ML17333A857
| ML17333A857 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/14/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. |
| References | |
| GL-87-02, GL-87-2, TAC-M69437, TAC-M69438, NUDOCS 9704160292 | |
| Download: ML17333A857 (8) | |
Text
April 14, 1997 Mr. E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, MI 49107
SUBJECT:
DONALD C.
COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 -
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS (TAC NOS.
M69437 AND M69438)
Dear Mr. Fitzpatrick:
By letter dated January 30, 1996, you.submitted a response to Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors."
Our review of that response will require additional information regarding operator'ctions specified in the report.
Please provide a response to the enclosed request for additional information within 60 days.
Please contact me at (301) 415-3017 if you have any questions regarding the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Proje'ct Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos.
50-315 and 50-316
Enclosure:
Request for Additional Information cc w/encl:
See next page Docket File PUBLIC PD3-3 R/F JRoe EAdensam (EGA1)
GMarcus JCaldwell, RIII OGC ACRS GGalletti RPelton
$ 60017 DOCUMENT NAME:
G:ii,DCCOOKiC069437.LTR To receive a copy ot tNs document, indicate In the box:
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~ Copy without attachment/enctosvre E'
Copy with attachment/enclosure N
~ No copy OFFICE PM:PD3-3 E
LA:PD3-3 E
NAME DATE JHickman
/i /97 Bo le
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/97 9704ib029'2 9704i4 PDR ADQCK 050003i5 P
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April 1 4, i 997 I~
Hr.
E.- E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
SUBJECT:
DONALD C.
COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS (TAC NOS.
M69437 AND H69438)
Dear Hr. Fitzpatrick:
By letter dated January 30, 1996, you.submitted a response to Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors."
Our review of that response will require additional information regarding operator'ctions specified in the report.
Please provide a response to the enclosed request for additional information within 60 days.
Please contact me at (301) 415-3017 if you have any questions regarding the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation I
Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC PD3-3 R/F JRoe EAdensam (EGA1)
GMarcus JCaldwell, RIII OGC ACRS GGalletti RPelton DOCUMENT NAME:
G:iDCCOOKiI,C069437.LTR To receive ~ copy oi this document, Indtcete in the box/ 'C' Copy without ettechment/enctosure E i Copy with ettechment/enclosure
'H
~ No copy OFFICE PH:PD3-3 E
NAME
. JHickman LA:PD3-3 E
Bo le DATE
/i /97
/
/97 OFFICIAL R CORD COPY
0 Eh
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 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 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 hugust l996
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RE(VEST FOR ADDITIONAL INFORMATION A. Section
- 5. 1, "Guidance Philosophy and Development," of the Safe Shutdown Equipment List Report, states in part, "operator actions are limited to those which have been proceduralized and the operators have been trained to perform."
The discussion also states that:
"Examples of anticipated additional (beyond normal actions) operation actions follows:," which includes actions to ensure control air, switchgear room cooling, and control room air conditioning is maintained.
Describe the operator training provided and or scheduled to ensure these additional operator actions are well understood and can be accomplished by the operating crew?
B.
C.
D.
E.
The discussion regarding the three additional (beyond normal actions) operator actions determined that there was ample time for the operators to decide that action needed to be taken and to actually perform the actions.
Describe the types of barriers to successful operator performance that were considered as part of this review.
Were issues such as lighting, heat and humidity, harsh environmental conditions, and the potential for damaged plant equipment and structures along the ingress/egress paths to the local areas where operators need to take these actions considered?
Section
- 5. 1, "Procedure Assumptions," indicates that the seismic procedure is patterned after the Westinghouse Emergency Operating Procedures (EOPs).
Section 5.2, "Synopsis of Operator Actions," also looks very similar to the current EOP E-0 entry procedure.
In the event of a plant transient caused by a seismic event, are the operators directed to initiate the seismic abnormal operating procedure in lieu of the EOPs?
If the seismic event causes a reactor trip, do the operators then transition into the EOPs (E-0) and perform the EOPs and well as the seismic abnormal procedure concurrently?
How have the operators been trained to take such actions and has this philosophy been adopted into the appropriate administrative procedures governing operator conduct of operations and EOP usage?
Section 5.0, "Operator Actions," of the Relay Evaluation Repor't discusses two actions which must be performed as a result of the relay evaluation.
It appears that these two actions have been discussed in the Safe Shutdown Report and are the subject of question (A), above.
If these actions are different then those discussed
- above, please indicate what types of evaluations were performed to ensure operators were able to take these
- actions, in the time frame specified, with consideration for possible harsh or adverse environmental conditions prevailing at the time these actions were required?
Are the operator actions associated with resetting the SSEL equipment affected by the postulated contact chatter considered to be routine and consistent with the skill of the craft? If not, what operator training and operational aids were developed to ensure the operators will perform the actions required to reset the affected equipment?
Section 4.6, "Class of Twenty-One Evaluation Results," of the Seismic Evaluation Report described a few generic interaction issues including seismic housekeeping issues in the control room.
Were any of the items identified significant missile hazards to plant personnel or control room equipment?
How were these housekeeping issues addressed?
ENCLOSURE
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