ML20236C364

Forwards List of Outstanding Items in Safety Review of Application for Ols.Requests Schedule for Supplying Addl Info for All Listed Outstanding Items within 7 Days of Ltr Receipt

ML20236C364
Person / Time
Site:	Diablo Canyon, 05000000
Issue date:	09/26/1975
From:	Parr O Office of Nuclear Reactor Regulation
To:	Morrissey J PACIFIC GAS & ELECTRIC CO.
Shared Package
ML20236A877	List: ML20236A874 ML20236A896 ML20236A920 ML20236A950 ML20236A959 ML20236A975 ML20236B012 ML20236B016 ML20236B024 ML20236B067 ML20236B072 ML20236B116 ML20236B278 ML20236B286 ML20236B312 ML20236B315 ML20236B345 ML20236B356 ML20236B362 ML20236B403 ML20236B420 ML20236B436 ML20236B440 ML20236B476 ML20236B480 ML20236B506 ML20236B514 ML20236B522 ML20236B539 ML20236B547 ML20236B550 ML20236B560 ML20236B571 ML20236B594 ML20236B612 ML20236B630 ML20236B635 ML20236B650 ML20236B655 ML20236B670 ML20236B686 ML20236B695 ML20236B701 ML20236B705 ML20236B708 ML20236B726 ML20236B737 ML20236B748 ML20236B755 ML20236B793 ... further results
References
FOIA-87-214 NUDOCS 8707300028
Download: ML20236C364 (5)

Text

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'G SEP 2 6 B75 l Distribution NRC - PRD W. Hass Local PDR TIC

@ cket File J. R. Buchana LWR 1-3 File T.B. Abernath !

d 323 R$Hein an R. W. Klecker i ELD Pacific Gas and Electric Company

() l DAllison ATTN: Mr. John C. Morrissey 8" Vice President and General Counsel TR Branch Chiefs i

4 77 Beale Street rar h Cheifs San Francisco, California 94106 p

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Centlemen:

The purpose of this letter is to call your attention to the list of items which remain outstanding in the safety review of the application y for operating licenses for Diablo Canyon Units 1 and 2. A list of these items and their status is given in the enclosute to this letter and in Section 22 of Supplement Number 3 to the Safety Evaluation i

Report. As indicated in the enclosure, the resolution of a number l of these items cannot be completed until additional information has been received from you. Although we realize that the majority of your efforts in recent months have been spent in the areas of geology i

and seismology, we want to emphasize that all of the outstanding items I

listed in the enclosure must be satisfactorily resolved before the issuance of operating licenses for the Diablo Canyon Units.

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Please inform us within 7 days af ter receipt of this letter of your schedule for supplying the additional information that is required for all of the outstanding items listed in the enclosure. Do not hesitate to contact us if you have any questions regarding the information that has been requested.

Sincerely, Orletog 5 . ,, 7 O.D.pg," ~ -j Olan D. Parr, Chief Light Water Reactors / y [o_.J Project Branch 1-3 Division of Reactor Licensing

Enclosure:

Outstanding Items /

I in the Diablo Canyon Safety Review -

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or ric?C,3 S88 Page 2 i ch#R OWarr:mj f

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87073'U~O'd~25~87'd'7Y1 PDR FOIA CONNORB7-214 k [

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l Sr.r 4 01975 Pacific Gas and Electric Company i

9 ces Philip A. Crane, Jr., Esq.

Pacific Gas and Electric Company 77 Beale Street

! San Francisco, California 94106 i

Andrew J. Skaff, Esq.

California Public Utilities Commission-  !

i 350 McAllister Street San Francisco, California '94102 Mr. Frederick Eissler, President l Scenic Shoreline Preservation conference, Inc. j 4623 More Mesa Drive Santa Barbara, California ' 93105 'j L ,

Ms. Raye Fleming l 1746 Chorro Street San Luis Obispo, California 93401 Ms. Sandra A. Silver 5055 Radford Avenue North Hollywood, California 91607 Mx. John Forster  ;

985 Pabs Street .

l San Luis Obispo, California 93401 j Mr. William P. Cornwell  ;

P. O. Box 453 Morro Bay, California 93442 Mr. W. J. Lindbald, Project Engineer ~ j Pacific Gas End Electric Cotapany 77 Beale Street San Francisco, California 94106 14r. Gordon A. Silver 5055 Radford Avenue f

North Hollywood, California 91607 orrie s

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Form AEC.318 (Rev. 9 53) AECM 0240 W u. s. oovannuswy ensuvine orness se74.sas. tee i

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. ENCLOSURE SEP 2 C 575 I l

OUTSTANDING ITFl!S IN THE DIABLO CANYON SAFETY REVIEW l

1. Effects of Tsunamis Caused by Near-Shore Generators Our evaluation of this item has not been completed; however, ,

we presently do not believe that we will require any additional information. ,

2. Earthquake Potential of the Hosgri Fault We have not yet received all of the additional information which was requested in our letter to you dated February 12, 1975.

3. Pipe Break Outside Containment i

Additional information on this item was requested in our letter to you dated August 7, 1975.

4. Seismic qualification of Category I Instrumentation and Electrical Equipment Part of the required information regarding qualification of balance-of-plant equipment was requested in our letter to you dated August 7, 1975. The remainder of this information is being requested from Westinghouse on a generic basis.

6. Thermal and Hydraulic Design We will require some additional information concerning fuel rod bowing af ter the first fuel cycle before our evaluation of- this item can be completed. This matter is being handled on a generic '

basis with Westinghouse.

8. Singic Failures in the Containment Sump Isolation Valves Our evaluation of this item has not been completed.. This item is related to the single failure analysis that we have requested in conjunction with the ECCS analysis (See item 9 below).  !

9. Emergency Core Cooling System Analysis We have not received all of the additional information which was requested in our letters to you dated April 3, 1975, June 13, 1975, and July 9, 1975. In addition your f'inal ECCS analysis for Unit 2 has not been receiv,ed. .

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10. Physical separation in the Process Analog System Additional information on this item was requested in our letter

- to you dated September 4, 1975.

11. ATWS Our evaluation of this item has not been completed. No additional information is required at this time.

12. Environmental Qualification of Category I Instrumentation and Electrical Equipment Part of this information regarding qualification of balance-of-plant equipment was requested in our letter to you dated August 7, 1975. The remainder of this information is being requested from Westinghouse on a generic basis.

16. Feedwater Hammer Our evaluation of this item has not been completed. No additional information is required at this time.

17. Tornado Missile Protection We have not yet received all of the information which was requested in our letter to you dated July 11, 1975.

In addition, as we have discussed with your representatives the following information will also be required.

(a) A discussion of areas other than the 4.16 kV switch-gear rooms where the emergency power busses cre vul-nerable to damage from tornado missiles. ,

(b) The reasons for the dif f erence between the tornado'

. missile resisting capabilities you have listed for the containment structure and the containment access hatches. (See Table 3.3-2 of the FSAR).

l (c) Additional discussion of the availability of reactor coolant makeup water following postulated damage to the refueling water storage tank from tornado missiles.

18. Fire Protection Additional information on this item was requested.in our letter to you dated August 7,1975. -

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19. Adequacy of the Reactor Vessel Supports Our evaluation of this item has not been completed. No additional information is required at this time.

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