ML20042C469

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Forwards Draft Responses to Concerns Identified in Draft SER Re Containment Sys.Responses Will Be Incorporated in Amend to FSAR
ML20042C469
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 03/22/1982
From: Davidson D
CLEVELAND ELECTRIC ILLUMINATING CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML20042C470 List:
References
NUDOCS 8203310427
Download: ML20042C469 (4)


Text

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THE CLEVELAND ELECTRIC ILLUM!N ATitlG COMPANY P o. BOX 5000 m CLEVELAND. oHlo 44101 e TELEPHONE (216) 622-9800 m ILLUMINATING BLDG- e 55 PUBLICSoVARE Dalwyn R. Davidson emng e Best Location in the Nation viCE PRESIDENT SYSTEM ENGINEf RING AND CONSTRUCTION g# /,g ,

Q^ , L March 22, 1982 . .g c..) .g \

c 8' Mr. A. Schwencer i , . n n n n 1982.7 -

"- " " " i ,..-cJ Chief, Licensing Branch No. 2 Division of Licensing 5 a d"I U. S. Nuclear Regulatory Commission S[

t tith [G Washington, D. C. 20555 V g,s

/7o, hp Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Response to Draft SER Containment Systems Branch

Dear Mr. Schwencer:

This letter and its attachment is submitted to provide draft responses to the concerns identified in the Draft SER for Containment Systems.

It is our intention to incorporate these responses in a subsequent amendment to our Final Safety Analysis Report.

Very Truly Yours, M

Dalwyn R. Davidson Vice President System Engineering and Construction DRD: mlb cc: Jay Silberg John Stefano Max Gildner 8203310427 820322 t k

PDR ADOCK 05000440

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l' . . .

480.31 The response to question 480.4 was inadequate. Provide the information requested regarding the subcompartment analysis, blowout panels, and the experimental data or test program to support the analysis. Also, provide the same information for the air seals in the reactor annulus region.

Response

The Pressure Relief Panels (blowout panels) for the RWCU Compartments are designed to use explosion release fasteners, approved, listed, and tested by Factory Mutual Research Corporation. The test program consisted of:

a. static fastener tension tests
b. small scale dynamic panel tests in fastener shear
c. small scale dynamic panel tests in fastener tension
d. large scale dynamic panel tests in fastener shear Based upon testing, it is concluded that the pressure relief panels meet their design criteria used in the subcompartment analysis and satisfy the criteria of the Standard Review Plan Section 6.2.1.2.II.3.

i The design basis and the summary of the Factory Mutual Research Corporation testing are attached.

Additionally, a summary of the air seals used in the reactor annulus region is attached.

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Perry Nuclear Power Plant Units 1 & 2 Pressure Relief Panels - RWCU Compartments DESIGN BASIS / CRITERIA

1. Release System - Explosion Release Fasteners tested, approved and listed by F.M. - June 21, 1971 Serial No. 20166.

Necked-down shank aluminum bolts by size group with

. average ultimate strength !15%.

2. Panel System - Single panel aluminum 2 '-6" x 5'-0" to 3 '-0" x 7'-1" in size. Alloy 3004-H14. Swinging and Fixed panels.
3. Framing System - ASTM A36 steel - primed with Carbozine ll.
4. Restraining System - Aircraf t restraining cables along 3'-0" and 5'-0" panel dimensions.
5. Maximum Blow-Out Pressure - 25 p.s.f. !15%

Range - 21.25 psf to 28.75 psf (<30 psf)

6. Maximum Panel Weight - 2.5 psf

D-101-053 - Reactor Bldg. Floor Plans - Unit 1 Elev. 654-0 c 661-7 4

D-151-053 - Reactor B1dg. Floor Plans - Unit 2 Elev. 654-0 & 661-7 4

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