ML20249C471
| ML20249C471 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/24/1998 |
| From: | Wen P NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9806300087 | |
| Download: ML20249C471 (32) | |
Text
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June 24, 1998' MEMORANDUM TO: Thomas H. Essig, Acting Chief
. Generic lasues and Environmental Projects Branch Division of Reactor Program Management Omce of Nuclear Reactor Regulation
= FROM:'
Peter C. , Wen, Project Manager Generic issues and Environment C. M[l ro cts Branch
. Division of Reactor Program Management .
Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF JUNE 11,1998, MEETING WITH WESTINGHOUSE .
OWNERS GROUP (WOG) REGARDING PART LENGTH CONTROL ROD DRIVE MECHANISM (CRDM) ISSUES .
' OrEJune 11,1998, a public meeting was held at the U.S. Nuclear Regulatory Commission's .
(NRC's) offices in Rockville, Maryland, between members of the WOG, Westinghouse, and NRC
, ~j staff. Attachment i lists attendees at the meeting, and Attachment 2 contains a copy of the
. material presented at the meeting.
The purpose of the' meeting was to continue discussion of activities by WOG on part length CRDM issues;;This is a follow-up meeting to a previous NRC/WOG meeting held on May 7,1998; l jThe WOG representative started the meeting by presenting the status of the WOG subgroup s , f program and achons performed since the May 7,1998 rneeting. Since the part length CRDM 4
- ' leak event occurred at Prairie.lsland Unit 2 on January 23,1998, WOG has inspected 78 welds
, on part length CRDMs; these include 54 (out of total population of 284) of Type 309 stainless
,em ! steel (309-SS) welds and 24 (out of total population'of 128 welds) of alloy-82 welds. Other than v the one failed at Prairie Island Unit 2, no flaw was identified during these inspections. Additional it 4 <
l:J1: (^ inspection of 48 welds on 309-SS and 18 welds on alloy-82 is planned.
,q j-i 1.f 1 The WOG also' presented the process and the result ofits fabrication records review. They ' '
t1 4 concluded that the fabrication process has no pattem with respect _to welders, inspectors, and fabrication date. They believe that the Prairie Island flaw was an isolated event.
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y, , Westinghouse representative presented the safety assessment of part length CRDM
- issue from both' deterministic and probabilistic points of view. '
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.T. Essig -2 June 24, 1998 Deterministic - ,
On the basis of the weld inspection and the fabrication records review performed so far, the WOG believes that the Prairie Island flaw was an isolated instance and it is not likely a significant flaw exists et other WOG sites. A statistical justification that with 95 percent confidence 95 percent of welds would not have flaws of interest was presented to the staff at May 7,1998 meeting.
Assuming a significant flaw due to inadequate fabrication did exist, a load from plant operation would likely cause it to leak before breaking. This leak would likely be detected during normal plant surveillance prior to breaking.
In the unlikely event that it did break, a medium loss-of-coolant accident (LOCA),
with 2 inches to 6 inches break, would occur. Because of the location of the postulated break, no safety equipment that is required to respond would be affected. Therefore, the event is bounded by the existing safety analyses.
Probabdistic -
. Based on the following assumptions:
The probability for a significant flaw not previously identified to exist is 0.05. This value is derived from the 95/95 confidence level.
The frequency for an abnormal eveilt which could result in excessive load causing the flaw to break is 1E-05 to 1E-03/ year.
The conditional core damage probability (CCDP) based on generic medium LOCA is 1E-04 to 1E-02.
The estimated core damage frequency (CDF) is SE-07/ year (in the range of
! 1E-10/ year to 1E-06/ year.) This estimated CDF is comparable to a value indicated in Reg Guide 1.174,"An Approach for Using Probabilistic Risk Assessment in Risk-informed Decision on Plant-Specific Changes to the Current Licensing Basis," and is deemed to be small.
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- Based on the above assessment and in the interest of minimizing radiation exposure to the plant personnel, the WOG concluded that if no further unacceptable flaw is identified in the planned inspection, the WOG subgroup is planning to close this part length CRDM issue.
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T. Essig - June 24, 1998 The NRC staff stated that it was not amenable to this assessment because the criterion of 95 percent confidence that 95 percent of the welds would not have flaws of interest does not provide acceptable assurance of reactor pressure boundary integrity. The staff indicated that it would review the statistical and risk information and discuss the results of its review with management.
Attachments: As stated cc w/atts: See next page i
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'5 T. Essig 3- June 24,'1998 The NRC staff stated that it was not amenabic to this assessment because the criterion of 95 percent confidence that 95 percent of the welds would not have flaws ofinterest does not provide acceptable assurance of reactor pressure boundary integrity. The staff indicated that it would review the statistical and risk information and discuss the results of its review with management.
Attachments: As stated cc w/atts: See next page DISTRIBUTION See attached page
- See Previous Concurrence j
- Document Name: g:\pxq\msum0611.wog /
OFFICE PM:PGEB:DRPM (A)BC:EMCB SC:PkBg NAME PWen:sw -pcy TSullivan* FM'icz DATE 60#98 6/24'/98 669N8 OFFICIAL OFFICE COPY l
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~
l NRC/WOG MEETING ON PART LENGTH C.TY. ISSUES LIST OF ATTENDEES June 11,1998 NAME ORGANIZATION I Ted Sullivan NRR/EMCB Robert Hermann NRR/EMCB Keith Wichman NRRIEMCB Darl Hood . NRR/PDI-1 Peter Wen NRR/PGEB Ted Huminski CP&L/WOG Mike Schoppman FP&L Dick Labott PSE&G Phil Lindberg WPSC Bruce MicKatavage AEP Jim Benneth . Va Power Larry Methews SNC Kare Jacobs NY Power Authority Terry Woods TVA David Cambell {
Westinghouse Nancy Closky Westinghouse Warren Bamford Westinghouse l
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l .; ; Westinghouse Owners Group -
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Mr. Nicholas .Liparulo, Manager- ,
Regulatory s'nd Engineering Networks
- Westinghouse Electric Corporation ,
Mail Stop ECE 4-15 P.O. Box 355 Pittsburgh, PA 15230-0355 Mr. Andrew Drake, Project Manager Westinghouse Owners Group Westinghouse Electric Corporation Mail Stop ECE 5-16 .
- P.O. Box 355-Pittsburgh, PA 15230-0355 J'ack Bastin, Director Westinghouse Electric Corporation
' 11921 Rockville Pike, Suite 107 Rockville, MD 20852 Mr. Hank Sepp ;
Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA - 15230-0355 j:
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