ML20214T860

Forwards Current List of NRR Allegation Numbers & Corresponding Util Ref Numbers

ML20214T860
Person / Time
Site:	Diablo Canyon, 05000000
Issue date:	02/25/1985
From:	Ley M Office of Nuclear Reactor Regulation
To:	Meeks R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
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 NUDOCS 8706100452
Download: ML20214T860 (5)

Text

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FEB 2 51985 Docket Nos.: 50-275/323 NOTE T0: Ronald A. Meeks, Senior Investigaton Office of Investigations Field Office Region V FROM: Marilyn C. Ley,_ Project Manager Licensing Branch No. 3 Division of Licensin'g 4,

SUBJECT:

REFERENCES FOR DIABLO CANYON ALLEGATION RESOLUTION As requested in our telephone conversation today, attached is a current listing of NRR allegation nuinbers. and their corre-sponding Pacific Gas and Electric reference letter number (s).

You will be informed of any updates to this list.

44 c.d7 Marilyn C. Ley

Enclosure:

As stated l l

1 cc: C. Grimes

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o,, UNITED STATES

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o . . GJ WASHWCTON. D. C. 20555 FEB 221985 -

MEMORANDUM FOR: Gus C. Lainais, Assistant Director

• for Operating Reactors, DL Thomas M. Novak, Assistant Director for Licensing, DL FROM: Dennis M. Cr' u tchfield, Assistant Director for Safety Assessment, DL

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 83-28 ITEMS 2.1, 2.2, 3.1.3, 3.2.3, 4.4 AND 4.5

Reference:

Memo from R. Wayne. Houston to the Assistant Directors in the Division of Licensing on the above subject, dated January 22, 1985.

The memorandum contains guidance for the project managers for issuing requests for additional information (RAIs) regarding the subject Generic Letter (GL) 83-28 items. Enclosure 1 contains a sample letter for issuance to the licensees.

All plant-specific infonnation is underlined and in parenthesis.

1 Enclosure 2 presents plant-specific RAIs. background / supplemental infonnation regarding the It is requested that the project managers review Enclosure 2 and write the appropriate RAI. In most cases, the ICSB wording .

(see reference) should be sufficient. -

It is requested that the project managers issue the RAIs as soon as possible.

It is also requested that the appropriate LPMs be put on distribution for all RAIs, and that they are provided with copies of all responses to the RAIs.

Enclosure 3 provides a listing of.all the LPMs. If there are any questions, contact T. Alexion (x28929) of my staff.

C , Y - m a .s

'M Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

Enclosures:

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ENCLOSURE 1 SAMPLE LETTER FOR ISSUANCE TO LICENSEES (DRESDEN)

DOCKET N0(S).

LICENSEE ADDRESS l i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF REVIEW OF LICENSEE RESPONSES TO GENERIC LETTER 83-28 Re:

(Dresden Nuclear Power Station. Unit Nos. 2 and 3) .

The staff has completed a preliminary review to assess the completeness and adequacy 3.2.3, of licensee 4.4 and 4.5. Forresponses to Generic Letter 83-28 Itess 2.1, 2.2, 3.1.3, the (Dresden Units), your responses were found to be incomplete for Items _(2.1, 2.2.2 and 4.5.3). Brief descriptions of the deficiencies are given as guidelines for corrective action in the enclosed request for additional information. Efforts by Owners Groups, INPO and NSSS Vendors have been or are being made to produce generic responses that may be useful in meeting the requirements of Generic Letter 83-28 Iters (2.1, 2.2.2 and 4.5.3). You may wish to contact your Owner's Group or INPO regarding the applicability of such generic responses to your (Dresden Units).

In order to preserve our present review schedule, the staff needs to have

- the supplementary information within 60 days for Items (2.1, 2.2.2), and within 90 days for Item (4.5.3). (If you intend to formally endorse the '

BWR Owners Group response to Item 4.5.3 (NEDC-30844), the staff should. be advised within 60 days. Your plant-5 )ecific response to Item 4.5.3 should 3

then be provided within 90 days after 1RC completes its review of NEDC-30844 and issues its evaluation). We request your cooperation in meeting this schedule.

This request for additional information was approved by the Office of Management 1985. and Budget under clearance number 3150-0011 which expires' April 30,  !

Comments on burden and duplication may be directed to the Office of I Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503. l

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Sincerely, John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

Request for Additional Info rma tion

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- ENCLOSURE 2 BACKGROUND / SUPPLEMENTAL iNFORMATION FOR PLANT-SPECIFIC RAIs

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1. The statement regarding efforts by Owners Groups should include all items that were found to be incomplete (as applicable) except Items 3.1.3 and 3.2.3

2. A 60-day r'esponse time is appropriate for all items except Items 4.4 and 4.5, where a 90-day response time is appropriate.

