ML17333A763
| ML17333A763 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/04/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| TAC-M96357, NUDOCS 9702060288 | |
| Download: ML17333A763 (7) | |
Text
Februar y 4, 1997
I Hr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power 1
Nuclear Generation Group k
500 Circle Drive
- Buchanan, HI 49107
'l 1(
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE DC'COOK NUCLEAR POWER PLANT, UNIT 2 SECOND 10-YEAR INTERVAL INSERVICE,INSPECTION PROGRAM PLAN REQUEST FOR RELIEFEACTOR VESSEL NOZZLE WELDS (TAC NO. H96357)
II
Dear Mr. Fitzpatrick:
By letters dated June 28, 1996 and September 10,
- 1996, you requested deferral of examination of reactor vessel nozzle to shell welds for D.
C.
Cook Nuclear plant, Unit 2 due to examinations having been. performed, at an instrume'nt gain setting below that required by the ASME B&PV Code.
Additional information is required in order for the staff to complete its review of your request.
Please review the enclosed request for additional information and provide a
response within 60 days.
In addition, to expedite the review process, please send a copy of the RAI response to NRC's contractor, INEL, at the following address:
Michael T. Anderson INEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions on these
- items, please contact me at (301) 415-3017.
Sincerely, Docket Nos.
50-316
Enclosure:
As stated cc w/encl:
See next page Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation ACRS DISTRIBUTION:
Docket File PUBLIC EAdensam(E)
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February 4,
1997 Mr. E.
E. Fitzpatrick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, MI 49107
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE DC COOK NUCLEAR POWER PLANT, UNIT 2 SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF REACTOR VESSEL NOZZLE WELDS (TAC NO. M96357)
Dear Mr. Fitzpatrick:
By letters dated June 28, 1996 and September 10,
- 1996, you requested deferral of examination of reactor vessel nozzle to shell welds for D.
C.
Cook Nuclear plant, Unit 2 due to examinations having been performed at an instrument gain setting below that required by the ASME BatPV Code.
Additional information is required in order for the staff to complete its review of your request.
Please review the enclosed request for additional information and provide a
response within 60 days.
In addition, to expedite the review process, please send a copy of the RAI response to NRC's contractor, INEL, at the following address:
Michael T. Anderson INEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions on these
- items, please contact me at (301) 415-3017.
Sincerely, Docket Nos. 50-316
Enclosure:
As stated cc w/encl:
See next page Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation DISTRIBUTION
'ocket File PUBLIC PD3-3 Reading JRoe OGC JCaldwell, RIII DOCUMENT NAME:
G:iDCCOOKiC096357.RAI EAdensam(E)
GMarcus TMcLellan ACRS OFFICE LA'PD33
~
PM PD33 To recehre ~ copy of this document, Inrscste In the hoxr c
~ copy without sttschment/enc/osure
'E
~ Copy with sttschmsnt/enctosure N
a No copy NAME JHickman EBarnhill DATE
'2/ g/87 8 /
- /97 OFFICIAL R CORD COPY
Hr.
E.
E. Fitzpatrick Indiana Michigan Power Company Cco Regional Administrator, Regi'on III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street
- Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Site Vice President Donald C.
Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's 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 Drinking Water and Radiological Protection Division Michigan Department of Environmental guality 3423 N. Hartin Luther King Jr Blvd P. 0.
Box 30630 CPH Hailroom Lansing, Michigan 48909-8130 Donald C.
Cook Nuclear Plant Hr. Steve J.
Brewer Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, Michigan 49107 August l996
IANA H CHIGAN POWER COHP Y
DONALD C.
COOK NUCLEAR POWER PLANT UNIT 2 OC U BE 5 -3 6 CIV GI EE I G
G OSCIENCES RANCH SIO 0
GIN I
G e
est o
d itio al fo at o
Second 10-e r Interval Re est or e ief for Reactor Pressure Vessel Nozzle-to-Shell Weld Examinations I.
Sco e Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Hechanical Engineers (ASHE) Boiler and Pressure Vessel Code Class 1, Class 2,
and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASHE Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design,
- geometry, and materials of construction of the components.
This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during a 120-month inspection interval comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
The Code of record for the second 10-year interval is the 1983 Edition of ASHE Section XI with the 1983 Summer Addendum.
The staff has reviewed the information submitted by the licensee in
- letters, dated June 28,
- 1996, and September 10, 1996, requesting approval Enclosure
of ultrasonic examinations performed on the reactor pressure vessel nozzle-to-shell welds at an instrument gain setting below that required by the Code for the D. C. Cook Nuclear plant, Unit 2.
2.
ddition nformation e uired Based on the current review, the staff has concluded that additional information and/or clarification is required to complete the evaluation.
- 2. 1 Provide the percentage of Code-required volumetric coverage that was obtained for each of the subject nozzle-to-shell welds.
2.2 The licensee has stated that the one recordable flaw ( Indication 1, Examination Number 50rr, dispositioned as acceptable) detected during the first interval examinations was again detected in the second interval.
A data evaluation report by Southwest Research Institute dated August 1996 is included with the licensee's September 10,
- 1996, submittal.
This report discusses this indication, which was determined to be unacceptable based on the initial evaluation results.
It is further stated that this indication was sized in 1988 and again in 1990 using a tip-diffraction technique from the outside surface of the vessel and determined to be a Code-acceptable flaw.
Mhat was the requirement for confirming the flaw size in two separate outages?
Based on the review of the Detection Evaluation/Correlation Of Previous
- Data, Table A, it appears that this indication was first detected in 1977 below the Code recording threshold.
Considering the information provided, it appears that the indication has developed from a nonrecordable flaw to a recordable flaw that has been monitored.
Discuss the reason for concluding that the subject flaw is stable.
2.3 The 1996 ISI Sizing Evaluation, Table B, identifies ten recorded flaws.
Based on a review of the table, it appears that five of the recorded flaws exceed the "a/t" allowable by Code.
Provide the
disposition and basis for disposition for these indications.
For flaws exceeding the acceptance criteria of Table IWB-3512-1, analytical evaluation of the flaws may provide a basis for acceptance.
Has fracture analysis been performed on any of the subject flaws2 Has manual sizing of other recorded indications included in Table A been performed2 It should be noted that flaws found acceptable by fracture analysis for Class 1 components require additional examinations for three successive periods.
2.4 The licensee has stated that the type of flaws recorded for the nozzle-to-shell weld examinations are typical of slag inclusions.
The licensee further stated that Indication 1, Examination Number
- 50rr, was found acceptable by a tip-diffraction sizing technique.
Tip-diffraction sizing techniques are typically applied to crack-type indications.
Signal characteristics of slag inclusions may differ from crack-like reflectors.
Therefore, provide the basis for concluding that the data obtained for sizing the subject flaw indicates the true flaw size.
The schedule for timely completion of this review requires that the licensee
- provide, by the requested
- date, the above requested information and/or clarifications regarding the second 10-year interval reactor pressure vessel nozzle-to-shell welds examinations.