ML17335A304
| ML17335A304 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/21/1998 |
| From: | Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0969BN, AEP:NRC:969BN, NUDOCS 9810280028 | |
| Download: ML17335A304 (8) | |
Text
CATEGORY 1 REGULA RY, INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NER:9810280028 DOC.DATE: 98/10/21 NOTARIZED: NO 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 POWERS,R.P.
(formerly Indiana 8 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards background info Ec justification amend 1 to Code Relief Request 4 for Class 1 RPV lower head
& closure head dollar plate welds for Cook Nucl'ear Plant Units 1
6 2 third 10-yr.interval ISI plan.
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR 4 ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief
&rom ASME Code GL-89-04 NOTES:
RECIPIENT ID CODE/NAME PD3-3 LA STANG, J INTERNAL: AEOD/SPD/RAB NRR/DE/ECGB OGC/HDS3 RES/DET/EMMEB COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD3-3 PD ILE CENT R
NUDOCS-ABSTRACT RES/DET/EIB COPIES LTTR ENCL 1
1 1
1 1
1 1,
1 G
0 EXTERNAL: LITCO ANDERSON NRC PDR 1
1 1
1 NOAC D
0 E
'N NOTE TO ALL, "RIDS" RECIPIENTS:
PLEASE HELP'US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12
Indiana Michiga~
Power Company~
500 Circle Drive Buchanan, Ml 491071373 October 21, 1998 AEP:NRC:0969BN Docket Nos:
50-315 50-316 U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop 0-Pl-17 Washington, D. C. 20555-0001 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1
& 2 RELIEF REQUEST FOR THE THIRD TEN-YEAR IN-SERVICE INSPECTION PLAN
References:
- 1. Letter, AEP:NRC:0969AJ, "Ponald " C.
Cook Nuclear Plant Units 1 and 2,
RELIEF REQUESTS 'FOR THE'HIRD TEN-YEAR IN-SERVICE INSPECTION PLAN", dated January 25, 1996.
- 2. Letter, John B.
- Hickman, NRC to E.
E. Fit'zpatrick,
- AEP, "REQUEST FOR ADDITIONAL INFORMATION REGARDING THE D.
C.
COOK NUCLEAR PLANT, UNITS 1
AND 2 THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF (TAC NOS.
M94871 and M94872), dated January 14, 1998.
- 3. Letter, AEP:NRC:0969BK, "Donald C.
Cook Nuclear P'ant Units 1
and 2,
ADDITIONAL INFORMATION REGARDXNG THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN", dated July 8, 1988.
able g<'I
~ g81O28QO28 go~gg 28 98102i
,PDR AOQCK 6
Cook Nuclear Plant's third ten year in-service inspection
- plan, together with its associated relief request, was transmitted to the NRC in reference 1
~
Subsequent to this submittal, reference 2 transmitted a request for additional information regarding the test plan and the relief requests.
Reference 3 responded to the request for additional information.
As part of the response; we stated that we would revise relief request number 4 for both units to correct a mis-statement regarding the examination of meridional welds.
The previous, relief requesthad stated 'that one meridional weld would. be examined,"'hereas 'he access
'ength of all meridional welds will be 'examined."
U.
S. Nuclear Regulatory Commission
~ Page 2
AEP:NRC:
0969BN The relief request, which is being submitted under the provisions of 10 CFR 50.55a(g)(5)(iii), is attached to this letter.
Sincerely, P.
Powers Vice President
/jmc Attachment J.
A. Abramson J.
L. Caldwell, w/attachment MDEQ DW
& RPD NRC Resident Inspector, w/attachment J.
R.
- Sampson, w/attachment
U. S. Nuclear Regulatory Commission
~
Page 3
AEP:NRC:
0969BN bc:
T.
P. Beilman, w/attachment E.
R. Eckstein/D.
R. Hafer/K.
R. Baker J. J.
Euto FOLIO, w/attachment B. J. Hickle G.
