ML20213E632
| ML20213E632 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/21/1983 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0655, CON-WNP-655 NUDOCS 8310260404 | |
| Download: ML20213E632 (2) | |
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s DISTRIBUTION DMB PSRB Reading DHFS R/F SEP 21 1983 DLZiemann GRMazetis MAMcCoy MEMORANDUM FOR:
Voss A. Moore, Chief Human Factors Engineering Branch Division of Human Factors Safety FROM:
Dennis L. Ziemann, Chief Procedures and Systems Review Branch Division of Human Factors Safety
SUBJECT:
ACCEPTANCE REVIEW FOR WNP-2 SPDS SAFETY ANALYSIS REPORT
Reference:
Memorandum from V. Moore to 3 rent Clayton dated August 11, 1983 As you requested in Reference 1, the Procedures and Systems Review Branch has performed an acceptance review of the licensee's submittal (Safety Analysis Report) for the WNP-2 Safety Parameter Display System (Letter, G. Bouchey to A. Schwencer, dated July 1, 1983).
Although we find the content of the submittal dealing with the basis for the selection of SPDS parameters to be generally sufficient to initiate our review, one additional item identified in the enclosed Additional Infonnation Request is necessary to complete our review.
The PSRB review will cover only Section 3.0 of the submittal. The target date of October 7,1983, identified in Brent Clayton's memorandum to you dated August 12, 1983, will now be subject to the licensee's response to the request for additional information.
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Dennis L. Ziemann, Chief Procedures and Systems Review Branch Division of Human Factors Safety
Enclosure:
Additional Information Request cc w/ enclosure:
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f ADDITIONAL INFORMATION REQUEST WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 SAFETY PARAMETER DISPLAY SYSTEM The staff has reviewed the WNP-2 Safety Parameter Display System (SPDS)
Safety Analysis Report submitted by letter from G. D. Bouchey to A. Schwencer dated July 1, 1983.
To complete our review, we require that the following additional information be submitted to the NRC.
640.01 Define the operability status of the Safety Parameter t
(Section 3.1)
Display System (SPDS) during the refueling mode of reactor operation.
Justify the non-operability of i
any specific parameter display during this mode.
Only those needed parameters related to the operator's capability to determine the status of the safety functions presented in Supplement 1 to NUREG-0737 need be addressed.
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