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{{#Wiki_filter:PRIORITY (ACCELERATED RZDS PROCESSING)
{{#Wiki_filter:PRIORITY (ACCELERATED RZDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9507070175 DOC.DATE: 95/06/30 NOTARIZED:
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
YES DOCKET N FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 P 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
ACCESSION NBR:9507070175           DOC.DATE:   95/06/30   NOTARIZED: YES                             DOCKET N FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315                                     P 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME           AUTHOR AFFILIATION FITZPATRICK,E.       Indiana Michigan Power Co. (formerly Indiana & Michigan Ele                               R RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Application for amends to Licenses DPR-58&DPR-74,changing'S Section 5.3.1 to allow fuel reconstitution,per GL 90-02, 0 Suppl 1.DISTRIBUTION CODE: A014D COPIES RECEIVED:LTR ENCL SIZE: R TITLE: Generic Ltr 90-02 re Line-Item Tech Spec Improvement
Application for amends to Licenses DPR-58 &
-Alternative Re I NOTES: RECIPIENT ID CODE/NAME PD3-1 PD HICKMAN J INTERNAL NSEtR e./DSSA/SRXB RES/DS IR/EI B EXTERNAL NOAC COPXES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD11-3 NRR/DSSA'GC/HDS2 NRC PDR COPXES LTTR ENCL 1 1 1 1 1 0 1 1 D 0 N NOTE TO ALL s'RZDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD8 (415-2083)
Section 5.3.1 to allow fuel reconstitution,per DPR-74,changing'S GL 90-02,         0 Suppl 1.
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF.COPIES REQUIRED: LTTR 10 ENCL 9 indiana Michigan Power Company P.O.Box 16631, Columbus, OH 43216 1 June 30, 1995 AEP'NRC'1124C Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
DISTRIBUTION CODE: A014D         COPIES RECEIVED:LTR                 ENCL                   SIZE:               R TITLE: Generic     Ltr   90-02 re Line-Item Tech Spec Improvement Alternative Re NOTES:
Donald C.Cook Nuclear Plant Units 1 and 2 PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO ALLOW FUEL RECONSTITUTION (GENERIC LETTER 90-02 SUPPLEMENT 1)REQUEST FOR ADDITIONAL INFORMATION This letter is in response to the changes to submittal AEP:NRC:1124B discussed on June 20, 1995.As agreed upon, the following statement has been incorporated into the wording for the proposed change to technical specification (T/S)Section 5.3.1."Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases.A limited number of lead test assembli'es that have not completed representative testing may be placed in non-limiting core regions." The attachment contains the revised page for each unit.These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed at the next regular meeting of the Nuclear Safety and Design Review Committee.
I RECIPIENT            COPXES            RECIPIENT                             COPXES ID  CODE/NAME          LTTR ENCL        ID CODE/NAME                           LTTR ENCL PD3-1 PD                   1    1      PD11-3                                      1    1 HICKMAN   J               1    1 INTERNAL             NSEtR   e.       1    1      NRR/DSSA                                    1    1
C:~OO79 9507070175
              /DSSA/SRXB             1    1                'GC/HDS2 1    0 RES/DS   IR/EIB            1    1 EXTERNAL   NOAC                       1     1     NRC PDR                                     1   1 D
'750630 PDR ADOCK 05000315 PDR pl C'a U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:1124C 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, 8F E.E.Fitz rick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~i 4 DAY OF i~r a 1995 No ary Public My Commission Expires: C~-2-d'-5'$'h Attachment CC: A.A.Blind G.Charnoff J.B.Martin NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett I''I r ATTACHMENT TO AEP:NRC: 1124C PROPOSED REVISED TECHNICAL SPECIFICATION PAGES}}
0 N
NOTE TO ALL s'RZDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF. COPIES REQUIRED: LTTR             10   ENCL           9
 
