ML20138G468

Safety Evaluation:Replace Power Ascension Test Program APRM Calibr Procedure W/Tech Spec Surveillance Procedures & Delete APRM Calibr During Heatup

ML20138G468
Person / Time
Site:	Hope Creek
Issue date:	10/09/1985
From:	Public Service Enterprise Group
To:
Shared Package
ML20138G467	List: ML20138G463 ML20138G468 ML20138G474 ML20138G479 ML20138G487 ML20138G493 ML20138G497 ML20138G505 ML20138G513
References
PSE-SE-Z-007, PSE-SE-Z-7, NUDOCS 8510250482
Download: ML20138G468 (4)

Text

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J'o PUBLIC SERVICE ELECTRIC AND GAS CONPANY HOPE CREEK PROJECT SAFETY EVALUATION No. PSE-SE-Z-007 TITLE: REPLACE POWER ASCENSION TEST PROGRAM APRM CALIBRATION PROCEDURE WITH TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES AND DELETE THE APRM CALIBRATION DURING HEATUP Date: OCT 9 1985 1.0 PURPOSE The purpose of this Safety Evaluation is to document the results of the evaluation of the proposal to replace the Hope Creek power ascension test procedure for APRM calibration with the Hope Creek Technical Specification surveillance procedures and to delete the preliminary APRM calibration during heatup.

2.0 SCOPE The APRM system is part of the incore neutron monitoring system.

3.0 REFERENCES

1. FSAR Chapter 7 and 14

2. GE Startup Test Specification (STS) No. 23A4137, Revision 0

3. NRC Regulatory Guide 1.68, Revision 2, August 1978

4. Hope Creek Generating Station Draft Power Ascension Procedure: TE-SU.SE-122(O)

5. Hope Creek Generating Station Draft Power Ascension Procedure TE-SU.SE-121(O)

6. Hope Creek Generating Station Draft Technical Specifications

7. Hope Creek Generating Station Draft Reactor Engineering Procedure: RE-ST.SE-002(O)

8. Hope Creek Generating Station Draft Reactor Engineering Procedure: RE-RA.22-001(O)

9. Hope Craek Generating Stetion Draft Instrumentation and Control Procedure: IC-CC.SE-030(O)

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2 4.0 DISCUSSION Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraph 5.y requires that the incore neutron flux instrumentation be calibrated and its performance verified at approximately 25%, 50%, 75%, and 100 % power.

Appendix C, paragraph 4.c requires that reactor power be determined by heat balance and that the nuclear instruments be calibrated accordingly at approximately 25%, 50%, 75%, and 100 % power. Tes t Number 10, Average Power Range Monitor APRM Calibration, performs the calibration of the APRM system during heatup below rated pressure and at Test Conditions 1, 2, 3, 5, and 6. It is proposed that the Hope Creek Technical Specification surveillance procedures for APRM calibration be substituted for the APRM calibration performed by Test Number 10. It is also proposed to delete the APRM calibration during heatup and instead to preadjust the LPRM and APRM gains based on results from previous BWR plant startups.

.; Presently, the draft power ascension procedure for APRM calibration specifies that the calibration be performed in accordance with the plant Technical Specification surveillance procedures. The power ascension procedure is scheduled by the power ascension test program test sequencer. This proposal would reference plant i procedures directly in the test sequencer and eliminate l

the intervening power ascension test procedure.

Therefore, the proposal does not represent a change in the way the calibrations are performed. It should be noted however, that the power ascension test procedure requires the APRM to be calibrated within +7, -0% of rated thermal power as indicated by heat balance whereas the Technical Specification surveillance requires that the APRM system be calibrated and gains adjusted if the absolute power difference is greater than 2%. The power ascension test procedure has a conservatism that is not required for reactor safety. Compliance with the Technical Specification criterion is adequate.

Prior to startup, gain settings from past BWR starti:p testing will be used to determine an optimum low power gain setting. The APRM and LPRM gains will be ,

preadjusted to realistic but conservative values based on i results from previous plant startups with similar equipment. The predetermined gains will be chosen to l

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provide IRM/APRM indication overlap as well as indication greater than actual reactor power. However, the gains will be chosen so as'not to result in indication that is so much greater than actual power that the potential for scram is unacceptable (note: the APRM scram setpoint will be established at less than or equal to 20% above the test condition power level in the RUN mode and is fixed at the 15% power level in the STARTUP mode. ) As a result of these preadjusted gains, the APRM calibration during heatup can be deleted.

5.0 CONCLUSION

Compliance with the plant Technical Specification surveillance procedures using the power ascension test 1

program test sequencer to schedule calibrations for APRM calibration will satisfy the objectives of Regulatory Guide 1.68, Appendix A, paragraph 5.y and Appendix C, paragraph 4.c and the intent of Test Number 10. In addition, because of the conservative preadjustment of the LP9M and APRM gains and the setting of the scram setpoint, APRM calibration during heattp can be safely deleted. For these reasons, the proposed changes will not adversely af fect any safety systems or impair the safe operation of the plant, and as such, do not involve an unreviewed safety question. Therefore, the plant Technical Specification procedures for APRM calibration can be substituted for Test Number 10, APRM Calibration, and the APRM calibration during heatup can be deleted.

6.0 DOCUMENTS GENERATED None 7.0 RECOMMEDATIONS The FSAR and startup test procedures shall be revised to reflect the replacement of the APRM calibration power ascension test procedure with the plant Technical Specification surveillance procedures for APRM ,

calibration and the deletion of the preliminary APRM calibration during heatup.

8.0 ATTACHMENTS None PSE-SE-2-007 3 of 4

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