ML19225C943
| ML19225C943 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/09/1979 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908030338 | |
| Download: ML19225C943 (10) | |
Text
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Meeting Summary for Point Beach Unit 2.
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@CPOR Local POR NRR Reading ORB 1 Reading H. Denton E. Case D. Eisenhut G. Zech W. Gammi.ll J. iiller L. Shao R. Vollmer W. Russell B. Grimes T. J. Carter T. Ippolito R. Reid A. Schwencer D. Ziemann V. Noonan P. Check G. Lainas G. Knighton Chief, Systematic Evaluation Bran:n Project Manager COR Licensing Assistant OELD OISE (3)
R. Fraley, ACRS (15)
Program Support Branch TERA J. R. Suchanan NRC Participants Mr. Bruce Churcnill, Escuire Shaw, Pi ttman, Potts and Troweridge 18C0 M Street, N.W.
Washington, D. C.
20036 Mr. Glen Reed, Manager Nuclear Power Division Point Beacn Nuclear P1 ant Wi sconsin Electric Power Company h
231 West Micnigan Street U
Milwaukee, Wisconsin 43201 D
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50-301 LICENSEE: Wisconsin Electric Power Company FACILITY: Point Beach Nuclear Plant, Unit No. 2
SUBJECT:
SUMMAdY OF MEETING HELD ON JULY 6,1979 TO DISCUSS FEECWATER LINE WELD REPAIRS On July 6,1979, the NRC staff met with representatives of Wisconsin Electric Power Company and others as indicated in Attachment 1 to discuss the repair of welds found on the feedwater lines inside containment on Point Beach Unit 2.
Highlights of the meeting are summarized below. ' e Attachment 2 for the meeting agenda.
On July 2,1979, the feedwater line welds inside containment at Point Beach Unit 2 were inspected by radiography (RT). Some ul tra-sonic examination was also performed (UT). All welds were examined between the steam generator feedwater nozzle and the first seismic restraint (both steam generator feedwater lines).
As a result of this inspection, shallow cracks, crack-like indications and linear indications were found on the welds for the 18" x 16" reducers and at the elbow welds.
In addition, the welds wnich join the 3" auxiliary feedwater lines to the 16" main feedwater lines had some evidence of poor workmanship (a shallow 1/4" hole). Some pitting was found in the steans generator nozzles.
The licensee has cut out both reducers and sent the "A" reducer to Southwest Research Institute (SWRI) for detailed metallurgical examination. See Attachment S for some photo-micrograons. Seth recucers will be replaced and rewelded per ANSI 331.1, using a consummable insert.
The root pass wil.1 be examined oy licuid penetrant.
The crack-like indications in the elbow welds are being removed by polishing. The worst occurred in the *A elbow, whicn was 77 mils deep.
The polishing operation reduced the thickness below minimum wall for the schedule 30 piping, but not below the miriimum required by the stress analysis.
The licensee has not decided whetner the wall thickness will be increased by welding or left as-is.
Justification for the final course of action on this item will be provided.
453 045 7908o30s37;
Meeting Summary for Point Beach Unit 2 The auxiliary feedwater line welds will be re-welded.
The pitting in the steam generator nozzles will be removed by buffing.
The largest indications were found on the IS" end of the "A" reducer where it joins the steam generator nozzle - 6" long and about 40 mils deep.
This was classified as a crack. Other indications were categorized as " crack-like" or " linear indications" Most of the indications were in the counter-bore region. The indications dis-covered at Point Beach Unit 2 were smali compared to other plants recently examined. The licensee will complete all repairs on or about July 11,1979. The licensee plans to inspect Unit 1 during the next planned outage for refueling wnich will commence about September 23, 1979.
The Point Beach units are base-loaded plants and have..ad relatively few shutdowns. Neither unit has a history of waterhammer inside co nta inment. There have been r.0 leaks or other adverse operating experience.
The piping system is flexible. Stress levels are fairly low, and well within code allowables.
In 1974, the feedwater chemistry control was changed from coordinated phosphate treatment to all-volatile treatment. The steam generators are sludge-lanced each refueling.
There are about 40 tubesplugged (total for both steam generators ).
During hot standby, the steam generators are fed continuously, as opposed to on-off feeding which could cause cyclic thermal stresses.
At the conclusica of the meeting, the NRC :taff stated that the actions being taken by the licensee were acceptable for restart of Unit 2 provided that the following are accomplished prior to start-up:
1.
The licensee should submit a report documenting and summari:ing the inspection and repair, including the results of a 10 CFR 50.59 determination as to whether any unreviewed safety cuestion has been introduced by the repairs.
The report should include:
a.
the nature and extent of cracking, b.
an interim metallurgical evaluation; modes of failure, c.
a summary of tne stress analysis,
d.
feedwater chemistry information, e.
corrective actions taken,
'. a safety evaluation, including juscification for the operation of Unit I somewhat beyond the 90-day inspection deadline called for in IE Bulletin 79-13 (based on conditions found in Unit 2).
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Meeting Summ?ry for Point Beach Unit 2 2.
RT of the reducer welds should be conducted after post-weld heat treatment.
3.
A baseline RT and UT should be obtained.
4 The licensee should provide a commitment to conduct an RT and UT inspection of the reducer welds at the next refueling outage (Spring 1980).
In addition to the above, the staff requested that the licensee provide a copy of the final metallurgical recort when completed.
Based on the conditions found on Unit 2, the staff had no objection to the continued operation of Unit I pending inspection in September 1979. The licensee pointed out that IE Bulletin 79-13 called for an inspection of Unit 1 by September 23, but that the refueling outage for that unit was scheduled to start September 28, 1979. The staff had no objection to this relatively small (about 5 days) extension of time in which to inspect.
No special instrumentation of the feedline at Point Beach is warranted at this time.
CAe4 M /t d Charles M. Trammell, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments :
1.
List of Attendees 2.
Agenda 3.
Photomicrograchs g~,
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ATTACHMENT 1 LIST OF ATTENDEES POINT BEACH UNIT 2 JULY 6,1979 Wisconsin Electric Power Comoany Douglas Dill C. W. (Bud) Fay Bechtel Suresh Chitnis Paul Herbert Southwest Research Insitute Arthur Bursle Samuel Wenk Andy Pickett Shaw, Pitt: nan, Potts and Trowbridge Bruce Churchill NRC Charles Traccell Ed Jordan Pacer Woodruff Ray Klecker 3cb Hermann Tad Marsh Gary Zech g "L:7 048
hAC >&h h Agenda for Wisconsin Electric /NRC Meeting of July 6, 1979 n,V muu n.v
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.a POINT 3EACH NCC'IAR PLidiT 1.
Criginal Piping System Layout and Stress Analysis / Wisconsin Eleenric and Sechtel 2.
Cperating History /Wiscensin Electric 3.
Results of Recent Inspection /SwRI 4.
Preliminary Metallurgical Examination Results/SwRI 5.
Wisconsin Electric's Respense tc Bulletin 79-13/
Wiscensin Electric 6.
Discussion /All Attendees:
Wisconsin Electric NRC Mr.
C.W.
(Sud) Fay Mr. 3ruce Churchill Mr. Ocuglas Dill Sechtal Mr. Suresh Chitnis Mr. Paul Herbert Southwest Research Institute Dr. Arthur J. Sursic Mr. Samuel A. Wenk Mr. Andy Pickett dry 1 43 If)
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