ML17331A915: Difference between revisions

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{{#Wiki_filter:..zeezx.zmx~DOCmmm DrSr m"j.OX SvSrzrvr REGULAT INFORMATION DISTRIBUTION STEM (RIDS)ACCESS/ON, NBR:9308020133 DOC.DATE: 93/07/27 NOTARIZED:
{{#Wiki_filter:.. zeezx.zmx ~ DOCmmm DrSr                                       m"j.OX SvSrzrvr REGULAT         INFORMATION DISTRIBUTION         STEM (RIDS)
NO DOCKET FACIE: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.
ACCESS/ON, NBR:9308020133             DOC.DATE:   93/07/27   NOTARIZED: NO         DOCKET FACIE: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 & Michigan Ele RECIP.NAME           RECIPIENT AFFILIATION MURLEY,T.E.             Document Control Branch (Document Control Desk)
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Informs that util intends to invoke ASME Code Case N0481 for exam of primary loop pump casings at plant,per conditions of NRC 930413 ltr to LA=Walsh (WOG).Rev 3 of"Pump Inservice Test Program" encl.DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Informs that util intends to invoke ASME Code Case N0481 for exam   of primary loop pump casings at plant,per conditions of NRC Test 930413   ltr Program" encl.
Inservice/Testing/Relief from ASME Code NOTES: RECIP1ENT ID CODE/NAME PD3-1 LA DEAN,W INTERNAL: AEOD/DSP/ROAB NRR/EMCB OC LFDCB RE FIL Ol EXTERNAL: EG&G BROWN,B NRC PDR COPIES LTTR ENCL 1 0 2 2 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMEB NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EG&G RANSOMEgC NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 0 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
to LA= Walsh     (WOG).Rev 3 of "Pump   Inservice DISTRIBUTION CODE: A047D           COPIES RECEIVED:LTR         ENCL       SIZE:
PLEASE HELP US TO REDUCE WASTE!CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13 Indiana Michigan'ower Company P.O.Box 16631 Coiumbus, OH 43216 5 AEP:NRC:0969W Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 IST PROGRAM-USE OF ASME CODE CASE N-481 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: Dr.T.E.Murley July 27, 1993
TITLE: OR Submittal: Inservice/Testing/Relief from               ASME Code NOTES:
RECIP1ENT               COPIES            RECIPIENT          COPIES ID CODE/NAME             LTTR ENCL        ID CODE/NAME        LTTR ENCL PD3-1 LA                     1      0      PD3-1 PD                1    1 DEAN,W                       2      2                                              D INTERNAL: AEOD/DSP/ROAB                 1     1     NRR/DE/EMEB             1    1 NRR/EMCB                      1      1      NUDOCS-ABSTRACT         1    1 OC LFDCB                      1      0      OGC/HDS2               1    0 RE    FIL        Ol        1      1      RES/DSIR/EIB           1    1 EXTERNAL: EG&G BROWN,B                  1     1     EG&G RANSOMEgC          1     1 NRC PDR                      1     1     NSIC                    1     1 D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR                 16   ENCL   13


==Dear Dr.Murley:==
Indiana Michigan
References 1.Letter, J.E.Richardson (NRC)to L.A.Walsh (WOG), ASME Code Case N-481, dated April 13, 1993'.WCAP-13045,"Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems," dated September 1991.3.WCAP-13128,"A Demonstration of Compliance of the Primary Loop Pump Casings of the D.C.Cook Units 1 and 2 to ASME Code Case N-481," dated March 1992.4.Regulatory Guide 1.147,"Inservice Inspection Code Case Acceptability, ASME Section XI Division 1," dated April 1992.The purposes of this letter are to inform you that the Indiana Michigan Power Company intends to invoke ASME Code Case N-481 for the examination of the primary loop pump casings at Cook Nuclear Plant pursuant to the conditions of Reference 1, and to transmit Revision 3 of the Pump Inservice Test Program.p ,~9308050i33 935727 PDR'DOCK 05000315 P PDR Dr.T.E.Murley-2-AEP:NRC:0969W The examination of pump casings may take place as early as 1994 during scheduled refueling outages.The analyses required by the code case are contained in References 2 and 3 which will be available at Cook Nuclear Plant.The analyses demonstrate the safety and serviceability of the pump casing by satisfying code case items 1 through 7.The attachment to this letter contains the Pump Inservice Test (IST)program, Revision No.3.The pump IST is being revised to incorporate the use of ASME/ANSI Standard OM-1987 Part 6,"Operation and Maintenance of Nuclear Power Plants," for the Emergency Diesel Generator (EDG)fuel oil transfer pumps.The subject ANSI standard has been accepted by the NRC as an acceptable alternative to Subsection IWP of ASME Code Section XI (Reference 4).Sincerely, E.E.Fitz atrick Vice President dv Attachment cc: A.A.Blind-Bridgman J.R.Padgett G.Charnoff NFEM Section Chief J.B.Martin-Region III NRC Resident Inspector-Bridgman Attachment to AEP:NRC:0969W Pump Inservice Test Program, Revision 3}}
        'ower Company P.O. Box 16631 Coiumbus, OH 43216 5
AEP:NRC:0969W Donald C. Cook Nuclear Plant Units 1 and      2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 IST PROGRAM-USE OF ASME CODE CASE N-481 U. S. Nuclear Regulatory Commission Document      Control Desk Washington, D.C. 20555 Attn: Dr. T.      E. Murley July 27, 1993
 
