IR 05000311/1979017
| ML18079A341 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/21/1979 |
| From: | Bettenhausen L, Caphton D, Fasano A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A340 | List: |
| References | |
| 50-311-79-17, NUDOCS 7905300752 | |
| Download: ML18079A341 (5) | |
Text
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U.-S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No.* 50-311/7.9-17 Docket No. * 50-.311 *
License N CPPR-.53 Priority ------
Categor. Bl
Licensee:
Public Service Electric and Gas Company 80 Park.Plac Newark, New Jersey 07101 Fac.*ility Name:
Salem Nuclear Generating Station Unit 2 Inspection at:
Hancocks Bri.dge, New J~rsey
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Inspection conducted: March 6-8, 1979 c;;Z~~~
'date signed Inspectors:
- o L. H. Bettenhausen, Reactor Approved by:
date Inspectjon Summary:
Ins ection on March 6-8, 1979 Re art No. 50-.311 79-17 reas Inspected:
Routine, unannounced inspection by regional based inspectors of the startup test program including: test procedure review and verification;
.plans for plant operational tests; *and.plant tour of the control room, auxiliary building, and containmen The inspection involved 70 inspector-hours orisite by three NRC regional based inspector *
Results: No items of noncompliance or deviations were identifie Region I Form 12 (Rev. Aprfl 77)
7905300?S2-*
DETAILS
.. Persons Contacted Public Service.Electric and Gas Company Mr".
R~ Evans,. Assistant Manager - QA M R~ Griffith, Jr., Senior Staff Engineer - QA Mr. *J~ Jackson, Engineer - Reactor Staff*
M C~ Johnson, Startup Engineer Mr. D. McLaughlin, Senior Construction Engineer
- Mr. M. Metcalf, Engineer - Station QA
. *Mr. A. Meyer, Site QA* Engineer Mr. E. Meyer, Site QA Head * *
. *Mr. H. Midura, Manager.;. Sa 1 em Generating Station
. *Mr. J. Ni cha 1 s, Reactor Engineer*
Mr. L Pearce, Startup Test Engineer M E~ RosQioli, Senior Reactor Staff Supervisor Mr. W *.. Schell, Engineer - *Reactor Staff
. *Mr. J *. Stillman, Station QA Engineer
. *Mr. J. Zupko, Jr*., Chief Engineer**
USN RC
- Mr. L. Norrholm, Resident Reactor Inspector Th~ inspector also interviewed licensed operations personnel and members of the licensee's technical staff.*
. * denotes those present at the exi~ intervie.
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. Startup Test Program Procedure Reviews The inspector reviewed draft test procedures and discussed procedure content with licensee personnel to assure that the following criteria were met: FSAR Section 13, Draft Technical Specifications, Regulatory Guide 1.68 and Salem Startup Manual*to verify that testing commitments have been included in the procedure * Procedure format is consistent with ANSI 18.7 and Regulatory Guide 1.68 *
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3 Test objectives are clearly state Pertinent prerequisites are identifie Special environmental conditions, if any, are identifie f~
Acceptance criteria against which the test will be judged are*clearly identified and the procedure requires comparison
.of~results with acceptance criteria~ Initial test.conditions are specifie The procedure includes a section listing references to appropriate FSAR sections, and other requirements.* Step by step instructions for the performance of the procedure are complete*to the extent necessary to assure that test objec-tives are * me *
- Spaces are provided for initialing that.all items, including prerequisites,. are verified as havi_ng been performe *
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. The procedure requires that temporary connections, disconnec-tions or* jumpers be restored to normal or reference their control by another procedur The procedure provides identification of personnel conducting the testfog and evaluating test data. *
The. procedures which were reviewed and discussed are delineated in paragraphs belo a. _ SUP 60. Initial Core Loading Discussions included location, function and manning of core loading stations; calibration and operation of temporary and
.plant nuclear instrumentation;.steps*taken to meet status of containment building penetrations*during*fuel handling; boration *system controls~ operations a*nd concentration measure-ment frequency; core loading*sequence and recording of status; and conduct of core* loadi_n The boron concentration control method detailed in Appendix B, Section 1, of the procedure is not referenced or used in execution of the procedure~ This is*considered an*open item (311/79-17~01)
for followup during a subsequent inspection~
- Precritical Test Procedures SUP 70.l Reactor Coolant System Leakage Test SUP 70.2 RTD Bypass Flow Verification SUP 70.3 Reactor Coolant Flow Coastdown Measurements SUP.70.4 Pressurizer Spray and Heater Capability and Continuous Spray Setting
- SUP 70. 5 Reactor Coo 1 ant System. Fl ow Measurement SUP 70.6 Rod Position Indication System SUP 70.7 Rod Drive Mechanism Timing SUP 70.8 Rod Drop Time Measurements SUP 70.9 Full Length Rod Control System - Operational Test SUP 70.11 Incore Flux Mapping System The procedures and the methods by which they will be implemented were discussed with licensee representative Two items of discussion apply to several*ofthe procedures listed abov They are considered open i terns for foll owup in subsequent inspec-tians.. One item is the use* of Unit 1 nomenclature in the-test procedures for Unit 2; several examples were discussed with licensee representatives.(311/79-17-02).
The second item is an apparent inconsistency*in provisions for removal of test equipment or restoration of systems to normal operatio Some procedures have specific provisions for restoration while others do not.*
Licensee representatives stated that restoration is accomplished by application of station Operating Instructions or that the final test condition is the initial condition for the next test in the startup sequence. This is an open item (311179-17-03) pending further review and discussion. Except for the specific comments above*the*inspector had no further questions in this are * No items of noncompliance or deviations were identified *
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3.. Startup Test Program 4 *.
The* licensee's Phase III-Plant*operational Test Program covers the
. init.ial nuclear operation of the.plant from initia*l core loading through the: pl ant acceptance test. The administration' of the Phase III Test. Program, the procedural controls developed by the licensee, staffing and organization and interfaces among plant staff, reactor operators, test engineers and vendor personn.el as described in the Salem Startup Manual were reviewed and discussed with licensee representative In discussing the status of startup procedures, representatives stated that e*ssentially.all of the procedures had been reviewed as stated in the Startup Manual and the FSAR and were in-the process of being signed; verification of this approval will be done in a subsequ~nt inspection. While examining the cover sheet
. form signifying approval, the inspector noted that the sheet required release for* test by the Reactor Engineer, whereas the FSAR stated that this release would be given by the PSE&G Startup Group Startup Enginee This is an open item to be resolved in a subsequent fnspection (311/79-17-04).
Except* for the specific comments above, the inspector had no further questions in this*area *.
No items of noncompliance or deviations
wera identified~
Plant. Tour The inspectors toured the control room, auxiliary building, and containment *. ~he.inspectors observed preparations bein~ made for fuel loadin *
No items of noncompliance or deviations were identifie.. s*.
Exit Interview
At the conclusion of the site inspection on March 8; 1979, an exit meeting was conducted with the licensee's senior site representatives (denoted.in paragraph l)~ The findings of this inspection were discussed duririg the exit meeting. *