ML20209D304

Forwards List of Questions & Comments on Draft Test Procedure 42.7 Re Natural Circulation & Boron Mixing Tests. Items Addressed Need to Be Resolved Prior to Approval of Test Procedure

ML20209D304
Person / Time
Site:	05000000, Diablo Canyon
Issue date:	09/19/1984
From:	Sheron B Office of Nuclear Reactor Regulation
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-86-197 TAC-51638, TAC-55634, NUDOCS 8409270735
Download: ML20209D304 (3)

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J Spa ato oq#o, UNITED STATES j

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MEMORANDUM FOR:

George Knighton, Chief, Licensing Branch No. 3, Division of Licensing FROM:

Brian W. Sheron, Chief, Reactor Systems Branch

SUBJECT:

DIABLO CANYON UNIT 1 - RSB REVIEW 0F NATURAL CIRCULATION AND BORON MIXING TESTS (TAC 55634)

The Reactor Systems Branch (RSB) has completed its review of the draft Diablo Canyon Unit 1 Test Procedure No. 42.7 for natural circulation and boron mixing tests and the pre-test report transmitted by PG&E's letter j

dated May 11, 1983.

Enclosed is a list of staff's questions and I

comments regarding the draft test procedure.

Most of the staff's comments have been discussed with PG&E during our plant visit on August 22, i

1984.

RSB believes that all items addressed in Enclosure 1 to this memo need to be resolved prior to staff approval of the test procedure. f I

&UY 1

i Brian W. Sheron, Ch'ief Reactor Systems Branch l

Division of Systems Integretion-

Enclosure:

As stated r

cc:

R. Bernero R. Houston, bng RSB S/Ls C. Graves G. Mazetis F. Orr f

CONTACT:

C. Liang, x24754 s,

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- i ENCLOSURE 1

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DIA8LO CANYON UNIT 1 j -

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The licensee should develop proper criteria for test operation and j

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p termination.

2.

Tests should include plant cooldown to RHR initiation conditions r.,

and to cold shutdown using RHR system.

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The licensee should verify the effects of potential single failure

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.i on loop charging valve to the function of the auxiliary pressurizer d

l spray system during>RCS depressurization.

4.

The" test should demonstrate the adequacy of the safety related

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'ycendensate storage capacity for plant cooldown.

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-, The Itest shou'd demonstrate'the adequacy of the safety yelated r

nitrogen supply to air operated atmospheric steam dump valves for

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plantcodidown.

Condenser steam dump should not be operated during I

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The test s'hould ' incl,u e fo6r (4) hours of hot standby time before i

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cooldown to Mode'4;'

7.

During the test, ihe charging pumps should take suction from the 4

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safety related RWST. Non safety related reactor makeup control

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system'should not be employed during'the tests.

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Justification should be provided for manual operator's action outside the control room during the tests in light of BTP RSB 5-1.

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The normal pressurizer spray valves should not be used during the i

test.

10.

In the proposed test procedure, the RCPs are manually tripped after the reactor trip.. The staff suggested' that the time gap between the e

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2-1 reactor trip and the RCPs trip should be minimized to lessen the upper head cooling as a result of forced RCS flow.

1 11.

PG&E should submit a post-test report following the subject tests.

The report should include the necessary analysis to address the

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compliance of BTP RSB 5-1.

The use of non-safety related equipment

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in the test should be substantiated in the final report.

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