ML20217E685
| ML20217E685 | |
| Person / Time | |
|---|---|
| Issue date: | 03/23/1998 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-694 NUDOCS 9803310115 | |
| Download: ML20217E685 (82) | |
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UNITED STATES y
j NUCLEAR REGULATORY COMMISSION '
WASHINGTON, D.C. 20066-0001
/g March 23, 1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Egan Y. Wang, Reactor System Engineer Generic issues and Environmental j
Projects Branch
' = = -
d Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING
SUMMARY
OF FEBRUARY 27,1998 WESTINGHOUSE OWNERS GROUP (WOG) REGULATORY RESPONSE GROUP (RRG)
REGARDING CRACKING IN PART LENGTH CONTROL ROD DRIVE HOUSING On February 27,1998, representatives of WOG RRG met with representatives of the Nuclear Regulatory Commission (NRC). Members of the public, Westinghouse and utility representatives were also present. The purpose of this meeting was to inform NRC of the present situation with respect to the part length control rod drive mechanism (CRDM) housing cracking issue and WOG RRG activities on the issue. Attachment 1 lists the meeting i
attendees. Attachment 2 is a copy of slides presented by WOG RRG.
On January 23,1998 reactor coolant system (RCS) leak rate showed an increase in unidentified Ir>akage at Prairie Island Unit 2 (Pl 2). The unidentified leak rate increased from less than 0.1 gallon per minute (gpm) to about 0.26 gpm. On January 24,1998, Prairie Island Unit 2 was taken to cold shut down due to an unisolable RCS leak (0.31 gpm, unidentified). On February 1,1998, PI 2 determined that the leak was from CRDM G9 above the canopy seal weld and notified the NRC in accordance with 10 CFR 50.72. On February 20,1998, during an NRC requested conference call with WOG, the NRC officia!/ requested the activation of the WOG RRG for generic safety consideration of the Prairie Isiand Unit 2 part length CRDM leak.
In a letter, dated February 20,1998, the WOG notified the NRC that the WOG RRG had been activated.
in a background ' discussion, WOG RRG stated that the part length CRDMs were originally intended for Xenon cor@i and are non-scrammable. Currently, there are 30 similar CRDMs
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installed in operating p p n and tMy only function as a pressure boundary.
. WOG RRG discussed in detail the fabrication and inspection sequence during the manufacturing process of part length CRDMs. The WOG RRG representatives stated that j
WOG RRG has reviewed the fabrication records and the initial focus was weld wire heat, j
welder, inspector, and repair weld records. The WOG RRG initiated a metallurgical j
investigation and root cause assessment. The preliminary results indicated that the cracking
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-2 March 23, 1998 was located in the 309 SST buttering at the 403 SST base metal interface. The cracking was initiated on the inside diameter (ID) surface and progressed radially outward. The cracking was circumferential and covers 360* around the circumference. The cracking was comprised of discontinuous segments connected with intergranular/ intercellular ligaments. The cracking depth varied from 65% to 100% depending on the circumferentiallocations. A circumferential through-wall crack of about 0.5 inches was observed at 190* clock location on the outside diameter (OD) surface where the leak occurred. The fracture face was covered with high j
temperature oxide all the way up to the OD where the leak occurred. No evidence of fresh fracture (or dimpled ligament) was observed at the leak location. The analysis of ID surface deposits showed no evidence of contaminants such as halogens. Chemistry analysis results confirmed the presence of residuals and low melting species such as copper, sulfur, and boron j
in the oxide layer on the fracture face. An ultrasonic testing (UT) examination of similar welds j
in the remaining CRDM motor tubes showed no indications of cracking. Metallographic j
examination of axial sections through similar welds in two other tubes at Prairie Island Unit 2 q
confirmed no cracks. The preliminary investigation findings suggested hot cracking as the likely j
mechanism. However, other mechanisms such as crack extension due to reheat cracking during post weld treatment, and the potential role of cold cracking along the untempered 1
martensite at the inte face are also being investigated, l
Based on the preliminary investigation, the WOG RRG has concluded that the cracking originated from weld fabrication, and that no evidence of additional growth during service could be identified. Another key factor that WOG RRG noted was that the part length CRDM passed two hydrostatic tests: at 3450 pound per square inch (psi) in a test at the shop and at 3105 psi in a field test. WOG RRG also discussed additional activities to establish root cause, including:
review of fabrication records, residual stress measurements, sectioning and metallography on additional welds to confirm evidence or lack of cracking, weld chemistry and dilution measurements by electron microprobe, and additional oxide deposit analyses to identify evidence of: any recent fracture at leak, and any recent service induced fracture of internal ligaments.
