ML17331B273
| ML17331B273 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/24/1994 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1166M, NUDOCS 9403040278 | |
| Download: ML17331B273 (11) | |
Text
ACCELERATED DIS
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UTION DEMON ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9403040278 DOC.DATE: 94/02/24 NOTARIZED: YES DOCKET FACIL:50-315 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 MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Forwards addi info in support of 2.0 volt interim SG tube support plate plugging criteria for fuel cycle 14,per NRC 940223 telcon request re util 940215 proposed TS amend request.
DISTRIBUTION CODE:
A001D
.COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:
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RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTSB NRR/DRPW NRR/DSSA/SRXB
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! 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:
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~'ower Company P.O. Box 16631 Columbus, OH 43216 C
I'MINAMA SIICNE6'did NeOWM AEP: NRC: 1166M Donald C.
Cook Nuclear Plant Unit 1 Docket No. 50-515 License No.
DPR-58 ADDITIONALINFORMATION IN SUPPORT OF 2.0 VOLT INTERIM STEAM GENERATOR TUBE SUPPORT PLATE PLUGGING CRITERIA FOR FUEL CYCLE 14 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.
C.
20555 Attn:
T. E. Murley February 24, 1994
Dear Dr. Murley:
This letter is submitted pursuant to a request for additional information made by your staff during a teleconference held on February 23, 1994.
The request is related to our letter AEP:NRC:1166L, dated February 15,
- 1994, which proposed technical specification changes associated with a 2.0 volt interim steam generator tube support plate plugging criteria for fuel cycle 14.
The requested information is contained in the attachment to this letter.
This letter is submitted pursuant to 10 CFR 50.30(b),
- and, as such, an oath statement is attached.
Sincerely, E.
E. Fitzpatrick Vice President dr Attachments cc:
A. A. Blind G. Charnoff
-'J.
B. Martin - Region III NFEM Section Chief NRC Resident Inspector J.
R. Padgett 1
P 9403040278 440224 PDR.-,ADOCK'5000315 l?..
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STATE OF OHIO)
COUNTY OF FRANKLIN)
E.
E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing ADDITIONALINFORMATION IN SUPPORT OF 2.0 VOLT INTERIM STEAM GENERATOR TUBE SUPPORT PLATE PLUGGING CRITERIA FOR FUEL CYCLE 14 and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this ~~<
day of 19 ~9 NOTAR PUBLIC RlTA D. HILI-
ATTACHMENT TO AEP:NRC: 1166M ADDITIONALINFORMATION RELATED TO 2.0 VOLT INTERIM STEAM GENERATOR TUBE SUPPORT PLATE INTERIM PLUGGING CRITERIA TECHNICAL SPECIFICATION AMENDMENT REQUEST
1
Attachment to AEP:NRC:1166M Page 1
This attachment provides additional information regarding our 2.0 volt steam generator tube support plate interim plugging criteria (IPC) technical specification amendment request (AEP:NRC:1166L dated February 15, 1994);
The additional information was requested by the NRC staff during a February 23, 1994, teleconference.
ITEM 1:
ADDITIONALCLARIFICATION INFORMATION All flaw indications with bobbin voltages greater than 1.0 volt will be inspected using a rotating pancake coil probe (RPC).
2.
A sample RPC inspection of a minimum of 100 tube support plate intersections will be performed.
All intersections with dent voltages exceeding 5.0 volts willbe inspected by RPC.
Inclusion of other intersections in the sample population will be based on inspecting intersections with artifact indications and intersections with unusual phase angles.
Expansion of the sample plan, if required, willbe based on the nature and number of the flaws discovered.
3.
RPC flaw indications not found by the bobbin probe because of masking effects (due to denting, artifact indications, or noise) will be plugged or repaired.
The NRC will be
- informed, prior to plant restart from the refueling outage, of any unexpected inspection findings relative to the assumed characteristics of the flaws at the tube support plate elevations.
This includes any detectable circumferential indications or detectable indications outside the tube support plate.
5.
The probability of tube burst, during a postulated main steamline break, will be reported to the NRC prior to startup from the refueling outage.
ITEM 2:
CLARIFICATION ON USE OF SMALLER DIAMETER BOBBIN All steam generator tube support plate intersection inspections willbe conducted with a standard 0.720 inch diameter bobbin probe unless tube restrictions prevent passage of the standard probe.
A smaller diameter bobbin probe will be used in these instances.
A typical situation where the smaller diameter probe would need to be employed is when a hot leg tube end is sleeved (preventing hot leg entry of the standard probe) and U-bend ovality prevents passage of the standard probe from the cold leg side to the hot leg side.
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'ttachment to AEP:NRC:1166M Page 2
As discussed in our letter AEP:NRC:1166L, we are currently investigating the use of smaller diameter bobbin probes in conjunction with the IPC. It is our understanding that use of a smaller diameter probe will requ'ire a rigorous statistical analysis.
If the smaller diameter probe is used in conjunction with the IPC, it will be the subject of separate correspondence with the NRC. If this statistical analysis is not conducted, tube repair for tubes requiring a smaller bobbin probe will be based on the standard (i.e.,
non-IPC) technical specification criterion-of 40$ throughwall degradation as determined with the smaller bobbin probe.
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