ML20052H416
| ML20052H416 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Rancho Seco, 05000000 |
| Issue date: | 05/10/1982 |
| From: | De Agazio A, Deagazio A Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-48349, TAC-48384, NUDOCS 8205200360 | |
| Download: ML20052H416 (12) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ it%'o UNITED STATES + N NUCLEAR REGULATORY COMMISSION 5
- j WASHING TON, D. C. 20555 V W i ^ 332 Dockets Nos. 50-346 & 312 LICENSEES
- Toledo Edison Company, Sacramento Municipal Utility District f
FACILITIES: Davis-Besse 1, Rancho Seco i l
SUBJECT:
SUMMARY
OF THE APRIL 23, 1982 MEETING CONCERNING AUXILIARY l FEEDWATER HEADER DAMAG: IN CERTAIN B&W PLANTS On April 23, 1982 a mee;ing was held at the NRC offices in Bethesda, Maryland l te discuss damage to the auxiliary feedwater headers which has been discovered l at the Davis-Besse and Rancho Seco facilities. The meeting was attended by representatives from Toledo Edison Company, Sacramento Municipal Utility i District, Duke Power Company, Consumers Power Company, B&W, and NRC as shown in Enclosure 1. Not all B&W owner utilities were represented at the meeting. The absent utilities have steam generators with a different auxiliary feed-water design which is not subject to the particular damage discovered at ( Davis-Besse and Rancho Seco. The purpose of the meeting was to pmvide an I opportunity for the utilities to present up-to-date results from inspections of the steam generator and to discuss their action plan. The meeting agenda i is shown as Enclosure 2. Not all B&W owner licensees are affected by this problem, however, they are being kept infonned about the situation. With regard to the licensees who are affected and B&W, they are not ready to recommend a repair plan since the extent of the damage is still being assessed. The damage mechanism has not been determined and it is not known when the damage actually occurred. However, neither Toledo Edison or SMUD has any evidence that the auxiliary feedwater function has been impaired or its effectiveness diminished. I The damage was first discovered at the Davis-Besse facility when, during planned eddy current testing of the peripheral tubes, it was noticed that a number of indications coincided with the supports on the internal AFW header. A 16 inch access port in the shell of each steam generator was removed to allow visual inspection of the header region. The access port is located just below the header. (Refer to the figures in Enclosure 3 for location and arrangement.) The header is rectangular in cross section and encircles the tube bundle. It is totally supported by the steam shroud at eight locations by brackets and pins. A single tube connects the header to the AFW.feedwater inlet nozzle. This tube is slip fit into a hole in the outboard face of ' e header. The as fabricated clearance between the header and the tubes varies fmm 9/16 inch to 2 inches. The header size and shape was selected to minimize the interference with steam flow. g cn c 2llTD C %y gS%$[ob ? s% i tro/
. DB-1, RS The B&W plants which have this design are Davis-Besse, Rancho Seco, Oconee 3, Midland 1 & 2, and TMI-2 Earlier designs used an external feed ring with The internal seven shell penetrations but required numerous bolted connections. i header design was adopted to eliminate these bolted connections. At the time the design change was made no B&W plants were in operation. The damage discovered at Davis-Besse and at Rancho Seco is summarized in Enclosure 3. Because of the limited access (only one shell access port in the header Because of the limited zone) inspection has been accomplished with fiber optics. access and capability of fiber optics equipment, only about one nalf of tne neader has been inspected. Methods to extend inspection capability are being devised. (At the time of the meeting Oconee 3 was still operating but was scheduled to shut down and inspect its steam generators. Subsequent inspection in the week of May 3,1982 revealed header damage in both Oconee 3 steam generators.) The operational history of the plants reveals that Davis-Besse has had about 30 Davis-Besse experience AFW actuations, Rancho Seco about 20 and Oconee 3 about 10. includes 3 tests in which AFW was initiated to demonstrate natural circulation and ability to shutdown from outside the control room. A single actuation of AFW can actually entail numerous cycles as flow is varied for level control. B&W is retrieving records relating to the design to determine the design basis used. The affected licensees have organized a task force with the following members
- Jacque Lingenfelter, Toledo Edison-Chairman Robert Ihde, B&W Robert Gill, Duke Power Company Dave Perry, Consumers Pmger Company Bruce Strivers, SMUD The first meeting of the task force is scheduled for May 3,1982. By that time the results of the Oconee 3 inspection should be available.
