ML17083B090

Comments on NRC Program to Address Concerns W/Thermal Hydraulic Behavior of B&W Plants During Transients & Accidents.Gerda & SRI-II Facilities as Now Proposed Will Be Inadequate to Address NRC Concerns

ML17083B090
Person / Time
Site:	Diablo Canyon
Issue date:	10/13/1982
From:	Shewmon P Advisory Committee on Reactor Safeguards
To:	Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML16340C989	List: ML16340C988 ML17083B087 ML17083B090
References
TASK-2.K.3.30, TASK-TM TAC-45859, NUDOCS 8212130305
Download: ML17083B090 (2)

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UNITEDSTA) iS NUCLEAR REGULATORY COMM1SSlON ADVISORYCOMMITTEE ON RE! CTOR SAF GUARDS WASHIMCTOh', D. C. 2+55 Octob r l3, l982=

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P

. Nr. hilliam 0; Dircks

-"='xecu ive Director for Operations U. S. Nuclear.¹gul atory Commission Vashington DC.20555

Dear Hr. Dircks:

S'UBJ C I '

ACRS CQ+aliEtx I S OH lBC PROG. A a

0 ADDR SS CONCERNS'ITH TH RYAN H"DR'.ULIC BEH" VIOR 0"-

BANCO"K '.HD MILCOX PLAN S DURING TR/;HSIEHTS AHD ACCIDEHTS

. 'uring its 270.h

. Yaeting, October 7-8,

1S82, the Advisory Committee on Reac or Saseguards met with the HRC Stafe and representatives of the Babcock and l,'ilcox (Bcl')

Owners Group to discuss HRC Staff conc ms regarding the dyna;i c thermal

.hyd raul ic behavior of BEM pl ants during transients and accidents, portico) arly small break loss of coolant accidents.

For'ome time; the HRC Staff has identified a

need f'r experi~iental data for investigation of specific plant phenomena and for assessment of analyti-cal calculations oa BSM plant response to transients and accidents.

Re-

cently, a Test Advisory Group composed of HRC Staff members and, representa-tiv 5 0

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.he BN Osa'ners Group wa"s formed to eval uate al ternati ves.'vail abl e for 'obtaining the desired test data.

Tn

&ners Group has proposed use of two. industry test

=facilities (GERDA and SRI-II) in response

.to. the HRC Staff's concerns.

Phile we support the cooperative effort between NRC and the (hners Group, it appears that the GERDA and SRI-II facilities as now.proposed will be in-adeouate to satisfact'orily address the hRC Staff concerns in'his rnatter.

Although he data o'b ained from these facilities.rray be useful, xe believe tha a

more adequate facility, simil ar to the aproposed Semi seal e NOD-5 configura ion, is necessary to 'ddress the major -operational questions.

of concern.

Me also wish to emphasize that the timely acquisition of such data and associated analyses are required in order that HRR-can make use of SEM plant acciden analyses confidently.

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Sin.cer ely, 2i30305 82i206 R

ADOCK 05000275 PDR SheaiaaiOn

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