IR 05000311/1981030
| ML18086B259 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/06/1982 |
| From: | Bettenhausen L, Eapen P, Ebneter S, Meyer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18086B258 | List: |
| References | |
| 50-311-81-30, NUDOCS 8201230069 | |
| Download: ML18086B259 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSEPCTION AND ENFORCEMENT Report No. 50-311/81-30 Docket No. 50-311
Region I License No. DPR 75 Priority Category c
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Licensee: Public Service Electric and Gas Company 80 Park Plaza - 15A Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station - Unit 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted:
November 23 - 25, 1981
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Inspectors:
L. H. Bettenhausen, P date signed I /q fs1'
date signed
~{ da'tesigned Approved by:
<;1 J. ~
S. D. Ebneter, Chief dcite 1signed Engineering Inspection Branch, DETI Inspection Summary:
Inspection during November 23 - 25, 1981 (Report 50-311/81-30)
Areas of Inspection:
Routine unannounced inspections of startup test program, test data, review of test results and conclusions by region based inspector The inspection involved 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> onsite by two region based inspectors and a superviso Results:
No items of non-compliance were identifie r------------
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Details Persons Contacted
- Public Service Electric and Gas Company
USN RC
A. C. Darelius, Quality Assurance J. Driscoll, Chief Engineer J. Jackson, Senior Reactor Staff Supervisor J. O'Connor, Radiation Protection Senior Supervisor J. L. Stillman, Quality Assurance W. Hill, Resident Inspector M. McBride, Radiation Specialist K. Plumlee, Radiation Specialist The inspectors also talked with other licensee personnel during the course of the inspection, including operations, performance, maintenance and quality assurance personne Present at the exit meeting, conducted jointly for inspections 50-311/
81-30 and 50-272/81-30.
Actions on Previous Inspection Items (Closed) Unresolved Item (311/81-22-01), RTD Response Time The inspector reviewed the detailed analysis of the transient response for the hot leg RTD during the Generator Trip Test conducted on September 2, 198 The analysis showed that RTD response time met acceptance criteri The operation of the main steam relief valve was adequately explaine There were no further questions on this ite.
Unit 2 Startup Test Data Review The inspector reviewed completed test data for the following:
identification of deficiencies or exceptions to test and their resolutions, proper administrative review of test changes, annotation of change in test procedure and verification that the changes did not alter test objectives, verification that test data and procedure steps were properly recorded, initialed and dated,
Engineering Analysis and Evaluations of test results, including comparison of results with acceptance criteria, Review and acceptance of test results in accordance with the startup manua Test Program Review SUP 80.1, NSSS Startup Sequence, is the governing procedure for sequencing the required tests from initial core load to licensed full power operatio The completed test document, including procedures used, changes incorporated and exceptions taken, was reviewed and accepted by the Startup Group on November 4, 1981 and SORC on November 10, 198 The test program followed the sequence prescribed in SUP 80.1 with the following exceptions: changes were made to the Procedur.
12 exceptions and test deficiencies were identified during the course of testin These exceptions and changes were reviewed and approved.
Listed below are some of the significant changes and exceptions to SUP 80.1:
Step 10. The feed and condensate system performance test required by this step was not conducted to avoid an inadvertent trip of feed/condensate pump Problems with suction pressure and trips of feed and condensate pumps are under active investigation by the eng.ineering staf However, sufficient data was taken to establish the performance at the operating points specifie Appendix E Snubber Data Collection required by Appendix E within the bioshield was deferred until the post startup outag Step 10.5.12 This step was changed to compare the actual 100% values of Tave and Tref, instead of the extrapolated values at 100%, to the design value Tref was re-programmed using actual operating data at and below 100% of the Rated Thermal Power (RTP).
Initial power coefficient measurements at 93% and 95% Rated Thermal Power did not meet the acceptance criteria for this tes Subsequent tests performed on 10/14/81 met the acceptance criteri The initial moisture carryover test per SUP 82.7 failed to meet the acceptance criteria. A subsequent test on 10/12/81 met the acceptance criteri SUP 82.8, NSSS Acceptance, was accepted by station management with a 68 hour7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> continuous run above 95% RTP versus the acceptance criterion of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> above 95%.
