 Communication Syste SUP 10.4 Revision 0, Approved April 1, 1979. Test of CVCS Makeup Blend SUP. 19.l Revision 0, Approved April 2, 1979. Auxiliary Building Ventilatio S~P 19.8, Revision 0, Approved April 1, 197 Fuel Handling Ventilation Syste SUP 25B Revision 0, Approved April 1, 197 Vital Heat Trac SUP 50.l Revision 0, Approved April l, 197 Reactor Coolant System Thermal Expansio SU~ 50.19 Revision 0, Approved April 1, 1979. Preservice Examination of Support SUP 19.7 Revision 0, Approved April 2, 1979. Chilled Water Syste SUP 24 Revision O, Approved April 3, 197 Nuclear Instrumentation Syste SUP 26 Revision 0, Approved April 3, 197 Computer Input and Data Printout Verificatio SUP 17,1 Revision 0, Approved April 2, 1979. Manipulator Crane Indexin SUP 19.6 Revision 0, Approved April 5, 1979. Control Area Air Conditioning Syste SUP 20.l Revision 0, Approved April 5, 197 Reactor Protection/Emergency Safeguards Time Response Measuremen SUP 20.5 Revision 0, Approved April 5, 197 Reactor Plant Systems Setpoint Verificatio '...
/
The inspector reviewed the test results and made verifications of the licensee evaluations of test results, by the following methods:
Review of:
test changes, test deficiencies test exceptions, test summary and evaluation, the 11as-run 11 copy of test procedures, QA inspection records, and, Verification that the test results were accepted and approved by the licensees review and approval proces Findings:
The inspector made note of each procedure, change, exception,
,
and deficiency, and cross-referenced these items to the licensees outstanding items lis No discrepancies were noted in the review of these procedures and the inspector had no further questions at this tim.
Vibration Assessrnent*Program*far Reactor Internals References:
Public Service Electric and Gas Company, Final Safety Analysis Repor Regulatory Guide 1.20, Revision 2, Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testin Regulatory Guide 1.68, Revision 2, Appendix A, Vibration Test Site Data Book - Reactor Internals Assembly Specifications 2463A63, Revision 4, October 13, 197 The licensee has classified his reactor vessel as a Non-Prototype Categor Category I A program of "full inspection 11 as described in the Final Safety Analysis Report and Regulatory Guide l.20, Comprehensive Vibration Assessment Program for Reactor Internvals During Preoperational and *Initial Startup Testing, has been implemented and completed by the license *
The inspector examined documentation concerning data, comments, and observations for before, and after, functional testing; and discussed vibration analysis results with Westinghouse personne Findings:
No discrepancies were noted in the evaluation of test results by the licensee. Based upon the inspector's review, test data was determined to be within previously established acceptance criteri No items of noncompliance were identifie.
Plant.Tour The inspectors toured diesel generator rooms 2A, 28 and 2C; battery rooms 2A and 28; relay room and containmen The inspector observed work in progress, housekeeping and cleanliness in the subject areas. Storage, protection and cleanliness of equipment and components were visually observed and verified to be within requirement No. items of noncompliance were identifie.
_ Exit Interview At the conclusion of the site inspection on April 9, 1978, an exit meeting was conducted with the licensees senior site representatives (denoted in Paragraph 1). The findings of this inspection were discussed during the exit meeting *