ML17334A747

From kanterella
Jump to navigation Jump to search
Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change
ML17334A747
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/10/1998
From: Sampson J
INDIANA MICHIGAN POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1232F, NUDOCS 9806180126
Download: ML17334A747 (7)


Text

CATEGORY 1 ~

REGULAT~ INFORMATION DISTRIBUTIOP%YSTEM (RIDS)

ACCESSION NBR:9806180126 DOC.DATE: 98/06/10 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315

,, 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTh.,NAME AUTHOR AFFILIATION SAMPSON,J.R.

Indiana Michigan Power Co.

RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to licenses DPR-54

&, DPR-78,changing implementation date to reduce boric acid concentration in boric acid storage sys.Attachment 1 to ltr contains description of proposed change,& justification for change.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

General Distribution NOTES:

E RECIPIENT ID CODE/NAME PD3-3 LA STANG, J COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1

1 PD3-3 PD 1

1 COPIES LTTR ENCL 1

1 INTERN

~CENTER~

NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC 1

1 1

1 1

1 1

1 1

1 NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR 1

1 1

1 1

1 1

0 D

E N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 13 ENCL 12

American Electric P~r Nuclear Generation~

500 Circle Orive Buchanan, Ml 491071373 June 10, 1998 Docket Nos.:

50-315 50-316 AEP: NRC: 1232F U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop 0-P1-17 Washington, D.C. 20555-0001 Gentlemen:

Donald C.

Cook Nuclear Plant Units 1 and 2

LICENSE AMENDMENT CHANGE REQUEST:

BORIC ACID STORAGE SYSTEM BORON CONCENTRATION REDUCTION This letter and its attachments constitute an application for amendment to the Cook Nuclear Plant unit 1 and 2 facility operating licenses.

This amendment change request supercedes our previous request regarding this topic, which was provided in our letter AEP:NRC:1232E, dated April 28, 1998.

Per discussion with the NRC staff, this request is now being submitted in the form of a license amendment.

Additionally, we have modified the implementation date requested in our April 28, 1998, letter, from December 31, 1999, to December 31, 2000.

This change is necessary due to increased activities associated with our present extended outage.

The proposed'hange will change the implementation date to reduce the boric acid concentration in the boric acid storage system.

Attachment 1 to this letter contains a description of the proposed

change, justification for the
change, and analysis concerning significant hazards consideration pursuant to 10 CFR 50.92.

Attachment 2 contains the existing license amendment pages marked to reflect proposed changes.

Because of outage related activities, the required system modifications will not be completed by August 31, 1998.

Therefore, it will not be possible to implement the T/S amendments by that date.

We request that the implementation date be extended to December 31, 2000.

Because of the proximity of the present implementation date, we ask that this license amendment receive an expedited review.

This proposed change to the facility operating license for each unit has been reviewed and approved by the plant nuclear safety review committee and will be reviewed by the nuclear safety and design review committee at the next regularly scheduled meeting.

'.P806f80f26 9806f0 PDR ADOCK 050008f5 P

PDR

U.S. Nuclear Regulatory Commission Page 2

AEP: NRC: 1232F In compliance with the requirements of 10 CFR 50.91(b) (1), copies of this letter and its attachments have been transmitted to the Michigan Public Service commission and the Michigan Department of Public Health.

Sincerely, J.

R.

Sampso Vice President SHORN TO AND SUBSCRIBED BEFORE ME

.THIS f8 DAY OF 1998 Notary Pub zc My Commission Expires

/++a/

/vlb Attachment JANICE hl. BICKERS No~ Pub to, Benien County, Mi MyCommission Ex~es Feb. t8, 200t J.

A. Abramson MDEQ -

DW & RPD NRC Resident Inspector C. J. Papereillo

ATTACHMENT 1 TO AEP:NRC:1232F DESCRIPTION OF PROPOSED LICENSE AMENDMENT CHANGE AND 10 CFR 50.92 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS

Attachment 1 to AEP:NRC:1232F Page 1

DESCRIPTZON OF CHANGE ZN LICENSE AMENDMENTS BOTH UNITS This license amendment is effective as of the date of issuance, with full implementation when the required plant modifications are completed, but no later than December 31, 2000.

REASON FOR CHANGE Because of outage related activities, the required system modifications willnot be completed by August 31, 1998.

Therefore, it will not be possible to implement the technical specification (T/S) amendments by that date.

JUSTIFICATION FOR CHANGE The approved amendment request allows a reduction in required boric acid concentration, which, in effect, constitutes a relaxation of requirements.

During the period of the implementation, the existing approved T/Ss will be maintained.

10 CFR 50.92 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not:

~

involve a

significant increase in the probablity or consequences of an accident previously evaluated; create the possibility of a new or different kind of accident from any accident previously evaluted; or

~

involve a signific'ant reduction in a margin of safety.

CRITERION 1 Does the change involve a significant increase in the probability or consequences of an accident previously evaluated'P No.

Because the existing, approved T/Ss will be maintained, there is no resultant significant increase in the probability or consequences of an accident previously evaluated.

CRITERION 2 Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

No.

Because the existing, approved T/Ss, will be maintained, the possibility of a

new or different kind of accident from any accident previously evaluated is not created.

CRITERION 3 Does the change involve a significant reduction in a margin of safety'o.

The margin of safety requirements are not affected by maintaining the existing, approved T/Ss.

Attachment 1 to AEP:NRC:1232F Page 2

CONCLUSION It is concluded that operation of Cook Nuclear Plant units 1 and 2

with an implementation date of December 31,

2000, to reduce the boric acid concentration in the boric acid storage system,'s described
herein, does not involve any significant hazards consideration as defined in 10 CFR 50.92.

ATTACHMENT 2 TO AEP:NRC:1232F EXISTING LICENSE AMENDMENT PAGES MARKED TO REFLECT PROPOSED CHANGES