The unit had accumulated 243 hours0.00281 days <br />0.0675 hours <br />4.017857e-4 weeks <br />9.24615e-5 months <br /> of operation above 95% at the time this acceptance was mad Power Plateau Tests SUP 80.7, Startup Adjustment of the Reactor Control System, was reviewed and approved by the SORC on November 10, 198 The tests did not require any changes, exceptions or deviation SUP 81.7, Calibration of Steam and Feedwater Flow Instrumentation at Power, was completed on October 19, 198 No changes were required to perform this procedur The SORC reviewed and accepted this test report on November 10, 198 The inspector reviewed the procedures and the calibration data and concluded that the calibration was conducted in accordance with adequate test and calibration procedure SUP 81.11, Incore-Excore Calibration, was completed on August 5, 198 The Startup Group and the SORC reviewed and accepted the results and conclusion of SUP 81.11 on September 23, 1981 and November 10, respectivel One change to the procedure and one exception to a procedure step during this calibration were duly implemented and approve The inspecto found this test report adequate, except that plots of incore vs. excore axial offset were not made for a number of case This was discussed with the licensee representatives, The licensee attributed this to the recent change of calculations from manual to compute The computer calculation provides the mathematical form for the plot, but not the plot itsel The licensee advised the inspector that the necessary corrective actions, including a revision to Part 7 of the Reactor Engineers Manual and expansion of the computer calculations to generate the plots, will be instituted prior to the submittal of the Startup Repor SUP 81.12, State Point Data, was completed October 16, 1981, reviewed by the Startup Group and reviewed and approved by SORC on November 10, 198 No changes to the procedure were
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made, nor were any exceptions or deficiencies identifie The procedure is a compilation of plant data obtained at equilibrium conditions at each power platea The inspector had no further question Transient Tests SUP 81.8, Power Coefficient and Integral Power Defect Measurements, was completed on October 15, 198 Subsequent to the review by the Startup Group, the SORC reviewed and accepted these measurements on November 10, 198 No changes were required to the procedur Two exceptions were taken to the procedural steps to accommodate operational characteristics of the core at the beginning of lif These measurements were generally acceptable, except that a transcriptional error was noted in the calculations required to demonstrate compliance with acceptance criteri The inspector discussed this matter with the licensee representatives, and the licensee agreed to complete a review of the calculations and comparison of results to acceptance criteria prior to the issuance of the Startup Repor SUP 82.9, Generator Trip from 100% Power, was performed on September 2, 198 The results were reviewed by the Startup
- Group on September 23, 1981; SORC reviewed and approved these on November 10, 198 Two changes were made to SUP 8 An exception was taken to the test conditions to accommodate the test requirements for SUP 90.9 which immediately followed this tes The inspector found the Generator Trip Test acceptable after reviewing original test data and chart A lack of explanatory notes showing how all acceptance criteria were met was discussed with licensee staf The licensee agreed to review the test information in the course of preparing the Startup Test Report and add these explanatory notes to the test packag SUP 82.2, Large Load Reduction Tests, was performed on September Ii, 198 The Startup Group reviewed and approved this report on September 24, 198 SORC reviewed and accepted the report on November 10, 198 The management approved one change to SUP 8 This test required no exception from the SUP 82.2 procedural step The inspector found the test report to be adequate, except for the lack of explanatory notes to clearly demonstrate acceptance of the test result The inspectors discussed this matter with the licensee staf The licensee agreed to review the report and incorporate explanatory notes where clarification is required.
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SUP 90.9, Boron Mixing and Cooldown Tests, was conducted on September 2, 198 The Startup Group reviewed the test report on September 22, 198 The SORC reviewed and approved the report on November 10, 198 The management reviewed and approved one change to SUP 9 During the test, 130 ppm boron was added to the reactor coolan The system took five hours to reach boron equilibrium concentration after the additio The test also demonstrated a reactor coolant system cooldown of 65°F over a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following attainment of boron equilibrium concentratio The inspector reviewed the procedures, results and conclusions and had no further questions on this matte.
Exit Interview An exit interview was held with licensee representatives (participants identified in paragraph 1) on November 25, 198 The purpose, scope and findings of this inspection were presented.