During the meeting WOG RRG presented preliminary structural integrity assessment findings of part length CRDM cracking and concluded that very large flaws can be present at the weld of interest, and ASME Section XI margins will be maintained. The safety assessment WOG RRG performed included several considerations: metallurgical / structure, reactivity insertion, foss of j
coolant accident (LOCA), jet impingement, pipe whip, and missile generation. Based on the information presented, WOG RRG concluded that the effects of the postulated failure of a part length CRDM pressure housing are bounded by plant accident analyses. In addition, WOG RRG discussed risk-informed safety assessment. WOG RRG indicated that there was a high probability that there will be a leak before break. Based on the information presented during the meeting, WOG RRG concluded that plants can continue to operate without adversely affecting public health and safety while this issue is being addressed.
j For the near term activities, WOG RRG planned to form a subgroup to further develop and
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implement an integrated plan to address this issue. WOG RRG had scheduled a meeting with affected licensees on Monday, March 2,1998. With reference to NRC concems (attached to i
T. Essig
-3 March 23, 1998 the letter dated February 20,1998), WOG RRG plans to submit a conditional assessment on March 6,1998. WOG RRG will continue communications with Prairie Island Unit 2 and other plants.
The NRC staff acknowledged the responsiveness of WOG RRG, considering the short period and the workload. NRC staff commented that the WOG RRG presented a lot of information during this meeting and that the staff needed more time to review all the information presented in the meeting. The NRC staff commented that the WOG RRG was encouraged to continue their current actions.
The NRC staff requested a letter from WOG RRG that documented the WOG RRG recommendations to plants owners including, compensatory measures, inspection and repair plans, and a schedule for each licensee to inform NRC of their plant specific plans. In addition, the staff requested a docketed letter from each affected licensee outlining their plans, including a schedule and licensee voluntary actions regarding this part length CRDM cracking issue. The staff encouraged continuous communications on the ongoing activities. The staff also encouraged licensees to monitor RCS leak rate closely. The staff commented that when licensees replace part length control rod drives, it would be beneficial if the removed CRDMs were examined.
Both the NRC staff and WOG RRG representatives agreed that more communications should occur once more information becomes available.
Attachments: As stated cc w/att: see next page Project No. 694 l
1 a-
T. Essig the letter dated February 20,1998), WOG RRG plans to submit a conditional assessment on March 6,1998. WOG RRG will continue communications with Prairie Island Unit 2 and other plants.
The NRC staff acknowledged the responsiveness of WOG RRG, considering the short period and the workload. NRC staff commented that the WOG RRG presented a lot of information during this meeting and that the staff needed more time to review all the information presented in the meeting. The NRC staff commented that the WOG RRG was encouraged to continue their current actions.
The NRC staff requested a letter from WOG RRG that documented the WOG RRG recommendations to plants owners including, compensatory measures, inspection and repair plans, and a schedule for each licensee to inform NRC of their plant specific plans. In addition, the staff requested a docketed letter from each affected licensee outlining their plans, including a schedule and licensee voluntary actions regarding this part length CRDM cracking issue. The staff encouraged continuous communications on the ongoing activities. The staff also encouraged licensees to monitor RCS leak rate closely. The staff commented that when licensees replace part length control rod drives, it would be beneficial if the removed CRDMs were examined.
Both the NRC staff and WOG RRG representatives agreed that more communications should occur once more information becomes available.
