ML13319A741
| ML13319A741 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/22/1980 |
| From: | Nowicki S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010300156 | |
| Download: ML13319A741 (44) | |
Text
M KTIILS
SUMMARY
DISTRIBUTION Docki Loca PDR REGULATORY DOCKEI FILE COPY
'ocl DR ORB Reading NRR Reading HRDenton EGCase DEisenhut RPurple RTEdesco FNovak GLianas Jolshinski GZech JHeltemes, AEOd CThayer SVArga BClark TIppolito RReid Crutchfield SNowi cki OELD CI&E (3)
O!SD NRC Participants NSIC TERA AKCRS (16) 8o 10300 16 4
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 22, 1980 Docket No 50-206 LICENSEE:
Southern California Edison Company FACILITY:
San Onofre Unit No. 1
SUBJECT:
SUMMARY
OF JULY 31, 1980 MEETING TO DISCUSS SLEEVING OF THE SAN ONOFRE UNIT NO. 1 STEAM GENERATOR TUBES NRC and Southern California Edison (SCE) representatives met in Bethesda, Maryland, on July 31, 1980, to discuss the sleeving design concept for steam generator tube repair and plans to decontaminate the steam generator bowl prior to sleeving. The meeting attendees are listed in Attachment 1.
SCE requested the meeting to present details of the design concept of sleeving steam generator tubes with leak-tight sleeves as a repair mechanism for tubes that had undergone intergranular attack. In addition, SCE repre sentatives presented data and a description of their proposed method of decontaminating the steam generator bowl with a hydro grit stream composed of water and magnitite.
A copy of the material presented at the meeting (minus Westinghouse proprietary data) is enclosed in Attachment 2.
The major items discussed during the meetings are summarized below:
- 1. The NRC staff indicated some of their concerns related to the sleeving process that need to be addressed. These concerns included:
inspectability of sleeved tubes; leak tightness of the sleeves; mechanical strenght of sleeved tubes; radiological exposure to workers during the repair program; pluggability of sleeved tubes; and effects of stagnation of secondary water between the sleeve and tube.
- 2. The sleeves installed at Palisades were of a different design than proposed for San Onofre Unit 1. The Palisades sleeves were not designed as leak tight.
- 3. Cold leg inspections had been performed and four (4) tubes had indications of Phosphate thinning. Approximately 1400 tubes were inspected previously and 107 tubes examined during this inspection.
- 4. Pressure testing was performed on 25 tubes in the hot leg up to 3000 psig and no tubes leaked. The tubes are designed for a differential pressure of 2200 psig following an accident.
-2
- 5. SCE preposes to sleeve approximately 2500 tubes per steam generator or approximately 7500 tubes out of the 11,382.
- 6. SCE has performed an evaluationiand has concluded that the sleeving does not constitute an unreviewed safety question.
- 7. SCE has estimated that worker exposures will be 250 man rem for inspection plus tube pulling and approximately 1000 man rem for steam operator repair.
ALARA aspects will be covered in the August 15, 1980 meeting.
- 8. The NRC staff wants design details on the mechanical plugs in time to include this aspect in our review.
- 9. SCE requested NRC approval to install sleeves and any remaining concerns by September 10, 1980. SCE plans to return San Onofre Unit 1 to power about November 1, 19810.
Stanley J. Nowicki, Project Manager Operating Reactors Branch :#5 Division of Licensing Attachments:
As stated.
DL:
5 DL O F F IC E DATE_
9/ /80 9/j fl.80 NRC FORM 318 (9-76) NRCM 0240 U.S. GOVERNMENT PRINTING OFFICE: 1979-289-369
-2
- 5. SCE preposes to sleeve approximately 2500 tubes per steam generator or approximately 7500 tubes out of the 11,382.
- 6. SCE has performed an evaluationtand has concluded that the sleeving does not constitute an unreviewed safety question.
- 7. SCE has estimated that worker exposures will be 250 man rem for inspection plus tube pulling and approximately 1000 man rem for steam operator repair. ALARA aspects will be covered in the August 15, 1980 meeting.
- 8. The NRC staff wants design details on the mechanical plugs in time to include this aspect in our review.
- 9. SCE requested NRC approval to install sleeves and any remaining concerns by September 10, 1980. SCE plans to return San Onofre Unit 1 to power about November 1, 1980.
5 Stanley J. Nowicki, Project Manager Operating Reactors Branch #5 Division of Licensing Attachments:
As stated.