indiana Michigan Power Company P.O. Box 16631, Columbus, OH 43216 1
June 30, 1995                                                   AEP'NRC'1124C Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and       2 PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO ALLOW FUEL RECONSTITUTION (GENERIC LETTER 90-02 SUPPLEMENT 1)
REQUEST FOR ADDITIONAL INFORMATION This     letter is in           response   to the changes to submittal AEP:NRC:1124B discussed           on June 20, 1995.     As agreed upon, the following       statement has been incorporated     into the wording for the proposed change to technical           specification (T/S) Section 5.3.1.
    "Fuel assemblies shall be limited to those fuel designs that have been analyzed         with applicable NRC staff-approved codes and methods, and shown by           tests or analyses to comply with all fuel safety design bases. A limited number of lead test assembli'es that have not completed representative testing may be placed in non-limiting core regions."
The   attachment contains the revised page         for each unit.
These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed at the next regular meeting of the Nuclear Safety and Design Review Committee.
C:~OO79 9507070175 '750630 PDR       ADOCK 05000315 PDR                                                 pl
 
C' a
 
U. S. Nuclear   Regulatory Commission             AEP:NRC:1124C Page 2 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, 8F E. E. Fitz     rick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~i 4   DAY OF     i~r a   1995 No ary Public My Commission   Expires: C~ d'- 5'$'h Attachment CC:   A. A. Blind G. Charnoff J. B. Martin NFEM Section   Chief NRC Resident   Inspector - Bridgman J. R. Padgett
 
I'
'I r
 
ATTACHMENT TO AEP:NRC: 1124C PROPOSED REVISED TECHNICAL SPECIFICATION PAGES}}

Revision as of 13:35, 22 October 2019

Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1
ML17332A827
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/30/1995
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A828 List:
References
AEP:NRC:1124C, GL-90-02, GL-90-2, NUDOCS 9507070175
Download: ML17332A827 (6)
v • d • e


Text

PRIORITY (ACCELERATED RZDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9507070175 DOC.DATE: 95/06/30 NOTARIZED: YES DOCKET N FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 P 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to Licenses DPR-58 &

Section 5.3.1 to allow fuel reconstitution,per DPR-74,changing'S GL 90-02, 0 Suppl 1.

DISTRIBUTION CODE: A014D COPIES RECEIVED:LTR ENCL SIZE: R TITLE: Generic Ltr 90-02 re Line-Item Tech Spec Improvement Alternative Re NOTES:

I RECIPIENT COPXES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 PD11-3 1 1 HICKMAN J 1 1 INTERNAL NSEtR e. 1 1 NRR/DSSA 1 1

/DSSA/SRXB 1 1 'GC/HDS2 1 0 RES/DS IR/EIB 1 1 EXTERNAL NOAC 1 1 NRC PDR 1 1 D

0 N

NOTE TO ALL s'RZDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF. COPIES REQUIRED: LTTR 10 ENCL 9

indiana Michigan Power Company P.O. Box 16631, Columbus, OH 43216 1

June 30, 1995 AEP'NRC'1124C Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO ALLOW FUEL RECONSTITUTION (GENERIC LETTER 90-02 SUPPLEMENT 1)

REQUEST FOR ADDITIONAL INFORMATION This letter is in response to the changes to submittal AEP:NRC:1124B discussed on June 20, 1995. As agreed upon, the following statement has been incorporated into the wording for the proposed change to technical specification (T/S) Section 5.3.1.

"Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assembli'es that have not completed representative testing may be placed in non-limiting core regions."

The attachment contains the revised page for each unit.

These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed at the next regular meeting of the Nuclear Safety and Design Review Committee.

C:~OO79 9507070175 '750630 PDR ADOCK 05000315 PDR pl

C' a

U. S. Nuclear Regulatory Commission AEP:NRC:1124C Page 2 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, 8F E. E. Fitz rick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~i 4 DAY OF i~r a 1995 No ary Public My Commission Expires: C~ d'- 5'$'h Attachment CC: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett

I'

'I r

ATTACHMENT TO AEP:NRC: 1124C PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

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