ML17277B020

Forwards Addl Info Requested in 831027 Telcon Re Procedural Requirements for post-accident Sampling Per TMI Action Item II.F.1.2.Addl Info Will Be Reflected in Next Amend to FSAR

ML17277B020
Person / Time
Site:	Columbia
Issue date:	11/04/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
TASK-2.F.1, TASK-TM GO2-83-1022, NUDOCS 8311160067
Download: ML17277B020 (6)

Text

REGULATORY PORMATION DISTRIBUTION SYM (RIBS)

ACCEAION NBR:0311160067 DOC ~ DATE: 83/11/00 NOTARIZED; NO DOCKET FACIL:50-307 WPPSS Nuclear Projects Uni,t 2i Washington Public Powe 05000397 AUTH,NAME AUTHOR AFFILIATION SVRENSENEGGC, Washington Public I'ower Supply System HECIP,NAME RECIPIENT AFFILIATION SCHtfENCERgA ~

Licens>ng Branch 2

SUBJECT:

Forwards addi info requested in 831027 telcon re-procedural requirements for post-accident sampling per TMI Action Item IL.F,1.2,Addi info will be reflected in next amend to FOAL DISTRIBUTION CODE:

B001S COPIES RECEIVED:LTR g

ENCL SI/E:

TITLE: Licensing Submittal:

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 November 4, 1983 G02-83-1022 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:

Hr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NUCLEAR PROJECT NO.

2 POST ACCIDENT SAMPLING SYSTEM

Reference:

Letter, G02-83-918, G.C. Sorensen (SS) to A. Schwencer (NRC),

"Post Accident Sampling and Analysis of Dissolved Gases",

dated October 13, 1983 A request was made by C. Hiller (NRC) in a telephone conversation on October 27, 1983, to include the mention of procedural requirements for post accident sampling in the Supply System response to TMI Item II.F.1.2.

Attached is the addition requested which will be reflected in the next amendment to the FSAR.

Very truly yours, G.

C.

orensen, Acting Manager Nuclear Safety and Regulatory Programs BP/jdb

Attachment:

As stated cc:

R Auluck -

NRC D Hoffman -

NRC WS Chin

- BPA A Toth NRC Site 83iii60067 83ii04 PDR ADOCK 05000397 A

PDR

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WNP-2 DREST NO.

2 9 Na r ch 1983 accept flow control devices which have the capa-bility of maintaining isokinetic conditions with variations in stack or duct design flow velocity of

+ 208

~

Further departure from the is'okinetic condition need not be considered in design.

Corrections for non-isokinetic sampling condi-

tions, as provided in Appendix C of ANSI 13

~ L-1969, may be considered or. an ad hoc basis

~

d.

Effluent streams which may contain air with entrained wat r, e.g., air ejector discharge, shall. have provisions to ensure that the absorber is not degraded while providing a representative sample, e.g.,

heaters.

WNP-2 Position A shielded low flow particulate/iodine sampLing system is being installed to monitor the post-accident, effLuent air from the reactor bui1.ding ventiLation exhaust.

The sample system consists of a shielded fi1.ter holder, a running time m ter, and a

low vol.urn>> positive displacement sample pump which draws a sample from the reactor building elevated release duct.

The sampLe is drawn through th>> parti=ulate and iodine fil.ter asp mbly zt a rat of about 0

~ L cfm and then returned to the release duct.

The pump i~ automatically star ted when the high-high level alarm on the associated noble gas monitor is acti vated.

The pump wil 1 c continue to run until manually reset.

The sample filter hol.der has a

quick-release allowing it to be remove3 and han tied with remote tools reducing any potential personnel exposure.

To protect personnel, a 2-inch thick Lead shield is posi-tioned around th fiLter holder.

This will reduce the dos rate to S mR/hr at, one foot from the filt r under worst post-ulated conditions following a reactor accident based on Tabl II.F.l-2, Design Basis Shielding Envelope.

The shielded sample assembly will be used on the reactor building because of potential Leakage from primary contain-ment into the'eactor building following a reactor ac ident 1.easing fission products from the core.

Particulate/iodine sampling of th other buildings'ra9waste and turbine) exhausts will be hand1.>>d by the normal ef fluent samplers w'nere the post-accident releas concentration is quite low ~

B. 2-41

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