ML17333A936
| ML17333A936 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/09/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. |
| References | |
| GL-96-06, GL-96-6, TAC-M96801, TAC-M96802, NUDOCS 9707110069 | |
| Download: ML17333A936 (7) | |
Text
Gu1y 9, 1997
'r.
E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, Ml 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONALINFORMATION RE: GENERIC LETTER 96-06 (TAC NOS.
M96801
- 5. M96802)
Dear Mr. Fitzpatrick:
The staff has reviewed your January 28, 1997, and May 20, 1997, submittals regarding Generic Letter 96-06, "Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions."
In the first letter, you indicated that the Donald C. Cook facility was not susceptible to either water hammer or two-phase flow. However, you also identified that several pipe lines penetrating the containment are susceptible to thermally-induced pressurization and that you were performing further evaluations of these pipe lines.
In the second letter, you indicated that the evaluation of these pipe lines demonstrated that the design criteria are met for the accident conditions.
On the basis of our review of your submittals, the staff finds it needs additional information in order to complete our review of the generic letter.
Please respond to the enclosed Request for Additional Information within 60 days.
Please contact me at (301) 415-3017 if you have any questions on the above.
Siricerely, Original signed by:
John B. Hickman, Project Manager Project Director'ate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation I
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Quly 9, 1997 Mr. E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONALINFORMATIONRE'ENERIC LETTER 96-06 (TAC NOS.
M96801 8L M96802)
Dear Mr. Fitzpatrick:
The staff has reviewed your January 28, 1997, and May 20, 1997, submittals regarding Generic Letter 96-06, "Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions."
In the first letter, you indicated that the Donald C. Cook facility was not susceptible to either water hammer or two-phase flow. However, you also identified that several pipe lines penetrating the containment are susceptible to thermally-induced pressurization and that you were performing further evaluations of these pipe lines.
In the second letter, you indicated that the evaluation of*these pipe lines demonstrated that the design criteria are met for the accident conditions.
On the basis of our review of your submittals, the staff finds it needs additional information in order to complete our review of the generic letter.
Please respond to the enclosed Request for Additional Information within 60 days.
Please contact me at (301) 415-3017 if you have any questions on the above.
, Sin'cerely, Original signed by:
John B. Hickman, Project Manager Project 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 DOCUMENT NAME: G:iDCCOOKic096801.RAI DISTRIBUTION:
Docket Files PUBLIC PD3-3 R/F EAdensam (EGA1)
GGrant, Rill GMarcus JRoe OGC ACRS JFair BWetzel OFFICE NAME DATE PM:PD33 JHickma
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/97 LA:PD33 E
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/97 FFI IAL RECORD COPY
Mr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Re'gion 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 Stevensvi,lie, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Hayor, 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 equality 3423 N. Martin Luther King Jr Blvd P. 0.
Box 30630 CPH Mailroom
- Lansing, Michigan 48909-8130 Donald C. Cook Nuclear Plant Units 1 and 2
Hr. Steve J.
Brewer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, Michigan 49107
REQUEST FOR ADDITIONALINFORMATION GENERIC LETTER 96-06 DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 (TAC NOS. M96801 AND M96802) 1.
The January 28, 1997, submittal, indicated that seven piping runs susceptible to thermally-induced overpressure were determined to be acceptable based on the valve design.
These piping runs contained either spring-loaded globe or spring-loaded diaphragm valves that form isolation barriers.
In the submittal, it was stated that these valves would liftoff their seats and relieve tIIe pressure prior to the piping exceeding its design allowable stresses.
Provide the following information for each piping run evaluated in this manner:
a.
Describe the applicable design criteria for the piping and the valves.
Include the required load combinations; b.
Provide a drawing of the valve.
Provide the pressure at which the valve was determined to liftoff its seat and describe the method used to estimate this pressure.
Discuss any sources of uncertainty associated with the estimated liftoff pressure; and c.
Provide the maximum-calculated stress in the piping run based on the estimated lift off pressure.
2.
The May 20, 1997, submittal, indicated that the Reactor Coolant Pump Seal Water Return Line and the Accumulator Sample Line were evaluated using an enthalpy balance or thermodynamic analysis.
Provide the following information for each of these piping runs:
a.
Provide the applicable design criteria for the piping and the valves.
Include the required load combinations; b.
Provide a drawing of the piping run between the isolation valves.
Include the lengths and thicknesses of the piping segments and the type and thickness of the insulation; and c.
Provide the maximum-calculated temperature and pressure for the pipe run.
Describe, in detail, the method used to calculate these pressure and temperature values.
This should include a discussion on the heat transfer model used in the analysis and the basis for the heat transfer coefficients used in the analysis.
3.
The May 20, 1997, submittal, indicated that the three reactor coolant sample lines are isolated at a temperature above the post-LOCA containment temperature.
On this basis, it was concluded that pressure would remain below the design pressure for these lines.
Discuss whether there are any possible scenarios in which these lines could be isolated when the fluid is at the normal containment ambient temperature.
ENCLOSURE