In addition to the Generic Task Force each utility will organize its own action committees. The basic action plan is to first devise a method to allow inspection of the entire header to determine the current functional and structural capabilities. Based upon the inspection results, one or more methods of repair will be developed and evaluated. Finally, based upon the results of the evaluations for each plant a repair program will be selected. Each utility will evaluate the repair program to determine applicability to plant specific conditions. It is anticipated that it will be several weeks before the Task Force or the licensees will be able to provide substantial update on the situation. Based upon the limited information available it is speculated that additional down time to effect repairs at Davis-Besse is on the order of 2 to 4 months beyond scheduled restart of May 21, 1982. I
e DB-1, RS ; 4 1 Each licensee will keep the flRC infomed of developments.and should neet again g with the !!RC asffuture developments. warrant. t 1 C f qi.".':I Ei i A.11. De Agazio, Project !!anager Operating Reactors Branch f4 Division of Licensing
Enclosures:
1. theting Attendees 2. !!eeting Agenda 3. Sumary of Danage cc w/ enclosures: See next page 1 1 l l t [ I ORB #4:DL omet > surname).A...D..e....A 7 .S.n..o......:..c..b..* .h ..*....*.***.a........ DATE ) l I NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY usc % m i m. r
ORB #4:DL MEETING
SUMMARY
DISTRIBUTION Licensee:
- Copies also sent to those people on service (cc) list for subject plant (s).
06ckef File ((2> {'HRC'PDR-L PDR t ORB #4 Rdg TNovak JStolz Project Manager ~ Licensing Assistant-RIngram OELD Heltemes, AE0D IE SShowe (PWR) or CThayer (BWR), IE i Meeting Summary File-0RB#4 RFraley, ACRS-10 Program Support Branch-ORAB, Rm. 542 BGrimes, DEP SSchwartz, DEP SRamos, EPDB FPagano, EPLB Meeting Participants Fm. NRC: EGAdensam JKnight HCanter RLobel RJCook BNewlin HDenton H0rnstein NEconomos MPadovan DEisenhut ODParr DGarner JRajan JScinto PWagner KDWard o
1 AUXILIARY FEEDWATER HEADER DAMAGE APRIL 23, 1982 MEETING ATTENDEES NRC - BETHESDA, MD Toledo Edison Co. NRC R. P. Crouse E. G. Adensam, DL/LB#4 J. Lingenfelter H. Canter, SRI-Rancho Seco T. Murray R.: J. Cook, SRI-Midland T. J. Myers A. W. De Agazio, DL/0RB#4 H. Denton, NRR N. Economos, Reg. II SMUD D. Eisenhut, DL D. Garner, DL J. J. Mattimoe J. Knight, DE R. Lobel, DSI/ASB B. Newlin, PA T. M. Novak, DL B&W H. Ornstein, AEOD M. Padovan, DL/0RB#4 J. D. Brew
- 0. D. Parr, DSI/ASB J. Carlson J. Rajan, DE/MEB C. J. Domaleski J. Scinto, ELD R. H. Ihde J. Stolz, DL/0RB#4 D. E. Lee P. Wagner, DL/0RB#4 J. H. Taylor K. D. Ward, Reg. III/E0D G. J. Vames E. A. Womack Consumers Power Co.
Duke Power Co. T. J. Sullivan R. L. Gill J. F. Norris L i
MEETING AGEllDA APRIL 23, 1982 INTRODUCTION JOHN MATTIM0E 1 BACKGROUND OF INSPECTION DICK CROUSE
SUMMARY
OF INSPECTION RESULTS DOUG LEE
SUMMARY
OF INSPECTIOl1 RESULTS RANCHO SEC0 = B0B GILL OPERATIONAL PLANS ACTION PLAN UTILITIES UTILITIES OWNERS GROUP ORGANIZATION + h 4 l
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