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{{#Wiki_filter:P.RIQRITY 1 (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000315 05000316 P  
{{#Wiki_filter:P.RIQRITY (ACCELERATED RIDS PROCESSING 1
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9503080168                  DOC.DATE: 95/02/28          NOTARIZED: YES        DOCKET 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 FITZPATRICK,E.          Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele                  P RECIP.NAME              RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards proposed TS,revising train A/B battery profiles 6 modifying train N batteries profile request for mod.DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR J ENCL l SIZE: k~TITLE: OR Submittal:
Forwards proposed TS,revising train A/B battery profiles 6 modifying train N batteries profile request for mod.
General Distribution ACCESSION NBR:9503080168 DOC.DATE: 95/02/28 NOTARIZED:
DISTRIBUTION CODE: A001D TITLE:  OR COPIES RECEIVED: LTR Submittal: General Distribution J   ENCL l   SIZE:   k~
YES FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
NOTES                                                                                                R RECIPIENT                  COPIES                RECIPIENT          COPIES ID  CODE/NAME               LTTR ENCL          ID CODE/NAME       LTTR ENCL PD3-1 LA                         1      1        PD3-1 PD              1      1 HICKMAN,J                         1      1 INTERNAL:   IL'E 'CENTER       01           1      1        NRR/DRCH/HICB          1      1
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)NOTES RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: IL'E'CENTER 01~NRR/DSSA~SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1.0 1 1 R D 0 C U N NOTE TO ALL"RIDS" RECIPIENTS:
      ~NRR/DSSA~SPLB                       1     1       NRR/DSSA/SRXB         1     1 NUDOCS-ABSTRACT                  1     1       OGC/HDS2              1   . 0 EXTERNAL: NOAC                              1     1       NRC PDR                1     1 D
PLEASE HELP US TO REDUCE KVASTE!CONTACI THE DOCUiIENTCO4"I ROL DESK, ROOI1I PI-37 (EXT.504-2083)TO EL!ihIINATE YOUR NAi!E FROM DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON"I'EED!
0 C
TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10 I
U N
t/.~I'e~\'indiana Michigan'ower Company P.O.Box 16631 Columbus, OH 43216 February 28, 1995 ENtMANA NSCHESJEN PQ5ÃM AEP'NRC'0896U Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
NOTE TO ALL"RIDS" RECIPIENTS:
Donald C.Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGE REQUEST;REVISE THE TRAIN A/B BATTERY PROFILES AND MODIFY TRAIN N BATTERIES'ROFILE REQUEST FOR MODIFICATION
PLEASE HELP US TO REDUCE KVASTE! CONTACI THE DOCUiIENTCO4"I ROL DESK, ROOI1I PI-37 (EXT. 504-2083 ) TO EL!ihIINATE YOUR NAi!E FROM DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON"I'EED!
\The purpose of this letter is to modify our AEP:NRC:0896S letter, same subject, dated July 19, 1994, as requested by the NRR staff.In a January 13, 1995, telephone conference the NRR reviewing.
TOTAL NUMBER OF COPIES REQUIRED: LTTR                       11   ENCL     10
engineer requested that we adopt the language of the latest revision to IEEE Standard 450 with regard to the modified performance test and degraded performance test recommendations.
 
To satisfy his request, paragraph"e" on pages 3/4 8-14 and 3/4 8-18 for the Donald C.Cook Nuclear Plant Units 1 and 2 technical specifications respectively should read as follows."At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying.that the battery capacity is at least 80%of the manufacturer's rating.When this test is performed in place of a battery service test, a modified performance test shall be conducted.
I indiana Michigan t            'ower Company
Annual performance tests of battery capacity shall be given to any battery that showssigns of degradation or has reached 85%of the service life expected for the application.
/. \
Degradation is indicated when the battery capacity drops more than 10%from its capacity on the previous performance test, or is-below 90%of the manufacturer's rating.If the battery has reached 85%of service life, deliversa capacity of 100%or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation." 070OSS.9503080168 950228 PDR ADOCK 05000315 P PDR  
  ~
.~0 U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:0896U The battery surveillance requirements have been modified to reflect the comments as requested.
      ~ I'e
For your convenience, a copy of the existing T/Ss, marked to reflect all the changes, is included as Attachment 1~Attachment 2 is a typed copy of the T/Ss, as they should appear, with bar margins indicating the changes.Please note the new format we are implementing to allow electronic access to the T/Ss.With the new format there are pagination changes and minor administrative changes to Table 4.8-2 in both units in an ongoing effort to achieve uniformity between the units.We have reviewed the staff's requested changes and believe the significant hazards consideration performed pursuant to 10 CFR 50.92 for the original submittal is valid.Therefore, we have not provided further justification for the changes requested by the NRR staff.We believe the proposed additional changes will not result in (1)a significant change in the types of effluent or a significant increase in the amount of any effluent that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be approved by the Nuclear Safety and Design Review Committee at the next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.Sincerely, E'g pW E.E.Fit patrick Vice President eh SWORN TO AND SUBSCRIBED BEFORE ME THIS~P DAY OF~~c 1995 Attachment cc: A.A.Blind G.Charnoff J.B.Martin NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett No ry Public 0/ŽJ}}
          '
P.O. Box 16631 Columbus, OH 43216 ENtMANA NSCHESJEN PQ5ÃM February 28, 1995                                          AEP'NRC'0896U 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 TECHNICAL SPECIFICATION CHANGE REQUEST; REVISE THE TRAIN A/B BATTERY PROFILES AND MODIFY TRAIN N BATTERIES'ROFILE REQUEST FOR MODIFICATION
                                                                                  \
The purpose         of this letter is to modify our AEP:NRC:0896S letter, same     subject, dated July 19, 1994, as requested by the NRR staff.
In   a   January 13, 1995, telephone conference the NRR reviewing.
engineer         requested   that we adopt the language of the latest revision to           IEEE Standard 450 with regard to the modified performance test and degraded performance test recommendations. To satisfy his request, paragraph "e" on pages 3/4 8-14 and 3/4 8-18 for the Donald C. Cook Nuclear Plant Units 1 and 2 technical specifications respectively should read as follows.
                              "At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying
                              .that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.
Annual performance tests of battery capacity shall be given to any battery that showssigns of degradation or has reached 85% of the service         life expected for the application.
Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is-below 90% of the manufacturer's rating. If the battery has reached 85% of service life, deliversa capacity of 100%
or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation."
070OSS.
9503080168 950228 PDR   ADOCK 05000315 P                     PDR
 