==Dear Dr. Murley:==
 
References
: 1.     Letter, J. E. Richardson (NRC) to L. A. Walsh (WOG), ASME Code Case N-481, dated April 13, 1993
                                                              '.
WCAP-13045, "Compliance   to ASME Code   Case N-481 of the Primary Loop Pump Casings of Westinghouse   Type Nuclear Steam Supply Systems," dated September 1991.
: 3.     WCAP-13128, "A Demonstration of Compliance of the Primary Loop Pump Casings of the D. C. Cook Units 1 and 2 to ASME Code Case N-481," dated March 1992.
: 4.       Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability,     ASME Section XI Division 1," dated April 1992.
The purposes of this letter are to inform you that the Indiana Michigan Power Company intends to invoke ASME Code Case N-481 for the examination of the primary loop pump casings at Cook Nuclear Plant pursuant to the conditions of Reference 1, and to transmit Revision 3 of the Pump Inservice Test Program.
p
,~9308050i33 935727 PDR'DOCK 05000315 P                       PDR
 
Dr. T. E. Murley                                 AEP:NRC:0969W The examination   of pump casings may take place as early as 1994 during scheduled refueling outages. The analyses required by the code case are contained in References 2 and 3 which will be available at Cook Nuclear Plant. The analyses demonstrate the safety and serviceability of the pump casing by satisfying code case items   1 through 7.
The attachment   to this letter contains the Pump Inservice Test (IST) program, Revision No. 3. The pump IST is being revised to incorporate the use of ASME/ANSI Standard OM-1987 Part 6, "Operation and Maintenance of Nuclear Power Plants," for the Emergency Diesel Generator (EDG) fuel oil transfer pumps.       The subject ANSI standard has been accepted by the NRC as an acceptable alternative to Subsection IWP of ASME Code Section XI (Reference 4).
Sincerely, E. E. Fitz atrick Vice President dv Attachment cc:   A. A. Blind - Bridgman J. R. Padgett G. Charnoff NFEM Section Chief J. B. Martin - Region III NRC Resident Inspector - Bridgman
 
Attachment to AEP:NRC:0969W Pump Inservice Test Program, Revision 3}}

Revision as of 13:22, 22 October 2019

Informs That Util Intends to Invoke ASME Code Case N-481 for Exam of Primary Loop Pump Casings at Plant,Per Conditions of NRC 930413 Ltr to La Walsh (Wog).Rev 3 of Pump Inservice Test Program Encl
ML17331A915
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/27/1993
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17331A916 List:
References
AEP:NRC:0969W, AEP:NRC:969W, NUDOCS 9308020133
Download: ML17331A915 (4)
v • d • e


Text

.. zeezx.zmx ~ DOCmmm DrSr m"j.OX SvSrzrvr REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESS/ON, NBR:9308020133 DOC.DATE: 93/07/27 NOTARIZED: NO DOCKET FACIE: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 & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Informs that util intends to invoke ASME Code Case N0481 for exam of primary loop pump casings at plant,per conditions of NRC Test 930413 ltr Program" encl.

to LA= Walsh (WOG).Rev 3 of "Pump Inservice DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code NOTES:

RECIP1ENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 1 1 DEAN,W 2 2 D INTERNAL: AEOD/DSP/ROAB 1 1 NRR/DE/EMEB 1 1 NRR/EMCB 1 1 NUDOCS-ABSTRACT 1 1 OC LFDCB 1 0 OGC/HDS2 1 0 RE FIL Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EG&G BROWN,B 1 1 EG&G RANSOMEgC 1 1 NRC PDR 1 1 NSIC 1 1 D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13

Indiana Michigan

'ower Company P.O. Box 16631 Coiumbus, OH 43216 5

AEP:NRC:0969W Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 IST PROGRAM-USE OF ASME CODE CASE N-481 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: Dr. T. E. Murley July 27, 1993

Dear Dr. Murley:

References

1. Letter, J. E. Richardson (NRC) to L. A. Walsh (WOG), ASME Code Case N-481, dated April 13, 1993

'.

WCAP-13045, "Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems," dated September 1991.

3. WCAP-13128, "A Demonstration of Compliance of the Primary Loop Pump Casings of the D. C. Cook Units 1 and 2 to ASME Code Case N-481," dated March 1992.
4. Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI Division 1," dated April 1992.

The purposes of this letter are to inform you that the Indiana Michigan Power Company intends to invoke ASME Code Case N-481 for the examination of the primary loop pump casings at Cook Nuclear Plant pursuant to the conditions of Reference 1, and to transmit Revision 3 of the Pump Inservice Test Program.

p

,~9308050i33 935727 PDR'DOCK 05000315 P PDR

Dr. T. E. Murley AEP:NRC:0969W The examination of pump casings may take place as early as 1994 during scheduled refueling outages. The analyses required by the code case are contained in References 2 and 3 which will be available at Cook Nuclear Plant. The analyses demonstrate the safety and serviceability of the pump casing by satisfying code case items 1 through 7.

The attachment to this letter contains the Pump Inservice Test (IST) program, Revision No. 3. The pump IST is being revised to incorporate the use of ASME/ANSI Standard OM-1987 Part 6, "Operation and Maintenance of Nuclear Power Plants," for the Emergency Diesel Generator (EDG) fuel oil transfer pumps. The subject ANSI standard has been accepted by the NRC as an acceptable alternative to Subsection IWP of ASME Code Section XI (Reference 4).

Sincerely, E. E. Fitz atrick Vice President dv Attachment cc: A. A. Blind - Bridgman J. R. Padgett G. Charnoff NFEM Section Chief J. B. Martin - Region III NRC Resident Inspector - Bridgman

Attachment to AEP:NRC:0969W Pump Inservice Test Program, Revision 3

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