ML20246K172

From kanterella
Jump to navigation Jump to search
Comments on Preliminary Case Study Rept on Svc Water Sys Failure & Degradations in Lwrs.Making Svc Water Sys Inoperable Increased Core Melt Frequency by Factor of 100
ML20246K172
Person / Time
Issue date: 06/13/1989
From: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Novak T
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML19306D150 List:
References
NUDOCS 8907180083
Download: ML20246K172 (2)


Text

_-__

.r.*

P Enc]0sure 4

, h

- ~,4-~.

l t

JWi 131968 i

i" Thomas Novak., Director.

g MEWAANDUM FOR: Division for Analysis and Evaluation of Operational Data

./

6

~

}

~

J. Nelson Grece Regional Administrator FROM:

s REGION !! COMMENTS ON PRELIMINARY C WATER SYSTEM FAILURES AFD DEGRADAT10 o

4

$UBJECT:

REACTOR $

'I ability of sfrvice wattr i

l Region !! has been sensitive to tbtf issue of the vu ner On February 2, 1988.

systems to different types of degradation for some tim hangers to statermine w

j i..

l' operability to NRR for action.

h findings of ine service water inspections performeo in Region !! support t e s

i Review of the case study did not reveal My problems relat Some observations, based upon our the case study.

f the case study.

to the technical accuracy of.the report. inspection experienc E

r i l to problems Our inspectors found that the licensees have respoMed aggress v f

l are disecvered.

that have been identified at their sites.

monitor degradation are put in place shortly after prob ets W.

bl s not currently The licensees are not as' aggressive in searching for pro anRespons f

w.P l problems.

identification of identified at their sites.

programs for Nture monitoring of the potentiator period h

n The recommenostion m:

inopertble.

d apply problems prior to the head exchangers becomingi roposed by our draft bulletin, but the bulletin woul R, P.

i, to all safety relate Q,

water or not. '

d of your FRA W

Our regional review was able te supoort the ord lants with the m-SARA includes, in it:

I System Analysis and Risk Assessment (SARA) PC software. failure The NUFIG 1150 plants.

"4

]

database, the dominant sequences from the PRAs i

s were; water pumps to one or failing all service pump New

[

7.,

Original ig7rg, felt Frequency Core Melt Freoutncy u

M plant 2.476 E-2

[

1.54?E 4 3.288 E-3 Iton 3.011 E-S 2.288 E-3 I

Grand Gulf 2.457 E-5 2.166 E-3 Surry 8.579 E-5 1.705 E-4 5equoyah 8.394 E-6

~

f-

+

Peach Bottom r.

F Acti ' REG, b.q7WT A 04.'06/e9 13:3a p,

g 89071Mm3 e90707 PDR REVGF NRCCRGR MEETING 162 PDC

i l

v.*

. -l.;) 1..

l-

.~

l JUN 1 3 MS e

2 sl Thomas Novak "l

lt frequency Making the service water sy} stems inopereb3a increased the core m by a factor of 100 at the p s,nts.

directed to Rudy Bernhard at 4

Questions conceming our comments can tt

\\.

2; li 7T$ 242-0339.,

i 1

h t.Dnd i

k f;

J.. Nelson Grace Regicnal AcmGistrator

't

!?

t E. Leals. AE0Q cc:

M. Ernst. RI!

.1 A. Gibson. R1!

T L. Reyes RI!

A. Herdt. Rl!

F. Jape. RII R. Bernhard, Ri!

t s.

)

I

,f R

RII P

R RI!

RII ns f506/y/88 06/r /t 06//u/88 Id!'

mb n L7eges AHerdt

[Bembard:td F0s t....

06

/88 06/'s/83 t

06g /88 g,;

A.,

g ;.-

t1}:;

r s

8:~

5.,-

s i

j r

L

.i.'.d

  • ^

0 e

1

.t rF k8f1 'R E G. 2-A T L AN T A 02.'06/89 13:35 P.

3

.