ML14190A321
| ML14190A321 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/03/1979 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907300141 | |
| Download: ML14190A321 (19) | |
Text
Im ocket =No. 50-26 1 JL 1
LICENSEE: CAROLINA POWER AND LIGHT COMPANY FACILITY:
H. B. ROBINSON, UNIT NO. 2
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 29, 1979 WITH CAROLINA POWER AND LIGHT COMPANY TO DISCUSS FEEDWATER PIPING WELD CRACKS AND REPAIR PROGRAM On June 29,.1979, the NRC,staff.met with representatives of Carolina Power and Light Company.(CP&L) and others as indicated in Attachment I to discuss the cracks found in feedwater line welds at H. B. Robinson Unit No. 2. Highlights of the meeting are summarized below.
The chronology of events leading to the CP&L inspection is presented in, page 2-2. includes copies of all viewgraphs presented at the meeting.
Cracks were discovered (by radiography) in all three feedwater lines in' the 16"x18" reducer which joins the 16" feedwater piping to the 18" steam generator-feedwater nozzle. Cracks were found in the welds at the 18" end of the reducer (the reducer-to-nozzle weld).
No crabks were found at the 16" end.
See attachment 2 (p. 2-4) for a drawing of the feedwater line configuration.
The extent of cracking, is presented in Attachment 2 (pp.
2-5 through 2-11).
The -reducers, have been removed for metallurgical examination.
Samples have been sent to NRC.- All reducers are being replaced now.
The original welds at the 18" end of the reducer used backing rings.
The cracks consisted of circumfirential linear indications behind or near the backing ring.
Replacement reducers will, be welded with consumable inserts instead of a backing ring.
The longest indication was on the "A" steam generator:
12" long, about 3/4" deep.
In addition to cracking, some pitting corrosion was observed near-the thermal sleeves.. Some portions of the thermal sleeves have been cut out to repair these pits.
OPPICE SURNAME~
NRC FORM 318 (9-76) NRCM 0240
.S. GOVERNMENT PRINTING OFFICE: 197
- 265 - 769
Meeting Summary for H. B. Robinson Unit No. 2
-2 The "C" reducer was examined in detail.
Fatigue cracking and pitting corrosion were observed, along with oxide deposits, and some branching in shallow cracks..
Some residual stress.was evident.
The pipe moved about 1. 1/2" when the weld was cut..Maximum crack depths were:
A 113 mils 8
-750 mils C
750 mils The W analysis !did not identify any source of high-cycle fatigue, but a -possible harmonic between the steam generator and feidwater line may have existed. Spring supports (3 on each line) were off-scale (cold),
but -on-scale in the hot condition. -Chipped concrete wa's observed near the base plate support for one thermal restraint.
This is believed to have been caused by it being located too close to a steam line pene tration.
Nevertheless, the cause of the cracking has not been definitely esta blished. 'The pitting may be due to oxygen in the feedwater, fatigue cracking may be due to some unknown stress in the system.
There is no known history of feedline waterhammer at Robinson.
As corrective action, CP&L will use a consummable insert to eliminate crevices and stress risers.
The weld will have a generous radius; surface irregularities will be eliminated.
CP&L'will install instruments on two fedlines-to monitor.their dynamic response. Temperature,'pressure, acceleration, strain, and displacement will be measured at various locations between the steam generators and the containment penetrations.
CP&L stated that 10 more days would be needed to finish welding in the new reducers and install the special instrumentation.
Criticality is scheduled for about July 10.
Power operation would commence about July 13, following four days of the low power physics testing.
At the conclusion of the meeting, e told.CP&L that wve had no technical.
or safety problem"with respect to returning Robinson to service pro vided that repairs were completed as described at the meeting.'
BUltNAME*
S.DA T E NRC FORM 318 (9-76)
NRCM 0240 a.S GOVERNMENT PRINTING oPICE: 1978 - 265 - 769'!
Meeting-Summary for Robinson Unit No. 2
-3 We recommended that either the welds be heat-treated immediately following welding without a. cooldown after welding, or that final UT/RT examinations be made after post-weld heat treatment.
The; staff requested that CP&L submit a summary of the information furnished at the meeting (including a description of-the test
-instruments) and/ there plans for reporting the results of the special instrumentation.program to NRC in the future.
CP&L stated that they would do so by Friday, July 6.
C. M. Trammell, Project Manager Operating Reactors Branch #1 iDivision of Operating Reactors Attachments:
- 1. List of Attendees
- 2. Meeting Viewgraphs cc: w/attachments See next page.
FFICE11.
M ammel/j NRC...ORM.318
.976 NRCM024 I..NI.t....NGO.IC:9 MRC NORM 318 (91-76)
NRCM 0240
.S: GOVERNMENT.PRINTING OFFIC!E: 197 6
9~7
Ok REG&i4 0
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-261 JUL. 3 1979 LICENSEE:
CAROLINA POWER AND LIGHT COMPANY FACILITY: H. B. ROBINSON, UNIT NO. 2
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 29, 1979 WITH CAROLINA POWER AND LIGHT COMPANY TO DISCUSS FEEDWATER PIPING WELD CRACKS AND REPAIR PROGRAM On June 29, 1979, the NRC staff met with representatives of Carolina Power and Light Company (CP&L) and others as indicated in Attachment 1 to discuss the cracks found in feedwater line welds at H. B. Robinson Unit No. 2. Highlights of the meeting are summarized below.