Mr. September 22, 1980 cc Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)
Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall #2 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN:
EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC P. 0. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Chai rimn Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814
ATTACHMENT 1 ATTENDANCE
- 1. S. J. Nowicki NRC
- 2. R. W. Krieger SCE
- 3. E. G. Igne NRC
- 4. C. Y. Cheng NRC
- 5. B. L. Curtis SCE
- 6. W. J. Collins NRC
- 7. F. Almeter NRC
- 8. B. Turovlin NRC
- 9. C. Hinson NRC
- 10.
J. Wing NRC
- 11.
B. D. Liaw NRC
- 12. S. S. Pawlicki NRC
- 13. G. Georgiev NRC
- 14.
R. Dermann NRC
- 15. D. Huang NRC
- 16. E. Murphy NRC
- 17. R. Emch NRC
- 18. F. Witt NRC
- 19. L. Barrett NRC
- 20. E. Brown NRC
- 21.
H. Conroad NRC
- 22.
L. Frank NRC
- 23. D. Meoli NSD W
- 24. P. Dtosa W NSD
- 25. T. Timmons W NTD
- 26. A. Klein W NTD
- 27. E. Murphy W BLO
- 28. C. Hirst W NSD
- 29. J. Taylor W NSD
- 30. P. Matthews NRC
ATTACHMENT 2 SCE MEETING WITH NRC JULY 31, 1980 AGENDA INTRODUCTION SCE PROGRAM PUAN STATUS UPDATE SCE DECONTAMINATION PROCESS STEAM GENERATOR TUBE SLEEVING PROCESS LICENSING CONSIDERATIONS SCE Sueway SCE
ACTIONS CONTINUE RPC EDDY CURRENT TEST NG INDIVIDUAL PRESSURE TEST 5 LEAKERS IN SG-C INDIVIDUAL PRESSURE TEST TUBES (TEST FIRST WITH RPC)
PULL TUBES (TEST FIRST WITH RPC)
RCS PRESSURE TEST OF BUNDLE SS PRESSURE TEST OF BUNDLE PLUG TUBES CHEMISTRY FLUSHNG INSTITUTE CHANGES IN CHEMISTRY CONTROL REDUCED CONDITIONS OPERATIONS REPAIR
OVERALL OBJECTIVE Return the unit to power at earliest date consistent with safe operation.
REFERENCE APPROACH install leak tight sleeves in the largest number of tubes consistent with logistics and channel head access, with the intent to return the unit to 100%
power operation.
ALTERNATE APPROACH Mechanically plug the minimum number of.
tubes consistent with-safe operation. Unit will be returned to operation at reduced conditions to arrest corrosion in unplugged tubes.
OPERATIONAL BASIS Proceed in parallel with the following major tasks o Define zones for repair by means of eddy current testing, tube removals, individual tube pressure tests and primary hydro of tube bundle o Develop sleeving process and installation procedure o Design and qualify temporary plug to permit.recovery of tubes removed from operation o -Proceed with expedited production of 3/4" conventional plugs o Adapt abrasive DeCon System for operation in Model 27 SG's
RPC "A"l CorrlateRPCTube Press Tube Pull CreaeRCTest ln-Situ S/G A RPC &Bobbi B &C Data in SG-A New Gear Pressure On-Site Define ones Hydro Safety Test of RT of OK in AsdrSemet Tubes in Tubes SG A, B, C Lab R-r Not OK Sleeve as No Sleeve bll Br Practical Zones DefinedZoe HolesZoe Plug Secondary Remainder and/
.Hydro or Operational Constraints Repair as Require Pr imary Hydro Secondary Hydro Repair as Required ECT Sleeves Chem Flush Reurn to Power
SUMMARY
OF TUBE EXAMINATION R24-C71 (DISTORTED DENT) 95% MAX. WALL PENETRATION SEM & MET. COMPLETE R31-C28 (GRAY TUBE)
\\,70% MAX. WALL PENETRATION SEM & MET. COMPLETE R13-C67 (DISTORTED DENT)
%90% MAX. WALL PENETRATION SEM & MET. COMPLETE IGA "2500 R11-C69 (NON DISTORTED DENT)
"-90% MAX. WALL PENETRATION SEM & MET. COMPLETE IGA -180' R32-C71 (LARGE DENT)
EXAMINATION IN PROGRESS IGA >50% BY VISUAL EXAMINATION R14-C70 (NORMAL T/S SIGNAL)
BURST TEST COMPLETE 15,000 PSI MAX. PRESSURE "1/8" LONGITUDINAL CRACK VISUAL EXAMINATION COMPLETE "50-60% WALL PENETRATION BY VISUAL EXAMINATION R17-C52 (CREVICE INDICATION)
N,80% MAX. WALL PENETRATION MET. COMPLETE
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In TO APRIL, 1980
TUBE REMOVAL AND EXAMINATION Reasons:
I. To verify RPC data
- 2. To provide sludge free sample for burst test in laboratory
- 3. To outline boundary for sleeving Sample Removal:
Samples #1 & 2:
Periphery tube, judged to have a small dent, but in good condition, i.e., <20% wall penetration.
