ML17292A860

Submits Response to Request for Addl Info Re Response Time Testing

ML17292A860
Person / Time
Site:	Columbia
Issue date:	05/14/1997
From:	Swank D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-97-097, GO2-97-97, NUDOCS 9705210296
Download: ML17292A860 (5)

Text

CATEGORY j.

REGULAT(O INFORMATION DISTRIBUTION%STEM (RIDE)

~+a'CCESSION DOC.DATE: 97/05/14 NOTARIZED: NO DOCKET g NBR:9705210296 FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME, AUTHOR AFFILIATION SWANK,B.A. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Submits response to request for addi info re response time testing.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA PD4-2 PD COLBURN,T INTERNAL: ACRS FILE CENT NRR/DE/ECGB/A NRR DE/EMCB NRR/DRCH/HICB NRR/DSSA/SPLB NRR/DSSA/SRXB NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: NOAC NRC PDR NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 993S2-0968 May 14, 1997 G02-97-097 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

WNP-2, OPERATOR LICENSE NO. NPF-21 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TIME TESTING

Reference:

Letter GO2-97-071, dated April 15, 1997, JV Parrish (SS) to NRC, "Response to Request for Additional Information Related to Response Time Testing" On 'May 8,'997, during'a phone call between the Supply System and members of the staff, TG Colburn requested that additional information be provided to support the review of the information provided in the reference. The issue concerned the response times of differential pressure switches installed in the Reactor Pressure System (RPS) and the Primary Containment Isolation (PCI) System. In RPS, the instrumention is used to detect reactor pressure vessel water level - low, to initiate a reactor scram. In the PCI system, the instrumentation is used to detect excessive steam line flow, to initiate the closing of the main steam isolation valves. The Barton Model 288A differential pressure switch is used in each application.

Although the same model is used in the two applications, there are required differences in the instruments due to the differences in the applications. In the RPS application, the range is 72-30 inches of water column and the bellows is 1 5/8 inches in diameter. To support the higher differential pressure range of -15 to 0 to 150 psid in the PCI application, the bellows diameter is 3/4 inch. In a phone call with Supply System staff, Barton confirmed that components with the larger bellows and the smaller differential pressure range respond at a slower rate than the components with the 'smaller'diaphragm. Although this information supports the test'"data submitted in the reference, Barton was not able to quantify the difference in rate that should be expected. I I,

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Page 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TIME TESTING Should you have any questions or desire additional information regarding this matter, please call me or W.A. Pfitzer at (509) 377-2419.

Respectfully, D. A. Swank Manager, Regulatory Affairs CC: EW Merschoff, NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office TG Colburn - NRR NRC Sr. Resident Inspector - 927N DL Williams - BPA / 399 PD Robinson - Winston & Strawn