ML20153B183

Forwards Questions 440.245 & 440.249 from NRC 880302 Request for Addl Info Re Reactor Sys Aspects of RESAR SP/90 Design. Response Requested within 30 Days

ML20153B183
Person / Time
Site:	05000601
Issue date:	03/15/1988
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 8803210445
Download: ML20153B183 (4)

Text

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1 March 15,1988 Docket No. 50-601

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fir. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporatior.

Water Reactor Division Box 355 Pittsburg, PA 15230 Dear ifr. Johnson

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 By letter dated March 2,1988, I transmitted a request for addittenal information pertaining questions (Qto the reactor systers aspects of the design of RESAR SP/90.

440.245 and Q 440.249) 1ad been intentionally left blank Two Attached are those questions. .

Accordingly, I request you respond to this rcouest within 30 days of the date of this letter. If you have any questions regarding this natter, call me at (301) 492-1120.

Sincerely, nrw1wa utunni b:s Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

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%,...../ March 15, 1988 Decket No. 50-601 Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburg, PA 15230 Dear Mr. Johnson

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 By letter dated March 2, 1988, I transmitted a request for additional information '

to the reactor systems aspects of the design of RESAR SP/90. Two pertaining questions (Q 440.245 and Q 440.249) had been intentionally left blank.

Attached are those questions.

Accordingly, I request you respond to this request within 30 days of the date of this letter. If you have any questions regarding this matter, call me at (301) 492-1120.

Sincerely, b

Thom s J. Kenyo , Project Manager  ;

Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated ec: See next page

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! RESAR-SP/90 Docket No. 50-601  ;

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Attention: Dr. Robert Bari .

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REQUEST FOR ADDITIONAL INFORMATION RESAR SP/90 1

440.245 (Volume 1. Section 3.3.2/ Module 2. Section 3)

These sections discuss TMI issues relative to RESAR SP/90. However, not all of the THI issues documented in NUREGs-0660/0737 are discussed. Address the following TMI issues as they pertain to the RESAR SP/90 desipn:

I.G.1 - Training during low-power testing II.K.1.5 - Review of ESF valves

, II.K.1.10 - Operability Status II.K.3.2 - Report on PORY failures II.K.3.3 - Reporting SV & RV failures /cha11anges ,

II.K.3.7 - Evaluation of PORY opening probability

II.K.3.12 - Anticipatory trip on turbine trip II.K.3.17 - ECCS outages ,

II.K.3.30 - SB LOCA methodology II.K.3.31 - Cog 11ance with 10 CFR 50.46 i

440.249 (Module 13)

Provide the interface requirements for the following systems:

1 a. Essential Service Water System (ESWS) (Page 9.2-3) ,

Specify the interface requirements for the Class 1E power l

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< supplies for the ESWS. ,

2 b. Ultimate Heat Sink (UHS) (Page 9.2-17) i Specify the interface requirements for the VHS. Consideration l should be given to compliance of the interface requirements 1 i with GDC 1, 2, 3 and 4.

c. Compressed Air System (Page 9.3-1) 4 Specify the interface requirements for the safety-related air accumulators that are to supply safety-related air operated valves.

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