IR 05000311/1981022

IE Insp Rept 50-311/81-22 on 810730-0902.No Noncompliance Noted.Major Areas Inspected:Startup Test Program,Review of Test Results & Evaluations & Witnessing of Startup Tests

ML18086B028
Person / Time
Site:	Salem
Issue date:	09/29/1981
From:	Bettenhausen L, Caphton D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18086B027	List: IR 05000311/1981022 ML18086B026
References
50-311-81-22, NUDOCS 8111130614
Download: ML18086B028 (6)

Text

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Report N U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-31-1 /81-22 Docket N DPR-75 Priority ------

Category __ c _____ _

Lic2nse No. ------

Licensee:

Public Service Electric and Gas Company 80 Park Plaza - 15A Newark, New Jersey 07101 Facility Name:

Salem Nuclear Generating Station - Unit 2 Hancocks Bridge, New Jersey I n spec t ion at :

Inspection conducted:

July 30 - September 2, 1981 Inspectors:

L. H. Bettenhausen, Ph.D., Reactor Inspector Approved by: 5 ~ ~

f D. L. Caphton, Chief, Management Programs CG/\\ Section, Division of Engineering and Technical Inspection Inspection Summary:

date signed date signed date signed 1/z;j(!{i gned Inspection*during*Ju1y*30*~ septembet 2, 1981 (Repott 50~311/81~22)

Areas of Inspection:

Routine, unannounced inspections of startup test program, test data, review of test results and evaluations and witnessing of startup tests, by a region-based NRC inspecto The inspection involved 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> onsite by a region-based inspecto Results:

No items of noncompliance were identified.

Region I Form 12 (Rev. April 77)

DETAI.LS Persons Contacted Public Service El~ctric and G~s Company

• J. Destefano, QuaJ i ty Assurance

• J. Driscoll, Chief Engineer

• J. Jackson, Senior Reactor Staff Supervfsor

• W. Schell, Nuclear Engineer F. Schnarr, Reactor Engineer Westinghouse E. Watjen USN RC

• L. Norrholm, Senior Resident Inspector The inspector also talked with other licensee personnel during the course of the inspection, including engineers, operations, maintenance, performance and quality assurance personnel.

• Present at exit meeting conducted on 9/2/8 Action on Previous Inspection Items (Closed) Unresolved Item (311/81-19-01)

The i~specto~ revi~wed the engineering rep6rt on the feedwater hammer test (see paragraph 3.c.).

The inspector had no further questions on this ite * Uriit 2 Startup Test Data Review

- The in~pector reviewed test data packages for both completed startup tests and tests in progres Completed tests were reviewed fort.he following:

identification of deficiencies or exceptions to tests and their reso-1 ution, proper administrative review of test changes, annotation Of change in test procedure and verification that changes did not alt~r test objec-tives, verification th~t test data and procedure steps were properly recorded, initialed and dated,.

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engine~ring analysis and evaluation of test results, including comparison of results with acceptance criteria, review and acceptance of test results in accordance with the Startup Manua % Power Plateau Completed Tests SUP 81.3, Turbine Overspeed Trip Test, released for test May 30, 1981, was performed successfully on June 11, 1981, after rework of the trip mechanis Three on-the-spot changes were properly mad No test exceptions were note SUP 82.5, Shutdown from Outside the Control Room, was released for test June 23, 1981, and performed June 24, 198 One change was properly mad Minor deficiencies noted in Station Operations Review Committee (SORC) minutes are being corrected by procedural changes or Design Change Request SUP 82.6, Loss of Off site Power, was released for test June 2, 1981, and performed successfully on June 23, 198 Minor deficiencies noted in SORC minutes are to be corrected as abov SUP 81.5, Dynamic Automatic Steam Dump Control, was released for test May 25, 1981, and performed May 27-28, 198 While the test was successful, the operating characteristics of the steam dumps here and during load swing tests have resulted in a request to Site Engineering to review the design and installation of the steam dump valve The results of the above tests were reviewed by SORC at Meeting 81-56 on June 24, 1981 and approved by the Station Manager on June 25, 198 % Power Plateau Completed Tests SUP 81.4, Automatic Steam Generator Level Control, was released for test June 30, 1981, and performed, except for the steps requiring parallel operation of main feed pumps, at the 30% power platea The feedwater demand at 30% power was not great enough to operate the two feed pumps in parallel; parallel operation was successfully tested at 50% rated thermal power on July 24, 198 Three on-the-spot changes were procedural in nature, did not affect test objectives, and were properly reviewe SUP 81.6, Automatic Reactor Control, was released for test June 30, 1981, and performed successfully on July 4, 198 Three changes did not alter test conditions or objectives and were properly reviewed.

