ML20153B183

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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 (Qto the reactor systers aspects of the design of RESAR SP/90.

Two questions 440.245 and Q 440.249) 1ad been intentionally left blank 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:

As stated cc: See next page Distribution:

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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 (Q 440.245 and Q 440.249) had been intentionally left blank.

questions 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 1

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cc: Brookhaven National Laboratory i

Building 130 Upton, New York 11973 Attention: Dr. Robert Bari I

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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 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 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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