ML17334B627
| ML17334B627 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/27/1997 |
| From: | Marcus G NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17334B628 | List: |
| References | |
| TAC-M95721, TAC-M95722, TAC-M95890, TAC-M95891, NUDOCS 9706030233 | |
| Download: ML17334B627 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 May 27, 1997 So-3i< 3k Hr. E.
E. Fitzpatrick; Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
SUBJECT:
EVALUATION OF THIRD 10-YEAR INTERVAL FOR THE PUHP AND VALVE INSERVICE TESTING PROGRAH FOR DONALD C.
COOK NUCLEAR PLANT, UNITS 1
AND 2 (TAC NOS. H95721,
- H95722, H95890, AND H95891)
Dear Hr. Fitzpatrick:
By letters dated April 24,
- 1996, and June 12,
- 1996, you submitted the Third 10-Year Interval Inservice Testing (IST) Program for Pumps and Valves for the Donald C.
Cook Nuclear Plant, Units 1 and 2.
The staff has reviewed the proposed relief requests, deferred test justifications and other relevant sections of the licensee's IST program against the requirements of the 1989 Edition of Section XI of the American Society of Hechanical Engineers (ASHE)
Boiler and Pressure Vessel Code pursuant to paragraph 50.55a of Part 50 to Title 10 of the Code of Federal Re ulations.
The results of the review are provided in the enclosed Safety Evaluation (SE).
The review identified a number of anomalies which the licensee should address (see Section 6 of the SE).
Relief Requests REL-01, REL-03, and REL-07 are granted pursuant to 10 CFR 50.55a(f)(6)(i) based on the impracticality of the requirements and with consideration of the burden on the licensee if the requirements were imposed, provisional upon the inclusion of acceptance criteria and corrective actions in the appropriate inservice test procedure.
Relief Request REL-08 is granted pursuant to 10 CFR 50.55a(f)(6)(i) based on the impracticality of the requirements and with consideration of the burden, provisional on the sampling program complying with the guidance in Position 2
of Attachment 1 to Generic Letter 89-04 and NUREG-1482.
Relief Requests REL-02, REL-05, REL-06, REL-10, REL-ll, and REL'-12 (alternative test portion) are granted pursuant to 10 CFR 50.55a(f)(6)(i),
based on the impracticality of the requirements and with consideration of the burden on the licensee if the requirements were imposed, provided that the guidance in Position 2 of Attachment 1 to Generic Letter 89-04 is followed.
In addition, pursuant to 10 CFR 50.55a(f)(6)(i), Relief Request P-2 is granted on an interim basis for 90 days.
Pursuant to 10 CFR 50.55a(a)(3)(i),
Relief Request P-3 is granted based on the acceptable level of quality and safety that will be provided by the alternative.
0 lmm, pip g9I'IBICS'>
E. Fitzpatrick The alternatives requested in Relief Requests REL-04, REL-09, and REL-14 are allowed by the code and, therefore, requir'e no relief.
Relief Requests P-l, REL-12 (test frequency portion),
and REL-13 are denied.
The licensee should respond to the specific issues raised in the denied and interimly-approved requests within 90 days of the date of the SE.
The licensee should address the anomalies identified in Section 6 of the SE within an appropriate time period, no later than by the end of the next refueling
- outage, with a response to the NRC detailing the actions taken.
Sincerely, I
Original signed by:
Docket Nos.
50-315 and 50-316
='
Encl osure:
Safety Evaluati on cc w/encl:
See next page Gail H. Marcus, Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation I
DISTRIBUTION:
(w/encl )
Docket File PUBLIC PD3-3 R/F OGC ACRS JRoe EAdensam (EGAl)
JColaccino GGrant, RIII Q 3 u 0 1 9 THarris (TLH3, copy of SE ONLY)
DOCUMENT NAME:
G: iDCCOOKiC095721. REt.
To receive a copy of this document, Indicate In the box:
C
~ Copy without anachment/enctosure E
a C i t attachment/enctosure N
~ No copy OFFICE LA:PD33 E
PM:PD33 E
OGC N
D:PD33 DATE CBoyle 3
97 JHickma 5'//~
97
/P('7 OFFICIAL RECORD COPY GMarcus w>~
97
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E. Fitzpatrick The alternatives requested in Relief Requests REL-04, REL-09, and REL-14 are allowed by the code and, 'therefore, require no relief.
Relief Requests P-l, REL-12 (test frequency portion),
and REL-13 are denied.
The licensee should respond to the specific issues raised in the denied and interimly-approved requests within 90 days of the date of the SE.
The licensee should address the anomalies identified in Section 6 of the SE within an appropriate time period, no later than by the end of the next refueling
- outage, with a response to the NRC detailing the actions taken.
Sincerely, Original signed by:
Docket Nos.
50-315 and 50-316
Enclosure:
Safety Evaluation cc w/encl:
See next page Gail H. Marcus, Director Project Directorate III-3 Division of Reactor Projects'II/IV Office of Nuclear Reactor Regulation DISTRIBUTION:
(w/encl )
Docket File PUBLIC PD3-3 R/F OGC ACRS JRoe EAdensam (EGA1)
JColaccino GGrant, RIII THarris (TLH3, copy of SE ONLY)
DOCUMENT NAME:
G:iDCCOOK'ItC095721.REt.
To receive a copy of this document. Indicate in the box:
c
~ copy without attachmentlenctosute E
~ C i
attachmentlendosure st
~ No copy OFFICE LA:PD33 E
CBoyle PM:PD33 E
JHickma OGC D:PD33 GMarcus DATE 3
97 5 l>97 g('7 OFFICIAL RECORD COPY 52'7
0 I
E. Fitzpatrick The alternatives requested in Relief Requests REL-04, REL-09, and REL-14 are allowed by the code and, therefore, require no relief.
Relief Requests P-l,.REL-12 (test frequency portion),
and REL-13 are denied.
The licensee should respond to the specific issues raised in the denied and interimly-approved requests within 90 days of the date of the SE.
The licensee should address the anomalies identified in Section 6 of the SE within an appropriate time period, no later than by the end of the next refueling
- outage, with a response to the NRC detailing the actions taken.
Sincerely,
~j/8 ~
Gail H. Marcus, Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos.
50-315 and 50-316
Enclosure:
Safety Evaluation
,cc w/encl:
See next page
Hr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region 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'resident 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, Mich'igan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbrilge 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'rotection Division Michigan Department of Environmental equality 3423 N. Hartin Luther King Jr Blvd P. 0.
Box 30630 CPH Mailroom
- 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
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