ML20062J237

Forwards Latest Revisions of Piping Design Info for Midland Unit 2 Decay Heat Removal & Core Flooding Sys.Info Comprises Revision 8 of Matl for NRC Independent Confirmatory Piping Analysis.W/One Oversize Drawing.Aperture Card Is in PDR

ML20062J237
Person / Time
Site:	Midland
Issue date:	08/05/1982
From:	Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20062J239	List: ML20062J237 ML20062J292 ML20062J344 ML20062J361
References
18407, NUDOCS 8208160308
Download: ML20062J237 (21)

Text

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Consumers Power James W Cook b Vice President - Projects, Engineering 4 and Construction General offices: 1945 West Parnell Road, Jeckson. MI 49201 + (517) 788 0453 August 5, 1982 Harold R Denton, Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 MIDLAND NUCLEAR C0 GENERATION PLANT MIDLAND DOCKET NO 50-329, 50-330 ADDITIONAL INFORMATION CONCERNING STAET'S INDEPENDENT CONFIRMATORY PIPING ANALYSIS FILE: 0485.11, Bl.7 SERIAL: 18407

REFERENCES:

(1) J W COOK LETTER TO R L TEDESCO, SERIAL 10764, DATED JANUARY 12, 1982 (2) R L TEDESCO LETTER TO J W COOK DATED NOVEMBER 20, 1980 (3) J W COOK LETTER TO H R DENTON, SERIAL 14538, DATED OCTOBER 16, 1981 (4) J W COOK LETTER TO H R DENTON, SERIAL 14893, DATED NOVEMBER 30, 1981 (5) J W COOK LETTER TO H R DENTON, SERIAL 16222, DATED MARCH 4, 1982 (6) J W COOK LETTER TO H R DENTON, SERIAL 16629, DATED APRIL 12, 1982.

Enclosed herewith are three copies of the latest revisions of the piping design containing information for the Midland Unit 2 decay heat removal and core flooding systems. This is Revision 8 of the material being used for the staff's independent confirmatory piping analysis performed by the Energy Technology Engineering Center (ETEC).

This revision includes a revised index of drawings to reflect the current status of all the information provided. The following information is also included:

(1) Copics of the drawings which have changed (2) Bechtel Specifications 7220-M-345 Revision 2 and 7220G-G-6(Q) Revision 6 (3) B&W Specification No 18-1391000012-01

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r c 2 One copy of this information has been sent to Mr Paul Chen of ETEC by copy of this correspondence. Subsequent drawing updates will be issued on a quarterly basis. If there are any questions, please advise us.

JWC/WJC/bjw CC JRajan, NRC, w/a PChen, ETEC w/a RJCook, Midland Resident Inspector w/o RHernan, NRC w/a oc0882-0195a100

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BCC RCBauman, P-14-312B, w/o JEBrunner, M-1079, w/o DMBudzik, P-24-517A EMHughes, Bechtel, w/o RWiluston, Washington, w/o DFlewis, Bechtel, w/o DBMiller, Midland, w/o WSkelly, Bechtel, w/o RLTeuteberg, P-24-505, w/o Licensing Clerk NRC Correspondence File oc0882-0195b100

,- Q" INDEX

1. Piping Layout and Isometric Drawings Bechtel llanger Drawing 7 220-11-611, Sh 1( 0) , Rev 9

2. Support Drawings with Support Ilanger Spring Rates (See ITT Grinnell Catalog Pil79, Page ph-90 for support hanger spring rates):

ITT Grinnell Hanger Drawings Sketch Rev 2-611-1-1 0 2-611-1-2 2 2-611-1-3 4/F3 2-611-1-4 0 2-611-1-5 0 2-611-1-6 4/F4 2-611-1-7 4/F4 2-611-1-8 2/F5 2-611-1-9 2/F1 2-611-1-10 4/F3 2-611-1-11 3/F1 2-611-1-12 -

4/F1 2-611-1-13 3/F2 2-611-1-14 3 2-611-1-16 0 2-611-1-17 1 2-611-1-18 5 2-611-1-19 4/F1 2-611-1-20 0 2-611-1-21 5/F2 2-611-1-22 3/F2 2-611-1-23 5/F1 2-611-1-24 4/F1 2-611-1-25 0 2-611-1-26 0 2-611-1-27 0

2-611-1-28 3/F2 2-611-1-29 3/F2 2-611-1-30 2/B1 2-611-1-31 1/B1 2-611-1-32 0 2-611-1-34 0 2-611-1-35 0 2-611-1-36 5 2-611-1-37 4/F3 (Sub 6 also provided for clarity)

Revision 8 7/82

e l t Ske tch Rev 2-611-1-40 Superseded by 2-611-1-50 2-611-1-41 0 2-611-1-42 1/B0 2-611-1-43 0 2-611-1-44 0

! 2-611-1-45 0 2-611-1-46 3 l 2-611-1-47 1/F1 l 2-611-1-48 2/B0 2-611-1-50 0 2-611-1-100 Superseded by 2-611-1-2

3. Piping Design Specifications

a. 7220-M-321(0), Rev 0, Design Specification for i i

Nuclear Service Piping

b. 7220-M-345(Q), Rev 3, Design Specification for Component Supports for Nuclear Service Piping

c. 7220-M-481(0) Rev 20, Piping Class Sheets

d. 7220-M-480(Q), Rev 11, Piping Class Summary Sheets I

e. Summary of operating Conditions  ;

f. 7220-M-484(0), Rev 5, Pipe Insulation Schedule [

9 Reactor Coolant System Transient (B&W Specifica- I tion 18-1092 000012.04) '

4. Valve Weights and Center of Gravity Westinghouse Electric Corporation Drawings:

a. E-1165E45, Rev 7, Motor Operated Gate Valve (Bechtel Vendor Print 7220-M123A-38-5)

b. D-5058D90, Rev 5, Swing Check Valve (Bechtel Vendor Print 7220-M123A-43-4)

c. D-5058D91, Rev 6, Swing Check Valve (Bechtel Vendor Print 7220-M123A-42-5) '

5. Appropriate Response Spectra i 7220-G-6(O), Rev 6, Bechtel Specification for Earthquake Resistance Design of Equipment Located in the Reactor Buildi ng 4

Revision 8 7/82 1

6. Appropriate Anchor Point Movements

a. B&W Functional Specification 86-1123597-00 (Interim revision to B&W Specification 18-1391000012-01).

Reactor Coolant System Displacements and Seismic Spectra, pages 2, 3, 9, 10, 11, 12, and 18-104,

b. B&W 20004(6-76), B&W Specification 18-1235000012-08, Reactor Coolant System Foundation and Nozzle Loadings

7. ETEb Request for additional information.

8. ETEC Request for additional information 3/29/82.

Supplement - Load Histograms

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