ML19354D394

Responds to Generic Ltr 88-20,Suppl 1 Re Initiation of Individual Plant Exam for Severe Accident Vulnerabilities. Util Will Perform Level I PRA & Containment Performance Analysis for Plant.Major Milestones Provided

ML19354D394
Person / Time
Site:	Wolf Creek
Issue date:	10/31/1989
From:	Rhodes F WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-20, NUDOCS 8911080107
Download: ML19354D394 (4)

Text

. - _ . _ . . . _ .

7 U:. . L t ^, s a .

m , .. 1 g ,; . " ' w- y,  ;

1. V. .. .

l i

7't.

W$LF CREEK NUCLEAR OPERATING CORPORATION 1  :

Forrest i Rhodes October 31, 1989' l V

n  %% ET 89-0088 U. S. Nuclear Reg,ulatory Gaunission j ATTN: Document Control Desk '

Mail Station P1-137 Washington, D. C. 20555 .

,, 1

s. ,

Reference Letter deted November 23, 1989, Generic Letter 88-20, .

' Individual Plant Examination for Severe Accident ]

Vulnerabilities" j

Subject:

Docket No. 50-482: Response to Generic Lett J T-20,. .

Supplement No. 1: "

Initiation of the Indivis * 'lant j lH Examination for Severe Accident Vulnerabilitit i I

Gentlemen The purpose of this letter is to transmit. Wolf Creek Nuclear Operating i Corporetion's (WCNOC) response to Generic Letter 88-20, Supplement No. 1:- .i

" Initiation 'of the Individual Plant Examination for Severe Accident 3 Vulnerabilitier". The Reference requires tha performance of s' systematic

? . examination to identify any plant-specific vulnerabilities to severe l accidents and report the results to the Conunission.

Attachment 1 provides the proposed program fer completing the Individual l <. Plant Examinatien (IPE) for Wolf. Creek Generating Station and the schedule ll for submitting the results to the Coannission.

-If you have any questions concerning this matter, please c atact me or  !

Mr. O. L. Maynard of my staff. >

i Very truly yours.

A c _

8911080107 091031 Forrest T. Rhodes PDR ADOCK 05000482 p PNV Vice President Engineering & Technical Services FTR/aem ,

Attachment cc: B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a

~

R. D. Martin (NRC), w/a l D. V. Pickett (NRC), w/a pML P.0, Box 411/ Burlington, KS 66830 / P%ns: (316) 364 8831 I

' An Equal opporturvty Errgdoyer hWHe/ VET

.b* A w - -

• _ __  % e m ..s,-e--e.ss

-=re-v4*e -y-c w v s. ww-vw p ,_,w -w,we-,-wy rv- = + - +- 3,-wr ---*ry- **www-WWb"M

g -

a s ' g '.

+

.',. .s.,

, e-.

j

, i U ', \

STATE OP KAllSAS- ) I

) SS W COUllTY OP COPPKY )

]

Forrest T. Rhodeo, of lawful age, being first duly sworn upon oath says that l he is' Vice-President Engineering and Technical ' Services of Wolf Creek

, Nuolear Operating Corporation; that he has read the foregoing dooument and knows the content thereof; that he has executed that same for and on behalf i of said Corporation with full power and authority to do so; and that. the facts therein stated are ' t'ue and correct to the best of his knowledge, =

infomation and belief. .

f f

_4 Y By W -

Forrest T. Rhodes Vice-Prosident Engineerin6 and Technical Services v

SUBSCRIBED and sworn to before me this jD day of % 1989.

s.; C""$1.T

.Y/.,c.'oi.s*e g 4%% W Notary Public 1

% lit8 #,

~

.N o... . .. ..<., ,}p$ !

q,. .

Expiration Date

,M f /f b

(

1 i

h 4

C 'I fs~. ,'.

Ee;  :

. t vi h

e

'j7, e' l

, Attachment 1 to ET 89-0088  !

0 Page 1-of 2 f

L Response to Generic Letter 88-10, Supplement No. 1: ' Initiation [

i L

of the Individual Plant E===ination for Severe Accident Vulnerabilities' +

us, ,

Esassati i Identify the method and approach selected for performing the IPE.

Rannonant j Wolf Creek Nuclear Operating Corporation (WCNOC) will perform a Level I l Probabilistic Risk Assessment (PRA) plus a containment performance analysis' ',

for Wolf Creek Generating Station-(WCGS). The Individual Plant Examination

-(IPE) will use-current Level I PRA methods and inforsation. The containment  ;

performance analysis will. follow the general guidance given in Appendix 1 to '

Generic Letter C8-20.

7 The IPE will be performed by the Nuclear Safety Analysis organization with

_ support from the,0perations and Nuclear Plant Engineering organizations.-

WCNOC has contracted with Westinghouse Electric Company and its subsidiary,

• Fauske & As.ociates, Inc. to provide project oversight, training.. technology trantfer.. technical direction and review functions ~ . The documentation packages will be developed consistent with the requiremer*.s of 10 CFR 50, -

Appendix B. Currently. Union Electric and WCNOC intend to review each ,

others' documentation packages in order to ensure that no potential -i vulnerabilities are overlooked.

Reauest Describe th0 method to be used, if it has not been previously submitted for  :

staff review (the descript. ion may be reference).

Reenonses  :

WCNOC will utilize the methods provided in NUREG/CR-2300, "PRA Procedures Guide" and current PRA methods, as applicable, to determine the core damage  ;

The IPE will frequencies based on system and human-factor evaluations.

consider only internal initiating events (including internal flooding and loss-of-offsite power).- The PRA will be based on the plant design as of ,

January 1, 1989.

The coremelt analysis will be performed using faalt tree linking methods.

Both system level accident sequences and component / operator error level

^

cutsets will be quantified and dominant contributors will be identified and ranked.

. - __ , . . - - . . . . . , _ - . . _ . . . . . ~ _ - - - - - , -m ,- _ ,

E

[ ,;,

'- ]

g"g4 0 1

[

f

. c i l[' ' Attachment 1 to ET 89 0088  ;

Page 2 of 2

( >

[.

The containment performance analysis will be based on containment event trees relevsnt to WCGS and utilize the guidance provided in Generic Letter  ;

68-20 Appendix 1 and NUREG-1335. The IDCOR models incorporated into 'the  ;

. latest revision of MAAP 3.0B are the basic plant models that will be used i for the analysis. The parameter data needed will be consistent with the approach provided~in NUREG-1335, Appendix A.

l Raouest Identify' the allestones and schedules for performing the IPE and submitting the results to the.NRC.

Ressoase:

s.

2The IPE has been initiated for WCGS and is scheduled to be completed in September 1992 with the submittal of an IPE report providing the results of j the examination. The following are major milestones of the examinations

1. - Preliminary coremelt analysis completed June 1991-

2. Containment performance analysis completed December 1991

3. IPE report submitted to the NRC September '1992 E

v v

w- ,- -, ... .---.---.m- -,._.-4 _ _ . - - , _ , - , , -.