. ~ 0 U. S. Nuclear     Regulatory Commission                     AEP:NRC:0896U Page 2 The   battery surveillance requirements have been modified to reflect the comments as requested.         For your convenience, a copy of the existing T/Ss, marked to reflect all the changes, is included as     ~ Attachment 2 is a typed copy of the T/Ss, as they should appear, with bar margins indicating the changes.             Please note the new format we are implementing to allow electronic access to the T/Ss. With the new format there are pagination changes and minor administrative changes to Table 4.8-2 in both units in an ongoing effort to achieve uniformity between the units.
We   have reviewed the     staff's   requested changes and believe the significant hazards consideration performed pursuant to 10 CFR 50.92 for the original submittal is valid. Therefore, we have not provided further justification for the changes requested by the NRR staff.
We   believe the proposed additional changes       will not result in (1) a   significant change in the types of effluent or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be approved by the Nuclear Safety and Design Review Committee at the next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.
Sincerely, E'g         pW E. E. Fit patrick                   SWORN TO AND SUBSCRIBED BEFORE ME Vice President THIS ~P   DAY OF   ~~c       1995 eh Attachment                                     No  ry Public cc:     A. A. Blind G. Charnoff J. B. Martin NFEM Section   Chief NRC Resident   Inspector - Bridgman J. R. Padgett
 
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Revision as of 12:39, 22 October 2019

Forwards Proposed Ts,Revising Train A/B Battery Profiles & Modifying Train N Batteries Profile Request for Mod
ML17332A605
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/28/1995
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A606 List:
References
AEP:NRC:0896U, AEP:NRC:896U, NUDOCS 9503080168
Download: ML17332A605 (6)
v • d • e


Text

P.RIQRITY (ACCELERATED RIDS PROCESSING 1

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9503080168 DOC.DATE: 95/02/28 NOTARIZED: YES DOCKET 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 FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards proposed TS,revising train A/B battery profiles 6 modifying train N batteries profile request for mod.

DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED: LTR Submittal: General Distribution J ENCL l SIZE: k~

NOTES R RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: IL'E 'CENTER 01 1 1 NRR/DRCH/HICB 1 1

~NRR/DSSA~SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 . 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

0 C

U N

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE KVASTE! CONTACI THE DOCUiIENTCO4"I ROL DESK, ROOI1I PI-37 (EXT. 504-2083 ) TO EL!ihIINATE YOUR NAi!E FROM DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON"I'EED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10

I indiana Michigan t 'ower Company

/. \

~

~ I'e

'

P.O. Box 16631 Columbus, OH 43216 ENtMANA NSCHESJEN PQ5ÃM February 28, 1995 AEP'NRC'0896U 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 TECHNICAL SPECIFICATION CHANGE REQUEST; REVISE THE TRAIN A/B BATTERY PROFILES AND MODIFY TRAIN N BATTERIES'ROFILE REQUEST FOR MODIFICATION

\

The purpose of this letter is to modify our AEP:NRC:0896S letter, same subject, dated July 19, 1994, as requested by the NRR staff.

In a January 13, 1995, telephone conference the NRR reviewing.

engineer requested that we adopt the language of the latest revision to IEEE Standard 450 with regard to the modified performance test and degraded performance test recommendations. To satisfy his request, paragraph "e" on pages 3/4 8-14 and 3/4 8-18 for the Donald C. Cook Nuclear Plant Units 1 and 2 technical specifications respectively should read as follows.

"At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying

.that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that showssigns of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is-below 90% of the manufacturer's rating. If the battery has reached 85% of service life, deliversa capacity of 100%

or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation."

070OSS.

9503080168 950228 PDR ADOCK 05000315 P PDR

. ~ 0 U. S. Nuclear Regulatory Commission AEP:NRC:0896U Page 2 The battery surveillance requirements have been modified to reflect the comments as requested. For your convenience, a copy of the existing T/Ss, marked to reflect all the changes, is included as ~ Attachment 2 is a typed copy of the T/Ss, as they should appear, with bar margins indicating the changes. Please note the new format we are implementing to allow electronic access to the T/Ss. With the new format there are pagination changes and minor administrative changes to Table 4.8-2 in both units in an ongoing effort to achieve uniformity between the units.

We have reviewed the staff's requested changes and believe the significant hazards consideration performed pursuant to 10 CFR 50.92 for the original submittal is valid. Therefore, we have not provided further justification for the changes requested by the NRR staff.

We believe the proposed additional changes will not result in (1) a significant change in the types of effluent or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

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

In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.

Sincerely, E'g pW E. E. Fit patrick SWORN TO AND SUBSCRIBED BEFORE ME Vice President THIS ~P DAY OF ~~c 1995 eh Attachment No ry Public cc: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett

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