ML20236D905

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Forwards Safety Evaluation & Request for Addl Info Re Module 1,RESAR Section 6.5.4. Re Fracture Prevention of Containment Pressure Boundary.Module 4,Section 5.4.1.1 on Reactor Coolant Pump Flywheel Integrity Acceptable
ML20236D905
Person / Time
Site: 05000601
Issue date: 10/26/1987
From: Kenyon T
Office of Nuclear Reactor Regulation
To: Johnson W
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
Shared Package
ML20236D909 List:
References
NUDOCS 8710280406
Download: ML20236D905 (3)


Text

____ -

1 October-26, 1987 ~

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(Docket'No.50-601 Y

Mr W..-Jr Johnson

Nuclear Safety Department-Westinghouse ElectriciCorporation Water Reactor Division

. BOX 1355.

Pittsburgh,; Pennsylvania 15230

Dear Mr. Johnson,

j

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90
We h' ave reviewed Module 4, Section 5.4.1.1, Reactor Coolant Pumps (Flywheel j

Integrity).and.found this section to be' acceptable. Our. evaluation is

,provided;in Enclosure 1.-

L 0ur review of SRP Section 6.2.7 Fracture Prevention of Containment Pressure Boundary:(Module.I', RESAR Section 6.5.4) has determined that we need additional information to complete,the. review. Enclosure 2 provides our' 3

, request-for additional information.

.Also'in Enclosure 2:are' questions related to SRP Sections 4.5.1, 5.2.3, 7

5.4.2.1,.6.1.1, and 10.3.6.

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Please respond to this request within 90 days from the date of this letter.

i If you.have. any questions regarding this matter, please call me at (301)

..492-8206.

Sincerely, 1

i bd uh 6

W l

e Thomas d'. Kenyon, Projec anager Standardization and Non-Power Reactor j

Project Directorate Division'of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation Enclos'ure:

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..,,8 October 26, 1987 l

Docket.No. 50-601 Mr. W.lJ. Johnson Nuclear. Safety. Department i

Westinghouse Electric Corporation Water-Reactor Division BOX 355 Pittsburgh, Pennsylvania 15230 1

Dear Mr. Johnson,

j

SUBJECT:

. REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 We have reviewed Module 4, Section 5.4.1.1, Reactor Coolant Pumps (Flywheel Integrity) and found.this section to be acceptable.

Our evaluation is i

provided in Enclosure 1.

1 I

Our review of SRP Section 6.2.7 Fracture Prevention of Containment Pressure i

Boundary (Module 1, RESAR Section 6.5.4) has determined that we need l

' additional information to complete the review. Enclosure 2'provides our

'l req ues t. f o r ' a dd i tiona l i nforma ti on,

j Also in Enclosure 2 are questions related to SRP Sections 4.5.1, 5-2.3, 5.4.2.1,~6.1.1, and 10.3.6.

Please respond to this request within 90 days from the date of this-letter.

If you have any questions regarding this matter, please call me at (301).

492-8206.

Sincerely, j

Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate l

Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc:

See next page

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Docket No.1STN 50-601

.RESAR-SP/90.

.l cc:

Trevor-.Pratt-Brookhaven National Laboratory Building:130'

Upton, New York 11973 Mr.' William Schivley Westinghouse Electric Corporation-ECE-410 Mail Stop 4 Box.355 Pittsburgh, Pennsylvania ~ 15230-K

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