ML17333A607
| ML17333A607 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/21/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69437, NUDOCS 9610230289 | |
| Download: ML17333A607 (7) | |
Text
October 21, 1996 Hr. E.E. Fitzpatrick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO D.C.
COOK'S
RESPONSE
TO GENERIC LETTER 87-02 (TAC NO. H69437)
Dear Hr. Fitzpatrick:
The staff is reviewing your January 30, 1996, submittal responding to NRC Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46."
We have identified additional information as shown in the attachment which is necessary for our review.
If you have any questions on these
- items, please contact me at (301) 415-3017.
Sincerely, Docket Nos.
50-315 and 50-316
Enclosure:
As stated cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC PD3-3 Reading JRoe OGC ACRS JCaldwell, RIII YKim Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor 'Projects III/IV Office of Nuclear Reactor Regulation l
EAdensam(E)
GHarcus DOCUMENT NAME:
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October 21, 1996 Mr. E.E. Fitzpatrick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION RELATED TO D.C.
COOK'S
RESPONSE
TO GENERIC LETTER 87-02 (TAC NO. H69437)
Dear Hr. Fitzpatrick:
The staff is reviewing your January 30, 1996, submittal responding to NRC Generic Letter 87-02, "Verification of Seismic Adequacy of Hechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46."
Me have identified additional information as shown in the attachment which is necessary for our review.
If you have any questions on these
- items, please contact me at (301) 415-3017.
Sincerely, Docket Nos.
50-315 and 50-316
Enclosure:
As stated cc w/encl:
See next page DISTRIBUTION:
Docket File, PUBLIC PD3-3 Reading JRoe OGC ACRS JCaldwell, RIII YKim Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation EAdensam(E)
GMar cus DOCUMENT NAME:
G:ii,DCCOOKiC069437.RAI To recelee ~ copy of thte document. Inc%cote ln the box:
C
~ Copy whhctrt ettechmentfendoetee
'E Copy with ettechment/endoetee
'N' No copy OFFICE LA:PD33
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PH:PD33 NAME DATE JHickman
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Hr. E.
E. Fitzpatrick Indiana Hichigan 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, OC 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 Oivision 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 Hichigan 'Power Nuclear Generation Group 500 Circle Drive
- Buchanan, Michigan 49107 August 1996
RE UEST 0
ADDI ON INFORMA ON UNRESOLVED SAFET ISSU A-46 R VIEW ONALD C.
COOK NUCL AR ANT UNI 1
EL With respect to Section 2.2, page 2-2, discuss the engineering basis for using the In-Structure
Response
Spectra (ISRS) developed for the Diesel Generator Building to determine loads in the Auxiliary Building at Elevation 609 feet, and provide the Diesel Generator Building and Auxiliary Building ISRS.
Discuss key examples of designated "rigorously analyzed anchorages,"
(page 4-6) using hand calculation and ANCHOR4 software package and provide copies of their engineering calculations.
Also discuss a few cases of anchorage verification based on results of tug tests conducted and provide a description of the tests and applicable engineering justification for such an approach.
Table 4.5 shows that the 1.5 x Bounding Spectrum and the GERS with an amplification factor of 7 do not envelope the floor response spectra.
Provide copies of the seismic demand versus capacity spectral comparison.
Regarding the tightness check of expansion anchors performed on a
representative number of mechanical and electrical components, state whether the representative number meets the sample size for expansion anchor tightness check as listed on Table C.2-4 of the GIP.
Table 5.1 shows only four (4) vertical tanks for GIP review.
Provide the engineering criteria for selecting only four vertical tanks and the
" justification of the structural integrity of the other smaller vertical tanks for Safe Shutdown Earthquake (SSE).
Indicate the number of vertical tanks supported on skirts and structural legs at Donald C.
Cook Nuclear Plant, Units 1
8 2.
Section
- 5. 1.2 states that all four tanks reviewed met the intent of the GIP.
Indicate that the GIP-2 guidelines and methodology are fully met or identify any deviations from the guidelines and methodology.
Provide calculations for determining the seismic adequacy of the tanks (ID 1-TK-33 and 2-TK-32) using the methodology described in Section 7 of the GIP-2.
The evaluation of the anchors which restrain the tank moVement should also be provided.
Section 5. 1.5 states that horizontal tanks and heat exchangers reviewed met the intent of the GIP.
Indicate that the GIP-2 guidelines and methodology are fully met or identify any deviations from them.
Provide calculations using the methodology described in Section 7 of the GIP-2 for the following tanks and exchangers:
1-HE-14,'-HE-15E, 12-HE-16N, I-gT-107-AB and 2-gT-115-CD.
The evaluation of the anchors which restrain the tank movement should also be provided.
ENCLOSURE
Tables 6-1 and 6-2 provide a su+vary of the limited analytical reviews (LARs) for the selected cable and conduit raceways.
Provide copies of the calculations of the analyses for resolution of the outliers listed as LAR Numbers
- 005, 011, 022 and 023.
Also, provide typical sample calculations for the raceways that are not selected as outliers (i.e.,
LAR Numbers
- 001, 010, 027 and 030).
Discuss the issue described in the Information Notice 95-49 regarding Thermo-Lag panels, in particular, the issue regarding seismic resistance capability of the cable tray and its support when appropriate weight and modulus of the Thermo-Lag are included in the analysis.
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