ML17331A998
| ML17331A998 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/07/1993 |
| From: | Wetzel B Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E ILLINOIS POWER CO. |
| References | |
| GL-88-11, GL-92-01, GL-92-1, TAC-M83453, TAC-M83454, NUDOCS 9310140270 | |
| Download: ML17331A998 (6) | |
Text
October 7,
1993 Docket Nos.:
50-315 and 50-316 Hr.
E.
E. Fitzpatri ck, Vice Pres ident Indiana and Michigan Power Company c/o American Electric Power Service Corp.
1 Riverside Plaza
- Columbus, Ohio 43216
Dear Hr. Fitzpatrick:
DISTRIBUTION:
Docket Fi1 e NRC & Local PDRs PD31 Rdg File J. Roe J.Zwolinski W.Dean B.Jorgensen,RIII C.Jamerson OGC ACRS (10)
B.Wetzel D.HcDonald S.Sheng J.Strosnider
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION LICENSEE'S
RESPONSE
TO GENERIC LETTER 92-01, REVISION 1
(TAC NOS.
M83453 and H83454)
By letter dated July 13,
- 1992, Indiana Michigan Power Company submitted its response to Generic Letter (GL) 92-01, Revision 1, "Reactor Vessel Structural Integrity'," for the D.
C.
Cook Nuclear Plant, Units 1 and 2.
The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations,"
regarding reactor vessel structural integrity.
Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The staff has completed a preliminary review of your response to GL 92-01, Revision 1, for D.C.
Cook Units 1 and 2.
Enclosed is a request for additional information (RAI) which will allow the staff to complete its review.
We request a response to this RAI within 45 days of receipt of this letter.
If you have any questions concerning the enclosed RAI please contact me on (301) 504-1355.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OHB clearance is not required under P.L.96-511.
Enclosure:
RAI cc w/enclosures:
See next page Sincerely, Original Signed By:
Beth A. Wetzel, Acting Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation NAME LA:PD31 CJamerson PH: PD31 BAWetzel:sw A D:PD31 WMDean DATE 0
7 f$
/0 OFFICIAL RECORD COPY FILENAME: G:iWPDOCSiDCCOOK C083453.RAI 9310140270 '931007 PDR ADOCK.05000315
-'P 'DR~
I I
t l
,>RA(~Bk
~e
~
~p,q Rg'0~
')
C I
0O
+a*++
Docket Nos.
50-315 and 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 7, 1993 Hr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Hr. Fitzpatrick:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION LICENSEE'S
RESPONSE
TO GENERIC LETTER 92-01, REVISION 1
(TAC NOS.
H83453 and M83454)
By letter dated July 13,
- 1992, Indiana Michigan Power Company submitted its response to Generic Letter (GL) 92-01, Revision 1, "Reactor Vessel Structural Integrity," for the D.
C.
Cook Nuclear Plant, Units 1 and 2.
The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations,"
regarding reactor vessel structural integrity.
Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The staff has completed a preliminary review of your response to GL 92-01, Revision 1, for D.C.
Cook Units 1
and 2.
Enclosed is a request for additional information (RAI) which will allow the staff to complete its review.
We request a response to this RAI within 45 days of receipt of this letter.
If you have any questions concerning the enclosed RAI please contact me on (301) 504-1355.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosure:
RAI Beth A. Wetzel, Acting Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc w/enclosures:
See next page
Mr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street
- Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P.
O.
Box 30195
- Lansing, Michigan 48909 Donald C.
Cook Nuclear Plant Mr. S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216 July 1993
~ r
'v
RE UEST OR ADDI IONAL INFORM 0
EGARDING GL 92-01 REVIS ON I D. C.
COOK I TAG No. 183453 uestion 2a in GL 92-0 The response to GL 92-01 indicates that the initial upper-shelf energy (USE) values for all beltline welds, except the surveillance weld, are not known.
Either provide the Charpy USE for each beltline weld or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds will meet the USE requirements of Appendix G, 10 CFR Part 50. If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASNE Code.
Attachment 6 of the response lists two sets of USE values for all six beltline plates.
Confirm that the transverse USE values (under the heading NHWD) in Table 7 are derived from longitudinal specimens and the corresponding values in Table 8 are actual test data.
Also confirm that both sets of USE values are unirradiated ones.
uestion 2b in GL 92-01 Attachment 3 of the response reports a chemical composition of 0.28X copper and 0.74K nickel for the axial welds (wire heat numbers 13253 and 12008) and the circumferential welds (wire heat number IP3571).
This chemistry data is from the surveillance weld of wire heat
- 13253, and cannot be used for beltline welds with different heat numbers although they all used the same Linde 1092 flux.
Either provide the chemistry data for each beltline weld or establish a
generic chemistry value from all Linde 1092 welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification.
Update the end-of-life (EOL)
USE and RT yg calculations based on this new weld chemistry value to demonstrate that all beltline welds will meet the USE requirements of Appendix G, 10 CFR Part 50 and RT>>, limits of 10 CFR 50.61.
Attachment 6 of the response indicates that the initial RT>>, value for all beltline welds is O'.
The corresponding value from the pr~essurized thermal shock (PTS) submittal dated Harch 19, 1987, is -56'F.
Resolve this discrepancy and provide the basis for the single value to be reported.
D. C.
COOK 2 TAC No. N83454 uestion 2a in GL 92-01 Attachment 7 of the response listed the USE values for plates C5556-2, C5540-2, and C5592-I as 90,
- 110, and 103 ft-lb.
Identify the orientation of the Charpy specimens from which these values were obtained.