ML17326B103
| ML17326B103 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/10/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0773E, AEP:NRC:773E, NUDOCS 8402140122 | |
| Download: ML17326B103 (8) | |
Text
'REGULATO INFORMATION DISTRIBUTION STEh'I (RIDS)
ACCESSION NBR;8002140122'OC",DATE.:
84/02/10 NOTARIZED!
NO DOCKET FACIL:50 315 Donald O',
Cook Nuclear'ower. Planti Un)t ic Indiana 8
05000315
'50>>316 Donald"CD Cook Nuclear: Power PlantE Unit 2'E -Indiana L
05000316 AUTH,NAME
'UTHOR AFFILIATION ALEXICHgM,P,
'ndiana*
8 Michigan Electric Co.
RECIP ~ NAME RECIPIENT AFFILIATION OENTONgH ~ RE Office. of Nuclear-Reactor Regulationr Director
SUBJECT:
Provide's commitment dates re emergency operating procedures upgr'ade program.'Table 1 of AEP:NRC:0773D modified to reflect dates.Revised table encl.
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 February 10, 1984 AEP:NRC:0773E Donald C. Cook.Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Status Report on Emergency Operating Procedures Upgrade Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comm1ssion Washington, DC 20555
Dear Mr. Denton:
Pursuant to our conversation w1th members of your staff regard1ng our submittal of AEP:NRC:0773D, American Electr1c Power Service Corporation agrees to the following commitment dates regarding our Emergency Operating Procedures Upgrade Program.
1.
Ne commit to have a procedure generation package completed by the end of September,
- 1984, and 2.
He commit to having our EOP's completed and implemented by the end of 1985.
Ne have modified Table 1 to AEP:NRC:0773D to reflect these two commitment dates.
The revised Table is attached to this letter.
This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, Vice President MPA/th Attachment cc:
John E. Dolan N. G. Smith, Jr.
Bridgman R. C. Callen G. Charnoff E.
R. Swanson, NRC Res1dent Inspector - Bridgman 8402140i22 8402i0 PDR ADOCK '05000315 F
TABLE 1
I.
e e
e en er t n e
n A.
Status Report Commitment:
April 1985 B.
Target:
September 1985 II.
et e
e e
A.
Program Plan Report B.
Status Report C.
Final Summary Report Commitment:
December 1983 Canmitment:
September 1984 Target:
December 1985 III.
e u a e
en n
A.
Status Report on how we
&tend'to'eet Regulatory Guide 1.97 requirements B.
Complete implementation phase of, Regulatory Guide 1.97 work (MIDAS),
Commitment:
February 1985 I
11
.Target:
November 1985 IV.
e en A.
Status Report B.
Procedures Generation Package C.
Prooedures Generation Package D.
Validation
& Verifioation E.
EOP's Complete and Implemented Commitment:
January 1984 Target:
July 'l984 Canmitment:
September 1984 Target:
September 1984 Target:
Training started Ootober 1984 Training finished October 1985 F.
EOP's Complete and Implemented Canmitment:
December 1985
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UNITED S'l ATES NUCLEAR REGULATORY COMMISSION REGION III 799 ROOSEVELT ROAD GL EN ELLYN, ILLINOIS 60I37 Docket No. 50-315 Docket No. 50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company C/o American Electric Power Service Corp.
1 Riverside Plaza
- Columbus, OH 43216 fD15 SF~
Dear Mr. Dolan:
The NRC is in the process of conducting safeguards regulatory effectiveness reviews at certain nuclear power reactors.
I wish to inform you that the D. C.
Cook facility has been chosen-for such a review tentatively scheduled for the week of August 13-17, 1984.
An NRC Region III representative will contact Mr. Miliotiof your staff to ascertain anticipated plant availability and to provide more detailed information concerning team composition.
The prime purpose of the review program is to evaluate the overall effective-ness of the D. C. Cook safeguards program and to determine whether existing safeguards regulations yield the level of protection intended by NRC.
The team performing the review supports NRC's quality assurance program for safeguards, both as it applies to the D. C. Cook security system and to NRC's regulations.
The review will complement but will be independent of the licensing and inspection functions.
The review at D. C. Cook will be conducted by a team with representatives from the Division of Safeguards, Region III, and U. S.
Army Special Forces personnel from Fort Bragg, NC.
The review team will be comprised of two groups.
One group will look at the facility's safeguards from the perspective of an insider, while the other will look at it through the eyes of an external adversary group.
The overall plan of action will be initiated by an entrance briefing.
You may wish to have a representative of your corporate staff present during this br'iefing as it will provide, in a capsulized form, an overview of the team's objectives and anticipated activities for the entire period of the visit.
Any questions that may arise concerning the team's review technique or other matters will be addressed at that time.
Por the remainder of the first day, the team would like to have a plant orientation tour, with emphasis on safeguards areas and systems and begin our examination of plant vital areas.
The second through fourth days will be dedicated to completing the review of vital areas and components, and reviewing the security force, access control
- system, and physical security systems.
The, last (fifth day) is reserved for any activities the team has been unable to accomplish earlier in the week and for a briefing of plant and corporate personnel on the preliminary results of the review.
Mr. John Dolan FEB >
O m Please provide appropriate plant personnel support for the team during the scheduled review.
Those chosen for this purpose should include a reactor
- operator, an instrument technician, an electrician, and a security officer.
The team will make every effort to schedule its activities so as to minimize disruption of normal plant operations.
The time that various team members will spend on site will vary, but generally will range from four to seven hours per day.
If you have any questions regarding the conduct of these regulatory effective-ness reviews, which you wish to have answered prior to the team's visit, please contact Liz Ten Eyck, SGPR, at (301) 427-4191 or James R. Creed, (312) 790-5643, of the Region staff.
Sincerely, J.
A.
ind, Director Division of Radiological and Materials Safety Programs cc: