ML18219D889

Response to Questions Completing Facilitys Commitment to Stated Reg. Guides for Additional Information on Quality Assurance Program for Operations

ML18219D889
Person / Time
Site:	Cook
Issue date:	09/09/1977
From:	Tillinghast J Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Case E Office of Nuclear Reactor Regulation
References
Download: ML18219D889 (11)

Text

DISTRIBUTION AFTER ISSUANCE OF OPERATING LICENSE NRC FDRM 195 U S NUCLEAR REGULATORY COMI ION (2 76)

NFIC DISTRIBUTION FoR PART 50 DOCKET MATERIAL ooc TO

Mr. Edson G. Case IndOiana G Mihhigan Power Co.

FROM:

New York, N. Y.

10004 John Tillinghast DATE OF DOCUMENT 09/09/77 DATE RECEIVED 09/15/77 LETTE R

gN OTO R IZE 0

@ORIGINAL gUNC LASS IF I E D C3coPV jfE']. f-/

77 (7 /?

PROP INPUT FORM NUMBER OF COPIES RECEIVED I

s DEscRIPTIDN Ltr~ Notorized 09/09/77.

~. Trans Following:

ENCLOSU RE Consists of response to questions 410.

410.33, 410.34 and 410.35 completeing Facility's commitment to the stated Reg.

Guides for add-itional information on. the Donald C. Cook Nuc.

Plant Quality Assurance Program.

32 1p PLANT NAME:

DONALD C COOK UNITS.1 g 2

jcm 09/15/77 SAFETY BRANCH CHIEF:

7 FOR ACTION/INFORMATION G FIL INTERNALDISTRI BUTION I G E (2)

OELD HANAUER CHECK STELLO EISENHUT SHAO BAER BUTLER GRIMES J.

COLLI S LPDR:

~

Qd TIC NSIC 16 CYS ACRS SENT CATE EXTERNALDISTRIBUTION CONTROl NUMBER

INDIANA a MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 September 9,

1977 Donald C. Cook Nuclear Plant Unit Nos.

162 Docket Nos.

50-315 and 50-316 DPR No.

58 and CPPR No.

61 Spp Qf(yg<

Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Case:

This letter is in response to the letter of August 17, 1977 from Mr. Karl Kniel, Chief Light Water Reactors Branch No. 2, Division of project Management NRC, which asked for additional information on the Donald C. Cook Nuclear Plant Quality Assurance Program for Operations.

The attachment to this letter responds to Questions 410.32, 410.33, 410.34 and 410.35 which complete our commitment to the stated Regulatory Guides.

We are presently in the process of assembling our responses to the recent, series of letters on the Operations QA Program so that they may be incorporated in FSAR Section 1.7.19.

We expect to have this completed and forwarded to you in the form of an amendment by September 30, 1977.

Very truly yours, JT:mam Attachments John Ti lingh s Vice Preside Sworn and s

scribed to before me on this t

day of September 1977 in New York County, New York cc:

see next page Not ublic GII<GpftY )I GURICAN Notary PubIIc, State of New York ffo. 31-4643431 Qualified In New York Countv 7r P+5f+J4+ cseersslss Expires slsrsb

30. is.'7:s.

V 0

~

k 0

~

h

~

~

It

ATTACHMENT TO LETTER OF SEPTEMBER 6

1977 410;32 (1.7.19.2)

References in our QA program which now use the word "responsive" will be changed to "comply."

