ML19354D394
| 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) | |
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W$LF CREEK 1
NUCLEAR OPERATING CORPORATION Forrest i Rhodes October 31, 1989' V
ET 89-0088 n
U. S. Nuclear Reg,ulatory Gaunission j
ATTN: Document Control Desk Mail Station P1-137 Washington, D. C.
20555 1
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Reference Letter deted November 23, 1989, Generic Letter 88-20,
' Individual Plant Examination for Severe Accident
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Vulnerabilities" j
Subject:
Docket No. 50-482: Response to Generic Lett J T-20,.
lH Supplement No. 1:
Initiation of the Indivis
- 'lant j
Examination for Severe Accident Vulnerabilitit 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
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. examination to identify any plant-specific vulnerabilities to severe l
accidents and report the results to the Conunission. 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 PDR ADOCK 05000482 Forrest T. Rhodes p
PNV Vice President Engineering & Technical Services FTR/aem Attachment cc:
B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a
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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
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Forrest T. Rhodeo, of lawful age, being first duly sworn upon oath says that 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,
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infomation and belief.
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Forrest T. Rhodes Vice-Prosident Engineerin6 and Technical Services v
SUBSCRIBED and sworn to before me this jD day of % 1989.
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- , Attachment 1 to ET 89-0088 0
Page 1-of 2 f
L Response to Generic Letter 88-10, Supplement No. 1:
' Initiation
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i of the Individual Plant E===ination for Severe Accident Vulnerabilities'
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L 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 frequencies based on system and human-factor evaluations.
The IPE will 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
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cutsets will be quantified and dominant contributors will be identified and ranked.
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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
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