Attachments: As stated cc w/att: see next page Project No. 694 Document name: 980227MT. SUM
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NRC/ WESTINGHOUSE OWNERS GROUP MEETING LIST OF ATTENDEES Feb 27,1998 NAME ORGANIZATION Wetzel, A. Beth NRC/NRR/PDill-1 Wang, Egan NRC/NRR/PGEB Strosnider, Jack NRC/NRR/DE Tomes, A. Charles Wisconsin Public Service Crop Gilreath, Jeff Duke Power Jacobs, Karl New York Power Authority /WOG Borsum, Bob B&W Owners Group Schoppman, Mike Florida Power & light Co.
Long. Steve NRC/NRR/SPSB Li, Y. C. (Renee)
NRC/NRR/EMEB Carpenter, C. E.
NRC/NRR/EMCB Lund, Louise NRC/RES/EMMEB Bailey, Jack Tennessee Valley Authority Newton, Roger WEPCO/WOG Carpenter, Cynthia NRC/NRR/PDill-1 Bamford, Warren Westinghouse Hermann, Robert NRC/NRR Elder, Gary Westinghouse Satyam-Sharma, T American Electric Power Boyle, D. E.
Westinghouse Lainas, G. C.
NRC/NRR/DE Sullivan, E. J.
NRC/NRR/EMCB Walsh, Larry NAESCo./WOG Alexander, Donna CP&L/WOG Liberatori, Louis Consolidated Edison /WOG Closky, Nancy Westinghouse Galembush, John Westinghouse Bemis, Sumner Westinghouse Hornseth, Geoff NRC/NRR/EMCB Fridrchden, Jan Southern Nuclear /Farley Cozens, Kurt NEl Plantz, Joe WSI Cooper, Dick NSP-Pl Smith, Jim TVA/WOG Ormson, Len American Electric Power Chatterton, Muffet NRC/NRR/SRXB Benedict, Robert NRC/NRR/PECB Bastin, Jack Westinghouse Sepp, Hank Westinghouse Scott, Harold NRC/RES Shuaihi, Mahammed NRC/NRR/SRXB Dricks, Victor NRC/OPA Rao, Gutti Westinghouse Hughes, David PSE&G Lounsbury, David PSE&G/WOG ATTACHMENT 1
cc:
Mr. Nicholas Liparulo Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Hank Sepp Westinghouse Electric Corporation PO Box 355' Pittsburgh, PA 15230-0355 Mr. Andrew Drake WOG Project Manager Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Sumit Ray Westinghouse Electric Corporation
. PO Box 355 Pittsburgh, PA 15230-0355
i DOCUMENT COVER PAGE DOCUMENT NAME:
G:EYW\\980227MT. SUM
SUBJECT:
MEETING
SUMMARY
OF FEBRUARY 27,1998, WITH WESTINGHOUSE OWNERS GROUP.
ORIGINATOR:
Egan Wang SECRETARY:
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WESTINGHOUSE OWNERS GROUP / NRC MEETING Part Length CRDM CrackingIssue February 27,1998 8:30 Introduction RogerNewton, WEPCo Purpose ofMeeting WOG RRG Chairman Expect Outcome Chronology ofEvents Richard Lindsey, NSP WOGIRG/RRG Activities AddressingIssue RogerNewton Part Ingth CRDM Selected Design Aspects Dave Boyle, W Failure Investigation / Root Cause/ Status Gutti Rao, W I
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FAILURE PREDICTIONS FOR CONTINUOUS CIRCUMFERENTIAL FLAWS - PRAIRIE ISLAND PART LENGTH CRDMS : NORMAL / UPSET CONDITIONS 14,000
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FAILURE PREDICTIONS FOR THROUGH WALL FLAWS EXTENDING FROM CONTINUOUS CIRCUMFERENTIAL FLAWS (NORMAL / UPSET CONDITIONS)
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FAILURE MOMENT PREDICTIONS FOR A RANGE OF FLAWS FOR THE WOG PART LENGTH CRDM, EMERGENCY / FAULTED CONDITIONS 400 350 -
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