The following is the list of Regulatory Guides and endorsed ANSI Standards with which we will comply:

f N18.7 1972 Administrative Controls

& QA for the Operating phase of Nuclear power plants Regulatory Guide 1.8, 9/75 "Personnel Selection and Training" 1

and M18.1 1971 Regulatory Guide 1.30, 8/72 "Quality Assurance Requirements for the Installation, Inspection and Testing of Instru-mentation and Electric Equipment, " and M45.2.4, 1972 Regulatory Guide 1.37, 3/73 "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear power plants, " and M45.2.1, 1973 Regulatory Guide 1.38, 10/76, "Quality Assurance Requirements for packaging,

Shipping, Receiving,

Storage, and Handling of Items for Water-Cooled Nuclear power plants" and N45.2.2, 1972 Regulatory Guide 1.39, 10/76, "Housekeeping Requirements for Water Cooled Nuclear power plants" and N45.2.3, 1973 Regulatory Guide 1.54, 6/73 "Quality Assurance Requirements for protective Coatings Applied to Water-Cooled Nuclear Power plants, " and N101.4, 1972 Regulatory Guide 1.58, 8/73, "Qualification of Nuclear power plant Inspection, Examination and Testing Personnel,"

and, M45.2.6, 1973 Regulatory Guide 1.64, 10/73, "Quality Assurance Requirements for the Design of Nuclear power Plants, " and N45.2.11, 1974 Regulatory Guide 1.74, 2/74, "Quality Assurance Terms and Definitions, "

and. N45.2.10, 1973 Regulatory Regulatory Guide 1.88, 10/76, "Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records, " and N45.2.9, 1974 Guide 1.94, 4/76, "Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction phase of Nuclear power Plants, " and N45.2.5, 1974

o e

n o

f

(

~

e gs (

o o

o e

e e

~

~

~

~

e

[( 4oe

410. 33 (1.7.19.2)

Regulatory Guide 1.58, 8/73 is committed to directly in the preceding answer.

421.34 (ib.l7.19.2)

Our response to Question 421.12 (1.17.19.2) will be revised to state:

The systems, components and structures controlled by the QA Program are those identified as Class I.

An example of the classification and a partial list of Class I items is shown in Appendix B to the FSAR.

This has been expanded in a large computer printout "N" List which itemizes all Class I equipment controlled by the QA Program in design construction and operations.

Copies of the printout are available both at Cook Plant and AEPSC.

The above incorporates all equipment and systems to which the Operations QA Program applies.

Your letter questioned the classification of twelve (12) items.

These are addressed individually as follows:

1.

Sampling lines are Class I up to and including the containment isolation valves.

2.

The turbine stop valves are not Class I.

For Cook

Plant, the steam generator stop valves are the Class I valves.

3.

Leak Detection System these are described in the FSAR Question 4.20, none are Class I.

4.

Combustible Gas Control System the hydrogen recombiner system is Class I.

5.

Local Monitoring Panels and Controls for Systems Important to Safety the panels are Class I, their attachments are Class I, the controls are Class I where required 6.

Diesel Generators these are Class I 7.

Diesel Generator fuel oil, lubricating oil, starting and auxiliary systems are all Class I.

8.

Fuel Storage Building is part of the Class I Auxiliary Building.

~ II I ~

L

9.

Contxol and Diesel Generator Building is Class I.

10.

Electrical Cable Tunnels are Class I.

ll.

Diesel Fuel Storage and Day Tanks are Class I.

12.

, Spent Fuel pit Cooling System this is described in FSAR Section 9.4 it is not Class I.

410.35 We are presently in the process of assembling this

response, the acceptable parts of responses in our letters of May 17,

1977, June 28, 1977 and the present FSAR Secti'on 1.7.19, Amendment 72.

The revised Section 1.7.19 will be forwarded in the form of an Amendment to the FSAR by September 30, 1977.

f i P i>> g p

y s

Pl C

~ ~

N I

W) C F'4

= ~ - '~

F" I

~ N

~

P

'f I

C I

P

)4 CF p

a

~ I jl J

3 I

+~j CL

~

~ 'v II'II g" l(

l P

'Mr. E. G. Case Se ember 9,

1977 cc:

G. Charnoff R.

C. Callen R. J. Vollen P.

W. Steketee R.

W. Jurgensen D. V. Shaller Bridgman R. Walsh

RECEI VEO OOC UlCEhT PROCES)SIIIG URI I 1977 SEF'5 PM l2 24 K