IR 05000311/1979011
| ML18078B171 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/22/1979 |
| From: | Bettenhausen L, Cophton D, Mcnott T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18078B170 | List: |
| References | |
| 50-311-79-11, NUDOCS 7904100510 | |
| Download: ML18078B171 (6) | |
Text
Report No. 50-311/79-11 Docket No.. 50-311 U.S. NUCLEAR REGULATORY COMMISSIOK OFFICE OF INSPECTION AND ENFORCEMENT Region I
License No. CPPR-53 Priority ------
Category ___
B_l __ _
Licensee:
Public Service Electric and Gas Company 80Park Place Newark, New Jersey 07101 Facility Name:. Salem Nuc.lear Generating Station, Unit 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted:
February 8 and 9, 1979 Inspectors: ~-~~
L. H. Bettenhausen, R~r Inspector
- I.. _, §'.. 'yvt c, YL ~
T~ G. McNatt, Reactor Inspector Approved by:
I, ~
D. L. C ~ on, Chief, Nuclear Support Section No. l, :RO&NS Branch Inspection Summary:
Inspection on February 8 and 9, 1979 (Report No. 50-311/79-11)
.Z,h._2/79
- date signed date signed
. *.date* signed
- 1~0Jea Areas Inspected:
Routine, unannounced inspection by regional based inspectors of preoperational test program including: test procedure review and verification; test results evaluation; plans for plant operational tests; and plant tour of turbine building, auxiliary buildiiing, containment, and the control roo The inspection involved 29 inspector-hours on site by two NRC regional based inspector *
Results:
No items of noncompliance or deviations.were identified..
Region I Form 12 (Rev. April 77)
7904100510
- -
DETAILS Persons Contacted Public Service Electric and Gas Company
- Mr. S. Chawaga, Principal Staff Engineer - QA Mr. J. Cicconi, Senior Construction Engineer Mr. J. Cox, Senior Construction Engineer
- Mr. R. Griffith, Jr., Senior Staff Engineer - QA
- Mr. C. Johnson, Startup Engineer *
Mr. H. Lowe, Site QA Engineer
Mr. E. Roscioli, Senior Reactor Staff Supervisor The inspector also interviewed other* licensee personnel during this inspection, including control: room operators, clerical, technical and instrumentation staff personnel.
- denotes those presenttat the exit intervie.
Startup Test Program The startup test program and the status of preparation of procedures for Phase III - Plant Operational Tests of Salem Unit 2 was dis-cussed with licensee representatives from the Electric Production Department, the PSE&G Startup Group and the Quality Assurance staff. The inspector acknowledged that preliminary or sample copies of 32 of the 43 startup procedures employed in SUP 80.1, NSSS Startup Sequence (sample copy) had been made available through the Resident Reactor Inspector for NRC revie The transition from preoperational to plant operational testing and the corresponding transition of the NRC inspection program was discusse Draft copies of the following procedures were received:
SUP 70.l, RCS Leakage Test SUP 70.2, RTD By-pass Loop Flow Verification
..
SUP 70.3t R~actor Coolant Flow Coastdown SUP 70.4t Pr:essurizer Spray and Heater Capability; Continuous Spray Flow Setting SUP 70'.5, RCS FlOw Measurement SUP 70.6, Rod Position Indication Systems *
SUP 70.7, Rod Drive Mechanism Timing SUP 70.8t Rod Drop Time Measur:ement
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SUP 70. 9, Rod Contra 1 Sys tern Operation SUP 70.11, Iri-Core Flux Mapping System SUP 80.1, NSSS Startup Sequence SUP 80.2, Initial Criticality SUP 80.3, Nuclear Design Check Tests SUP 80. 4,. Rod arid Boroh*.;Worth Measurements SUP 80.5, RCCA Pseudo Ejection at Zero Power SUP 80.6, Minimum Shutdown Verification and Stuck Rod Wort SUP 80.7, Startup Adjustments of Reactor Control System SUP 81.4, Automatic Steam Generator Level Control SUP 81.5, Dynamic Automatic Steam Dump Control SUP 81.6, Automatic Reactor Control SUP 81.7t Calibration of Steam and Feedwater Flow Instrumentation SUP 81.8t Power Coefficient and Integral Power Defect Measurement
..
- SUP.81 ~g;:.RCCA Pseudo Ejection and RCCA Above Bank Position SUP 81.10, Static RCCA Drop and RCCA Below Bank Position SUP 82.1, Load Swing Tests SUP 82.2, Large Load.Reduction Tests SUP 82.4, Rods Drop and Plant Trip SUP 82.5, Shutdown from Outside Control Room SUP 82.6, Loss of Off-Site Power SUP 82.7, Steam Generator Moisture Carryover SUP 82.8, NSSS Acceptance Test SUP 82.9, Generator Trip from 100% Power A detailed review of approved procedures will be made in subse-quent inspections. The inspector had no further questions at
. this tim *
Preoperational Test Program a*.
Test Procedure Review and Verification The following procedures were reviewed for technical and administrative adequacy and to verff.Ythat adequate testing is planned to satisfy regulatory guidance and licensee com-mitments:
SUP 9, Revision 0, Approved-January 25, 197 Fire Protection System Detection and Alarm Operational
, System SUP 20.3, Revision 0, Approved January 26, 1979. Safe-.
guards System Operational Test SUP 24, Re vi's ion O, Approved January 29, 197 Nuclear Instrumentation Syste *
The inspector ascerta.ined by review of the above procedures that they are consistent with regulatory requirements, guidance and licensee commitment No discrepancies were noted in the review of these procedure Test Results Evaluation
,The following_ procedures were reviewed to ascertain whether 1 uniform criteria are being applied for evaluating completed
preo-peratfonal tests to assure their technical and administrative adequacy:
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SUP 19. 3, Revis ion l, Approved January 29, 197 Rod Drive Ventilation System SUP 31.lA, Revision 0, Approved January 9, 197 A Diesel Controls - Alarms and Auxiliaries SUP-:31:1B, Revision O, Approved January 9, 197 B Diesel Controls - Alarms and Auxiliaries The inspector reviewed the test results and verification of licensee evaluation of test results by the following methods:*
Review of all test changes; Review of all test deficiencies; Review of test su1TV11ary and evaluation; Review of /\\as-run" copy of test procedure; Review of QA inspection records; and, Verifying that the test results have been approve No discrepancies were noted in the review of these procedures and the inspector had no further questions at this time;.
- .Plant Tour The inspectors toured the turbine building,_ auxiliary building, containment, and the control room.. The inspectors observed po~
tions of the reactor vessel. inspection with the head, upper, and lower internals remove No items of noncompliance were identifie.
Exit Interview At the conclusion of the site.inspectfon. on February 9, 1979, an exit meeting was conducted with the licensee's senior site repre-sentatives {denoted in paragraph 1).. The findings of this inspec-ti on.:were discussed during the exit meeting.