Honma J.
B. Kingseed/G.
P. Arent/M. J.
Gumns J.
F. Stang, Jr., - NRC Washington, DC, w/attachment
ATTACHMENT TO AEP:NRC:0969BN BACKGROUND INFORMATION AND JUSTIFICATION AMENDMENT 1 TO CODE RELIEF REQUEST 84 FOR CLASS 1
RPV LONER HEAD AND CLOSURE HEAD DOLLAR PLATE WELDS FOR THE COOK NUCLEAR PLANT UNITS 1 AND 2 THIRD 10-YEAR INTERVAL
Attachment to AEP:NRC:0969BN Page 1
I System/Component for Which Relief Is Requested All class 1 reactor pressure vessel lower and closure head dollar plate welds for units 1
& 2.
lI Code Requirements In accordance with the Code of Federal Regulations Title 10, (a) paragraph 50.55(a)(g)(5)(iv),
ASME Section XI, 1989 edition, no addenda, Table IWB-2500, Examination Category B-A requires that circumferential and meridional head welds be volumetrically examined during each 10-year interval for the accessible length of weld.
III Basis for Code Relief The implementation of code requirements as written and interpreted in the 1989 edition of the ASME Section XI code for volumetric examination of the lower and closure head dollar plate welds is impractical due to limited access caused by the control rod drive mechanism (CRDM) head penetrations and CRDM heat shroud for the closure head and the instrumentation penetrations for the lower head dollar plate welds.
IV Alternative Method It is proposed
- that, in lieu of the volumetric examination requirements of ASME section XI for class 1
vessel head
- welds, the results of the system leakage test and VT-2 examination of all welds conducted during each refueling outage be used as a
means of assessing the dollar plate weld integrity.
Any through-wall leakage detected during these examinations would provide an early indication of a defective weld.
These examinations will be conducted in accordance with ASME Section XI, IWB-2500, Category B-P and Code Case N-498-1, which has been previously approved by the NRC for use at the plant, reference 1.
V Justification for Granting Code Relief Volumetric examination of the accessible length of the dollar plate welds for both heads is not possible due to examination limitations created by interference of the CRDM heat shroud and CRDM penetrations on the closur'e head dollar plate welds and the instrument penetrations located in the lower head.
Removal of the CRDM heat shroud and metallic insulation from the closure head would be required to perform a limited exam on those lengths of weld between CRDM penetrations.
Radiation exposure to remove the shroud and conduct a
limited volumetric examination is
l
Attachment to AEP:NRC:0969BN Page 2
significant and would offset the benefits of conducting a limited ultrasonic examination.
Access to the lower head dollar plate welds from the inside diameter of the vessel is not possible with the automated examination equipment due to instrumentation penetrations.
Access from beneath the. vessel to conduct a
volumetric examination after removing
'metallic insulation is also limited due to the penetrations and also would result in unacceptable radiation exposures due to removal of and re-installation of insulation and the ultrasonic examination activities.
Relief was requested and granted for units 1
and 2
during our first and second 10-year intervals, references 2
and 3.
There are no known reported industry failures of these'elds based on input from our second 10-year interval ISI vendor.
It is therefore concluded that the code relief requested above will not endanger life or property or otherwise compromise common defense and security.
References 1.
- Letter, C.
A. Carpenter to E.
E. Fitzpatrick, "D.
C.
Cook, Units 1 and 2, Requesting Approval of Code Case N-498-1 as an Alternative to the Required Hydrostatic Pressure Test",
dated July 5, 1995.
2.
- Letter, S.
A.
Varga to J.
- Dolan, "Safety Evaluations Related to Requests for Relief from Inservice Inspection Requirements",
dated April 15, 1983.
3.
- Letter, T.
G.
Colburn to MD P.
- Alexich, "Safety Evaluation Report of the Inservice Inspection Programs for D.
C.
Cook Units 1 and 2", dated January 24, 1991.