ML20235Z168

Summarizes ACRS 330th Meeting on 871008-10 Re Rept from Subcommittee on Auxiliary Sys Re HVAC Sys Failures & Impact on Safety Sys.Recommends NRC Examine Extent to Which Problem May Be Generic & Take Corrective Actions

ML20235Z168
Person / Time
Issue date:	10/15/1987
From:	Kerr W Advisory Committee on Reactor Safeguards
To:	Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML20235Z171	List: ML20235Z168 ML20245B661 ML20245B664
References
ACRS-R-1278, NUDOCS 8710210001
Download: ML20235Z168 (2)

Text

-- . _ - _ _ .

js "

1 I

u UNITED STATES

!@ Mo o

'g l 8" -

o NUCLEAR REGULATORY COMMISSION

$ ADVISORY COMMITTEE ON REACTOR SAFEGUARDS-

$ WASHINGTON, D, C 20555 O, ,

J

+9 4**** October 15, 1987 J 1

Mr. Victor Stello, Jr. '

Executive Director for Operations -

U.S. Nuclear Regulatory Connission ~

Washington, D.C. 20555 ]

SUBJECT:

. ACRS COMMENTS ON NUCLEAR POWER PLANT AIR COOLING SYSTEMS During the 330th meeting of the ACRS, October _8-10,1987, we discussed a.

report from our Subcommittee on Auxiliary Systems regarding heating, venti-- -l j

lating, and air conditioning system failures and their impact- on safety systems. This matter was discussed;on June 27, 1986 during a joint meeting l of the ACRS Subcommittees on Occupational and Environmental . Protection Systems and on Auxiliary Systems. It was also discussed by the Auxiliary Systems Subcommittee during a. meeting held on October 1,1987. The Subcom-mittees had the benefit of discussions-with representatives of the Office of  !

Nuclear Reactor Regulation and the document referenced.

I During the June 27, 1986 meeting, representatives of the NRC Staff stated  ;

that failures of air cooling systems for areas housing key components (for i l

example, RHR pumps, switch gear, diesel generators, etc.) 'in certain nuclear ' W power plants contribute significantly to estimated core-melt frequencies. I Because corrective measures are often taken once potential cooling ~ system i failures are identified, the impact of these potential failures on the proper j functioning of these systems has not been reflected in the final PRAs issued 1 for these plants. As a result, some members of the LNRC ' Staff and some i licensees whose plants have similar deficiencies may not be aware of these l problems.

J Based on these observations, we recommend that the NRC Staff examine the i extent to which these problems may be generic and take any corrective actions deemed necessary. ,

Sincerely,  !

~ William Kerr- 6 Chairman 6J/0 74 00*I Xh  ;

-_a__- _ _ _ _ _ _ _ - - _

.- ____=,:___ _ _ _ _ . _ _ _ - _ _ _ . L_

< , o y ,

y .,-

i

j..

q U

Mr. Victor Stello,'Jr, , . Octobsr 15,.1987 1

t 1 l

Reference:

i

l. Presentation ,naterial p'rovided by Arthur Busiik, Office- of . Nuclear Reactor : i Regulation, before a joint meeting on June 27, 1986 of the ACRS Subcommittees on Occupational and Environmental' Protection- Systems .and- on Auxiliary' Sys-tems, i

)

l I

, .1

.i j

.j I

l d 1

1

.q I

i

-l I

W 1

.}

~

l , 4;

_=__-_n___--_____-_-__-_. ,

. - . O