The above tests were reviewed by SORC on July 29, 1981, and approved by the Station Manager on August 7, 198 No items of noncompliance were identifie % Power Plateau Completed Tests SUP 81.10, Static RCCA Drop and RCCA Below Bank Position Measurements, was released for test July 14, 1981, and conducted on July 21-22, 1981. No on-the-spot changes were made to the test procedur The only test exception substituted RCS and pressurizer boron samples for the less accurate boric acid and primary water integrator reading The acceptance criterion for the nuclear enthalpy hot channel factor with rod H-12 11dropped

was me Results were reviewed by SORC on July 29, 1981, and approved by the Station Manager on August 7, 198 The inspector reviewed the completed test procedure, flux maps and thermocouple maps and spot-checked calculation SUP 81.9, RCCA Pseudo Ejection and RCCA Above Bank Position Measurement, was released for test July 14, 198 The test was performed on July 22, 198 The acceptance criteria for nuclear enthalpy and heat flux hot channel factors were me Results were reviewed by SORC on July 29, 1981, and approved by the Station Manager on August 7, 198 The inspector reviewed the completed procedure and the supporting flux map SUP 82.4, Rods Drop and Plant Trip, was released for test July 21, 1981, and performed July 23, 1981 from 46% Rated Thermal Powe Dropping rods B-4 and D-14 tripped the reactor protection system and tripped the plan Rod E-3 (the slowest rod from previous drop time tests) was timed in its drop to be 1.26 second All systems performed as expecte The acceptance criteria as modified by Change 1 to the Startup Test Procedure, incorporating Revision 2 to the NSSSVendor procedure, were all me The single test exception highlighted one change in NSSS Vendor acceptance criteri The test data were reviewed by SORC on July 29, 1981 and approved by the Station Manager on August 7, 198 A feedwater hammer test, described in Appendix G to SUP 80.1, was performed in conjunction with the trip resulting from performance of SUP 82.4 as described abov The inspector reviewed the engineering report (No. 66268 dated August 12, 1981) describing

the results of monitoring at two locations~tfte dfs-placement on three axes of the feedwater piping for Steam Generator #21 and the dynamic pressure response at drain valve 21BF-5 The maximum motion was approximately 0.35 inches peak-to-peak on the Z-axis with a frequency of 3.33 H No dynamic pressure response was noted during the transien.

Test Witnessing (a) Test Conditions Verified The tests discussed below were witnessed by the inspector and the resident inspecto The following were verified by direct observation:

appropriate procedures available and in use, crew requirements met, crew actions coordinated and timely, test prerequisites met, pertinent technical specification and license conditions met, special test equipment calibrated and in service; transient tests calibrated to common time base, quick summary analysis performed, all data collected for final revie (b) Transient Tests Witnessed SUP 82.2, Large Load Reduction Test, was performed from near the 100% rated thermal power (RTP) Level on September 1, 198 Power was reduced from 97% RTP to 45% RTP at the rate of 200% per minute as specified by the test procedur Inspector observation of the test and preliminary review of the data showed that the test met the specified acceptance criteri Licensee.test personnel judged the test successful after preliminary review of the dat SUP 82.9, Generator Trip from 100% Power, was performed on September 2, 198 The unit was tripped from approximately 98% RTP by opening the generator circuit breaker Licensee test personnel stated that all systems performed as expected and their preliminary assessment was that the test was acceptabl Inspector observation of the test and preliminary review of the data confirmed that the test generally met acceptance criteria, although it appeared that

one steam generator safety valve did lift and more detailed analysis of the transient response for the RTD for hot leg tem-perature is required for full acceptanc This will be an item for inspector follow-up (50-311/81-22-01).

No items of noncompliance were identifie.

Full Power License Conditions

• .c.(4)* Initial Test Program. The test program has been conducted as described in Chapter 13 of the Final Safety Analysis Report (FSAR).

No tests described in the FSAR were eliminate No modifications to test objectives or methods were noted by the inspecto One test, SUP 82.7, Steam Generator Moisture Carryover, was deleted at the 75% and 90% power levels at the recommendation of the reactor vendor and was identified not to be an essential test in a letter from Public Service Electric and Gas Company to NRC dated August 19, 198 The moisture carryover test is not a power ascension test identified in Regulatory Guide 1.68, Pre-operational and Initial Startup Test Programs for Water Cooled Power Reactor Moisture carryover tests were conducted at 100% RTP and lesser power level The licensee and the NSSS vendor are continuing review of the test results.

All other power ascension tests were completed in the period May 23-September 2, 1981, with a core burnup estimated by plant reactor engineers to be 1309 Megawatt-days per metric ton, equivalent to 34~ effective full power day The inspector had no further questions related to this license conditio number refers to paragraph in full power licens Exit Interview The inspector met with licensee management representatives (identified in paragraph 1) on September 2, 198 At the meeting, the purpose, scope and findings of this inspection were presented.