The chronology of events leading to the CP&L inspection is presented in, page 2-2. Attachment 2 includes copies of all viewgraphs presented at the meeting.
Cracks were discovered (by radiography) in all three feedwater lines in the 16"x18" reducer which joins the 16" feedwater piping to the 18" steam generator feedwater nozzle. Cracks were found in the welds at the 18" end of the reducer (the reducer-to-nozzle weld).
No cracks were found at the 16" end.
See attachment 2 (p. 2-4) for a drawing of the feedwater line configuration. The extent of cracking is presented in Attachment 2 (pp. 2-5;through 2-11).
The reducers have been removed for metallurgical examination. Samples have been sent to NRC.
All reducers are being replaced now.
The original welds at the 18" end of the reducer used backing rings.
The cracks consisted of cir'cumferential linear indications behind or near the backing ring.
Replacement reducers will be welded with consummable inserts instead of backing rings.
The longest indication was on the "A" steam generator:
12" long, about 3/4" deep. In addition to dracking, some pitting corrosion was observed near the thermal sleeves. Some portions of the thermal sleeves have been cut out to repair these pits
Meeting Summary for H. B. Robinson Unit No. 2
-2 The "C" reducer was examined in detail.
Fatigue cracking and pitting corrosion were observed, along with oxide deposits, and some branching in shallow cracks.
Some residual stress was evident.
The pipe moved about 1 1/2" when the weld was cut.
Maximum crack depths were:
A 113 mils B
750 mils C
750 mils The W analysis did not identify any source of high-cycle fatigue, but a possible harmonic between the steam generator and feedwater line may have existed. Spring supports (3 on each line) were off-scale (cold),
but on-scale in the hot condition.
Chipped concrete was observed near thebase plate support for one thermal restraint. This is believed to have been caused by it being located too close to a steam line pene tration.
Nevertheless, the cause of the cracking has not been definitely esta blished. The pitting may be due to oxygen in the feedwater; fatigue cracking may be due to some unknown stress in the system. There is no known history of feedline waterhammer at Robinson.
As corrective action, CP&L will use a consummable insert to eliminate crevices and stress risers. The weld will have a generous radius; surface irregularities will be eliminated.
CP&L will install instruments on two feedlines to monitor their dynamic response. Temperature, pressure, acceleration, strain, and displacement will be measured at various locations between the steam generators and the containment penetrations.
CP&L stated that 10 more days would be needed to finish welding in the new reducers and install the special instrumentation. Criticality is scheduled for about July 10.
Power operation would commence about July 13, following four days of the low power physics testing.
At the conclusion of the meeting, we told CP&L that we had no technical or safety problem with respect to returning Robinson to service pro vided that repairs were completed as described at the meeting.
Meeting Summary for Robinson Unit No. 2
-3
- We recommended that either the welds be heat-treated immediately following welding without a cooldown after welding, or that final UT/RT examinations be made after post-weld heat treatment.
The staff requested that CP&L submit a summary of the infomation furnished at the meeting (including a description of the test instruments) and their plans for reporting the results of the special instrumentation program to NRC in the future. CP&L stated that they would do so by Friday, July 6.
C. M. Trammell, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments:
1..List of Attendees
- 2. Meeting Viewgraphs cc:
w/attachments See next page
Meeting Summary for H.
Robinson Unit 2 Docket Files Dr. A. Dixon Callihan NRC PDR Union Carbide Corporation Local PDR P. 0. Box Y ORB1 Reading Oak Ridge, Tennessee 37830 NRR Reading H. Denton Dr. Richard F. Cole E. Case Atomic Safety and Licensing Board V. Stello U. S. Nuclear Regulatory Commission D. Eisenhut Washington, D. C. 20555 B. Grimes R. Vollmer A. Schwencer D. Ziemann P. Check G. Lainas D. Davis B. Grimes T. Ippolito R. Reid V. Noonan G. Knighton D. Brinkman Project Manager OELD 0.l&E.(3.)
C. Parrish, ACRS (16)
NRC Participants J.
Buchanan TERA Licensee G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C. 20036 Hartsville Memorial Library Home and Fifth Avenues Hartsville, South Carolina 29550 John F. Wolf, Esquire, Chairman 3409 Shepherd Street Chevy Chase, Maryland 20015
ATTACHMENT 1 LIST OF ATTENDEES CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON MEETING JUNE 29, 1979 CP&L R. Hanford J. Curley W. Flanagan S. Zimmerman H. Banks R. Starkey, Jr.
S. Grant J. Sheppard Westinghouse T. Mager F. Loceff T. Campbell J. Smith D. Marburger R. Muth NRC C. Trammell R. Birkel H. Walker, ACRS D. Sellers E. Igne, ACRS W. Hazelton T. H. Lin R. Klecker G. Zech R. Hermann J. Collins Others L. McAvay, VEPCO S. Boone, Ebasco Services J. Weeks, BNL
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