ML17333A569
| ML17333A569 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/19/1996 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1166AE, NUDOCS 9609250109 | |
| Download: ML17333A569 (3) | |
Text
CATEGORY j.
REGULAT TNFORMATTON DISTRTBUTZO&STEM (RZDS)
AC I p ACCESSION.hlBR:9609250109 DOC.DATE: 96/09/19 NOTARIZED: NO DOCKET g
FACI'i":54-33~ Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides clarification to several questions raised by staff re application for amend to TS for incorporating 2.0 volt SG tube support plate plugging criterion.
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Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 lNOlkiM NICHIGAN POWER September 19, 1996 Docket No.: 50-315 AEP: NRC: 1166AE U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C.
20555 Gentlemen:
Donald C.
Cook Nuclear Plant Unit 1 TECHNICAL SPECIFICATION CHANGES TO INCORPORATE 2.0 VOLT STEAM GENERATOR TUBE SUPPORT PLATE PLUGGING CRITERION REQUEST FOR ADDITIONAL INFORMATION This letter provides clarification to several questions raised by your staff regarding our application for amendment to the technical specifications (T/Ss) of Donald C.
Cook Nuclear Plant Unit 1 for incorporating the 2.0 volt steam generator tube support plate plugging criterion.
As discussed in our telephone conference call of September 6, 1996, we concur that the structural voltage limit should be 8.6 volts in lieu of the 8.8 volts referenced in our submittal AEP:NRC:1166AA.
When using the 8.6 volts as the structural voltage it now yields an end-of-,cycle safety ntargin of 5.4'volts and a maximum beginning-of-cycle '(BOC) voltage repair limit of 5.375 volts.
The method of dealing with probe wear was also discussed during the call.
An alternative method to the probe wear guidance contained in generic letter 95-05 will be used.
The alternative method will follow the NRC endorsed NEI plan as outlined in NEI letters dated January 23,
- 1996, and February 23, 1996.
On September 9,
- 1996, you requested our comments regarding three NRC perceptions.
Our comments 'follow directly after each NRC stated perception:
You will not be applying a fraction of bobbin cofl fndicatfons in the BOC voltage distribution resolved during the inspection process as NDD with RPC probe.
Is that a correct statementP The statement is correct.
You wfll use the probabflfstfc analytfcaI methods described fn WCAP-14277, not any deterministic methods also described fn the same
- report, for determining leak rate and tube burst probabilities.
Correct?
The statement is correct.
960925010'P 960919 PDR ADDCK 050003i5 25003$
P ool /g
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:1166AE The proposed TS 4.4.5.4.10.c is slightly different from GL 95-05
- model, "acceptabl e al terna tive inspection techniques" tha t are mentioned.
Is it correct'hat they will be qualifi'ed using similar criteri a as used for qualifying RPC probes?
The statement is correct.
Sincerely, E.
. Fitzpa rick Vice President CC:
A. A. Blind A. H. Beach NFEM Section Chief NRC Resident Inspector J.
R. Padgett