ML20138G463

Forwards Detailed Justifications & Safety Evaluations for Power Ascension Test Mods,Including Test 10 Re APRM Calibr, Test 23A Re MSIV Functional Tests,Test 23B Re MSIV Full Isolation & Test 24 Re Relief Valves

ML20138G463
Person / Time
Site:	Hope Creek
Issue date:	10/17/1985
From:	Mittl R Public Service Enterprise Group
To:	Butler W Office of Nuclear Reactor Regulation
Shared Package
ML20138G467	List: ML20138G463 ML20138G468 ML20138G474 ML20138G479 ML20138G487 ML20138G493 ML20138G497 ML20138G505 ML20138G513
References
NUDOCS 8510250481
Download: ML20138G463 (5)

Text

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4 I Pubhc Servce Electnc and Gas Company l- LJ Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570. Newark, NJ 07101 Robert L Mitti General Manager Nuclear Assurance and Regulation s

l l October 17,-1985 m -

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Director of Nuclear Reactor Regulation United States Nuclear. Regulatory Commission s 7920 Norfolk Avenue '

, Bethesda, Maryland 20814 l

l Attention: Mr. Walter Butler, Chief .

l Licensing Branch 2 P Division of Licensing l

i Gentlemen:

POWER ASCENSION PROGRAM CIIANGES HOPE CREEK GENERATIhG ffATION l

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DOCKET No. 50-354 ,

Public Service Elo'ctri and Gas Company (PSE&G) hereby submits the following detailed justifications portaining to power ascension test modifJcationa (attached) for NRC consideration:

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1. Test Number 10 - Average Power Range Monitor Calibration

2. Test Number 23A - MSIV Functiona,' Tests l

3. Test Number 23B - MSIV Full (Isolatic'n

4. Test Number 24 - Relief Valves

5. Test Number 28E - Recirculatlo) System Cavitation g

6. Test Number 31 - Drywell Piping Vibration s

7. Test Number 32 - Reactor Water Cleanup System

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t Attachment 1 consists of' General Electric Company's technical i analysis and PSE&G's safety evaluation fc each of the(Afore i mentioned items. The conclusion for'oach' item shows?the y proposed modifications' pose no increas p n tisk to the health and safety of the public or an unreviewed safety d iuestion. 9 The Station Operation Review Comn'ittee (SORC) . has reviewed /

cach evaluation and concurs with the conclusionJ recched ! '

therein. '

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~k tsl A $ 4 ,f The Energy People k, i

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Director of Nuclear 2 10/17/85 Reactor Regulation 9

Attachment 2 consists of marked up FSAR pages applicable to the proposed testing modifications. These FSAR changes will be included as an amendment to the FSAR pending approval for implementation from the NRC.

We have also included another copy of PSE&G's safety evaluation Test Number 28D - Recirculation Pump Runback which was sub-mitted on October 4, 1985. In reviewing our copy of the submittal we have discovered that the cover page to this safety evaluation was missing and an incorrect copy of sheet 2 was included. Please replace the previously submitted safety evaluation with Attachment 3.

The balance of justifications associated with the power accension test modifications are in the detailed review process in support of the safety evaluation and will be submitted as soon as possible.

Since the enclosed modifications impact finalizing the related power ascension testing detailed procedures, un expedited review is requested. PSE&G is ready to meet with cognizant NRC personnel *.o discuss the proposed modifications should you require additional information.

Very truly yours,

,s/ -

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Attachments C D.H. Wagner USNRC Licensing Project Manager A.R. Blough USNRC Senior Resident Inspector

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W ATTAC11 MENT 1

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GENERAL ELECTRIC COMPANY TECHNICAL ANALYSIS 7 HOPE CREEK GENERATING STATION L.

6 TEST NUMBER 10 - AVERAGE POWER RANGE MONITOR CALIBRATION SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE OBJECTIVES:

Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraph 5.y requires that the incore neutron flux instrumentation be calibrated and proper operation verified during power ascension testing. Tes t Number 10, Average Power Range Monitor (APRM) Calibration, performs calibration of the APRM system during heatup below rated pressure and at Test Conditions 1, 2, 3, 5, and 6. It is proposed to substitute APRM calibration by Technical Specification surveillance procedures for calibration by Test Number 10 at Test Conditions 1, 2, 3, 5 and 6. In addition, it is proposed to delete APRM calibration during heatup and to preadjust the LPRM and APRM gains based on results from previous plant startups.

DISCUSSION:

It is proposed that prior to plant startup, gain settings from past BWR startup testing be used to input an optimum low power APRM gain setting. The APRM and LPRM gains will be preadjusted to realistic but conservative values based on results from previous plant startups with similar equipment. The predetermined gains will be chosen to provide IRM/APRM indication overlap as well as indication greater than actual reactor powe r. However, the gains will be chosen to not 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). As a result of these preadjusted gains, the APRM calibration during heatup can be deleted.

Although calibration of the APRMs is not required below 25%

power by the Technical Specifications because considerable margin exists to thermal limits, the initial calibration will be performed during Test Condition 1 using the plant APRM calibration surveillance procedures when sufficient feedwater flow exists to provide an accurate heat balance (10-201 power).

Plant Technical Specifications (section 3/4.3.1) define the minimum calibration requirements for the APRM system as part of the Surveillance Requirements for the Reactor Protection Instrumentation System. The applicable Technical Specification section requires that at least once per seven days, the APRM system shall be calibrated and gains adjusted if the absolute power difference is greater than 2% (Test Number 10 requires a difference of +7%, -0% which has an added conservatism that is unnecessary and not required by the Technical Specification).

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e Test Number 10 currently directs calibration to be performed by using the Techical Specification surveillance procedures. The Technical Specification calibration consists of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during operation at greater than or equal to 25% of rated thermal power. Compliance with these Technical Specification requirements will satisfy the objectives of Test Number 10 at Test Conditions 2, 3, 5, and 6.

CONCLUSION Use of gain settings determined from previous BWR st'-'-

testing prior to initial APRM calibration and cor'~ ^ 4 d.. .'C - .a the Plant Technical Specification Surveillance F pr4 p ut - tor APRM calibration, via existing surveillance pros i tes, <!)

satisfy the objectives of Regulatory Guide 1.68 Yt '

'"4 tx paragraph 5.y. Based on the above discussions, - ru .. d change will not adversely affect any safety syste_m m che safe operation of the plant, and as such, does not involve an unreviewed safety question. Therefore, the Plant Technical Specification Surveillance Procedures for APRM calibration can be substituted for Test Number 10, APRM Calibration.

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