ML17329A465
| ML17329A465 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/21/1992 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17329A466 | List: |
| References | |
| AEP:NRC-1166B, NUDOCS 9204270241 | |
| Download: ML17329A465 (5) | |
Text
ACCELERATED DIS UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9204270241 DOC.DATE: 92/04/21 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Suppls 920327 application for amend to License DPR-58, changing TS to allow interim plugging criteria of 1.0 volt, per NRC 920409 verbal direction.Addi tubes will be pulled during Summer 1992 refueling outage.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:
D RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTS B1 1 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LFHB--
REG~Fl-EE'l
~~~ms~
EXTERNAL:
RC PDR COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 1
1 1
0 1
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
0 1
1 1
1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE iVASfE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL 16
0 lr
~
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 R
AEP: NRC: 1166B Donald C.
Cook Nuclear Plant Unit 1 Docket No. 50-315 License No.
DPR-58 SUPPLEMENT TO TECHNICAL SPECIFICATIONS CHANGE TO ALLOW INTERIM PLUGGING CRITERIA OP 1.0 VOLT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Attn:
T. E. Murley April 21, 1992
Dear Dr. Murley:
References:
1)
- Letter, AEP:NRC:1166, E.
E. Fitzpatrick (I&M) to T. E. Murley (NRC), dated March 20, 1992 2)
- Letter, AEP:NRC:1166A, E. E. Fitzpatrick (I&M) to T. E. Murley (NRC), dated March 27, 1992 Based on verbal direction received from the Cook Nuclear Plant NRR Pro]ect Manager, Mr. John Stang, on April 9, 1992, this letter is written to supplement our submittal AEP;NRC:1166A dated March 27, 1992.
The NRC review staff's schedule cannot accommodate our requested approval date of June 23, 1992, which is necessary to allow use of the interim criteria during the 1992 Unit 1 refueling outage.
Therefore, we accept the necessity to revise the 1.75 volt criteria requested in our AEP:NRC:1166A submittal to 1.0 volt. This 1.0 volt criteria is fully supported in both of our previous submittals on steam generator tube plugging criteria (References 1
and 2).
We are also proposing to amend T/S 4.4.5.4.a.10 to add a provision for performing a rotating pancake probe inspection.
Crack indications with bobbin coil signal amplitudes greater than 1.0 volt but less than or equal to 4.0 volts may remain in service if rotating pancake probe inspection does not detect degradation.
The no significant hazards considerations determination for the proposed changes contained in this submittal remains the same as indicated in our previous submittals, as do the Westinghouse Electric Company supporting documents that were attached to those
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Dr..T. E. Murley AEP: NRC: 1166B submittals.
For your convenience, a complete copy of the technical specifications pages associated with interim plugging.criteria is attached.
We remain committed to pull additional tubes during the summer 1992 refueling outage as stated in Reference l.
Examination of these tubes willnot be complete prior to returning Unit 1 to operation.
It is our understanding that, revising the interim plugging criteria to 1.0 volt will allow the NRC greater opportunity to review the alternate plugging criteria submitted in Reference (1).
Since the interim plugging criteria will be approved for only one refueling cycle, resolution of the alternate plugging criteria is needed prior to the start of the next refueling outage (beginning approximately January 1994).
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee.
In compliance with the requirements of 10CFR50.91(b)(1),
copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the NFEM Section Chief.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, ee'.
E. Fitzp rick Vice President dag Attachment cc:
D. H. Williams, Jr.
A. A. Blind - Bridgman J.
R. Padgett G, Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman NFEM Section Chief