ML20214T871

Requests Addl Info Specified in Encl Draft Ltr for Review of Licensee Response to Generic Ltr 83-28

ML20214T871
Person / Time
Site:	Diablo Canyon, 05000000
Issue date:	03/07/1985
From:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML20213E738	List: IR 05000275/1984007 ML20213E736 ML20213F014 ML20213F028 ML20213F157 ML20213F161 ML20213F166 ML20213F170 ML20213F182 ML20213F185 ML20214E696 ML20214T016 ML20214T080 ML20214T120 ML20214T141 ML20214T182 ML20214T191 ML20214T211 ML20214T271 ML20214T311 ML20214T334 ML20214T421 ML20214T453 ML20214T491 ML20214T582 ML20214T625 ML20214T670 ML20214T707 ML20214T725 ML20214T784 ML20214T834 ML20214T860 ML20214T871 ML20214T919 ML20214T946 ML20214T972 ML20214T976 ML20214T986 ML20214T994 ML20214U808 ML20214U872
References
FOIA-86-197 GL-83-28, TAC-52913, TAC-53068, TAC-53749, TAC-54059, NUDOCS 8706100460
Download: ML20214T871 (3)

Text

7: ,

o y JcG. L.g

. s e" "ECo,#'o, UNITED STATES 3[/yi c.c 'i

'j NUCLEAR REGULATORY COMMISSION.

REGION V-

3,.g$ ' .'s;'" g 1450 MARIA LANE,sulTE 210

%, ' N ># ,d WALNUT CREEK, CALIFoRNI A 94596

"*** MAR 7 1985 MEMORANDUM FOR: ' Hugh R. Thompson, Jr. , Director Division of Licensing, NRR FROM: Dennis F. Kirsch, Acting Director Division of Reactor Safety and Projects

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 83-28 TACS NOS. 52913, 53749, 53068 and 54059 Plant Name: Diablo Canyon Unit 1 Docket No: 50-275 Responsible Branch: Licensing Branch No. 3 Project Manager: H. Schierling Review Status: Incomplete In order to complete our review of this item, we find we need additional information as specified in the enclosed draft letter to the licensee. If you concur with these needs, please transmit this letter to the licensee at your earliest coevenience.

If yc,u have any questions, please call Jerry Zwetzig at FIS 463-3749.

e D nais . Kirsch, Acting Director Division of Reactor Safety and Projects

Enclosure:

Draft letter to licensee cc: H. Schierling, NRR G. Knighton, NRR }{

'( <

T. Alexion, NRR f S J. Stevens, NRR J. Hopkins, NRR gh '

hg J. Hannon, NRR v T. Novak, NRR J. Thoma, NRR R. Pate, RV D. Kirsch, RV G. Zwetzig, RV l

/l 0706100460 870604 PDR FOIA HOLMES86-197 PDR j

-t .

Docket No. 50-275 Mr. J. D. Shiffer, Vice President Nuclear Power Generation -

c/o Nuclear Power Generation, Licensing Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106

SUBJECT:

GENERIC LETTER 83-28 The staff is continuing its review and evaluation of the PG&E responses to Generic Letter 83-28, Implications of Salem ATWS Event. Based on our review as of this date we have identified the need for additional information as listed in the enclosure. It is requested that you provide the information identified in the enclosure within 30 days.

Sincerely, George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page.

i I

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION RELATING TO GENERIC LETTER 83-28 Facility: Diablo Canyon Unit 1 Docket No: 50-275 ,

1. )

Regarding Position 3.1.1, please confirm that the post-maintenance l testing required of safety-related components in the reactor trip system, demonstrates that the component is capable of performing all required {

s safety functions.

2. Regarding Position 3.1.2, your letter of January 2,1985, indicated that nine vendor recommendations still required review. Please confirm that this review has been completed for Unit I and that appropriate procedure revisions have been completed.

(

3. Regarding Positions 3.2.1 and 3.2.2, your letter of November 7, 1983, committed to submit a statement by August 1,1985, confirming implementation of these positions for Unit 1. Please ensure that the post-maintenance testing required of all safety-related components by such implementation, will verify the capability of components to perform all required safety functions. In addition, please explicitly confirm in your August 1 submittal that post-maintenance testing will verify this capability.

4. Regarding Position 4.5.1, your letter of January 24, 1985 (in Enclosure 2, paragraph B), states that "...on-line, independent, functional testing of the undervoltage and shunt trip features is performed in Modes 1 through 4, after maintenance, in accordance with STP I-33C." Please indicate the minimum frequency of breaker maintenance. This is needed to verify that the individual functienal testing will be performed "on-line" in Modes 1 through 4, as well as during refueling outages.

/

_m. , , . . - .. _ . . _

_