For Westinghouse plants that fornelly endorsed WCAP-10271 as their generic response to Item 4.5.3, plant-specific responses to Item 4.5.3 should be provided 90 days after NRC completes its review of WCAP-10271 and Supplement 1. Review completion of the WCAP is expected shortly. For GE plants that intend to forwelly endorse NEDC-30844 as their generic response to Item 4.5.3, the staff should be advised within 60 days. The plant-specific responses to Item 4.5.3 should be provided 90 days after NRC completes its review

, of NEDC-30844 3.

RAls for Item 2.2.1.6 regarding an equipment classification program for equipment important to safety should not be issued. GL 83-28 states that this information is not required to be submitted for staff review.

4 Regarding Item 4.5.3 for BWRs, a statement should be added to say that adequate justification has been provided to not require modification of the backup scram to provide on-line testability .

(see Dresden example). The staff has concluded, however, that testing of the backup scram should be included in the plant technical specifications - preferably during refueling outages (memo from Houston to the Assistant Directors in the Division of Licensing, dated November 16,1984).

5. T. Alexion, D. Lasher, and D. Beckham, should be on distribution for all 1

1 RAls. Also, the appropriate LPMs should be on distribution as well ---

(see Enclosure 3). I 1

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ENCLOSURE 3 ^

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MPA LISTING FOR GL 83-28 item

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Item item 1.1 - Post-Trip Review (Pro _ LM (MPA B-76) Descr. and Procedure) gram A. Sournia Item 1.2 - ,

Post Trip Review (Data and (MPA 8-85) In fo. ) A. Sournia Item 2.1 - Eauip. Class. & Vendor (MPA 8 77) R. Auluck Item 2.2 -

Interface (RTS Components) Equ1p. Class. 8 Vendor (MPAS86) R. Aulock Interface (All Other S.R.

Components)

Items 3.1.1/- Post-Maintenance Testing J. Hopkins 3.1.2 Verificatfon (RTS Items 3.2.1/- Post-Maintenance Testing j (MPA B-78) Components) 3.2.2 J. Hopkins (MPA8-87)

Verification.(All Other ,

' S-R Components).

Item 3.1.3 - Post-Maintenance Testing (HPA B-79) J. Hopkins Item 3.2.3 -

T.S. Changes (RTS Post-Mafntenance Testing Components) (MPA B-88) J. Hopkins T.S.' Changes (All Other I 5.R. Components) .

Item 4.1 - RTS Reliability (Vendor (MPA B-80)

J. Hopkins Related Modifications Items 4.2.1/- RTS Relfability (Maint.

r 4.2.2 R. Perch  !

l and Surveillance) Items 4.2.3/- RTS Reliability (Testing R. Perch (MPA B-81) 4.2.4 . andReplacement)

I k (WA8-89)

Item 4.3 - 'RTS Reitability (Auto (MPA B-82) L. 01shan Item 4.3(TS Actuation of Shunt Trfp) RTS Reitablitty (Auto L. 01shan (MPA B-90)Actuation ). of Shunt Trip-Tech. Specs.)

Item 4.4 - RTS Relfabflity (!sprovent. R. Kadhabi (WA 8-91) in Maint, & Test Procedures-88W Plants) -

Item 4.5.1 - RTS Reliability (System (MPA 8-92) Functional Testfng - Tes.t J. Stevens !'

Descriptton)

.- Items 4.5.2/- RTS Re11 ability (System J. Stevens 4.5.3 Functional Testing -

1 I (MPA8-93) Deviation from Reouf rements and T.S. Changes)  :

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Item 2.1 (part 1) - Incomplete Licensee must supply a statement confirming that reactor trip system components

!J were reviewed and that they are identified as safety-related on documents, procedures and information handling systems.

Item 2.1 (part 2) - Incomplete Licensee needs to submit detailed infomation describing his vendor. interface program for reactor trip system components. Information supplied should state how the program assures that vendor technical information is kept complete, 4 current and controlled throughout the life of the plant and should also indi-cate how the program will be implemented at DIABLO CANYON 182.

Item 2.2.1 - Incomplete Licensee needs to submit information on how equipment will be classified as safety-related and will be designated as such an plant documentation as

requested in.sub-items 2.2.1.1 to 2.2.1.6 of the generic letter.

Item,2.2.2 - Incompiete Licensee needs to supply detailed information describing his vendor interface prog' ram for all safety-related components. Infomation supplied should state j how the program assures that vendor technical information is kept complete, current and controlled throughout the life of the plant and should also indicate how the program will be implemented at DIABLO CANYON 182.

Item 3.1.3 - Incomplete

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Results of review of test and maintenance programs shall identify any post-

_ maintenance testirg that may degrade rather than enhance safety and shall describe actions to be taken including submitting needed Technical Specifica .,

tion changes.

Item 3.2.3 - Incomplete I

Same as item 3.1.3.

Item 4.5.3 - Incomplete Applicant needs to provide results of review of existing or proposed intervals ,

for on-line testing considering the concerns of items 4.5.3.1 to 4.5.3.5 of 1 i

the generic letter. Proposed Technical Specification changes resulting from I this review shall be submitted for review.

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