This tube will be used to.
obtain information to support items #1 and #3 above.
Samples #3, 4, & 5:
Tubes judged to have penetration of <20%,35%, and 62%
as determined by RPC.
Examinations and laboratory burst tests of these tubes will be used to support items #1 and #2 above.
Sample #6:
Central region tube judged to be a non-dented "good" (NDD) by RPC. Examination of this tube will be used to support items #1 and
- 3 above.
Logic:
Sample #1 will be removed first and a preliminary examination undertaken on site. This examination will consist of Visual Examination, Radiography, and Eddy Current testing. The result of this examination will enable a preliminary evaluation to be made on the validity of RPC and.the condition of the corrosion free periphery area.
Sample #6 will be removed second to establish the condition of the central corrosion free region.
If sample #1 & #6 agree with expected results, tubes #3. 4, 5 and 2 Qill then be removed to obtain further confidence In the RPC data and to obtain repre sentative tubes for laboratory pressure/leak rate/burst tests.
If sample #1 and
- 6 donot agree with expected results, tubes #3, 4, 5 and 2 will not be removed since there will be uncertainty as to the actual tube condition and the RPC data is judged to be suspect.
Tube pul Con I rm RPC No 100
- Sleeve, Abort tube (ub <
11 f *Red. Pwr Oper puin.
(ul) 5%.
T pwgpleae Tube pull (6)r PC N 0% lee Non-ente goodn rssOPlgo tube. Central9 ed Pr pe pulin gear.ar Ye
-SAN ONOFREfUNIT 1 TUBS PULL
SAN ONOFRE 41 TUBE PULL CANDIDATES CANDIDATE No.
SG/R-C BOBBIN RPC 400 kHz 100 kHz Mixed
- 1 A-R23C83 Ned.Dent Yes Med.Dent
- 2a A-R22C83 Mcd.Dent Yes Med.Dent NDD
- 2b A-R22C84 Sm. Dist. Dent Yes Sm.
Dent NDD
- 3 A-R12C70 Sm. Dent Yes Sm. Dent 20%
- 4a A-R15C70 Sm. Dist. Dent Yes Sm. Dist. Dent 35%
- 4b A-R20C85 Med.Dent Yes Med.Dent
- 5 A-R17C61 Sm. Dent Yes Dist.Dent 62%
- 6 A-R20C60 Normal Entry NDD NDD NVD
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COLD LEG TUBE REMOVAL AND EXAMINATION Reasons:
To determine the need for additional tubing and to establish the need for sleeving the cold leg side of the steam generators.
Sample Removal: The sample to be removed should be one showing a large indication by bobbin and/or R.P.C.
Logic:
The sample will be removed in a manner that will expedite on site determination of tube conditions. This on site examination will consist of radiography, eddy current and visual examination. This examination will provide the basis for a decision regarding immediate tube procurement. The tube will then be sent to Pittsburgh for a more critical examination to determine its condition.
Innic Chart*
See attachment.
SERIES 27 SCE-A P0 m-O t-OC ')'M
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COLD LEG TUBE REMOVAL No need for Not Cracked Cold Leg Sleeving Plans To Pittsburgh Remove Cold Leg
'Site
-o continued tube Examination for continued Large RCP indication examination Prepare to I
Sleeve at some time Cracked (order tubinb)
INDIVIDUAL PRESSURE TESTS
- 1. Define good tubes/zone boundaries.
Pressurize to 23000 psig If no leak, tube can withstand accident conditions if tube leaks, evaluate options a) Sleeve b)
Plug c) Operate at reduced conditions d) Combinations of a) to c).
- 2. Establish integrity of corroded tube a) In good zones b)
In active zones Press Test Leak at If no leak @
<2200
-3000--psi
<22 Leak @
2200 -
3000 psi I
~Eval total Confirm integrity Ev Sleeving
]
- outs-W e-of zone Sleeving Eval options
- 1. Sleeve
- 2. Plug
- 3.
Reduced options Implement options
SCE #1/A TUBE PRESSURE TEST SELECTION R-C RPC CONV.
TYPE Arc' ZONE 1 A-13-70 55%
2200 NDD 1
13-71 89 240 NOD 2
11-60 97 350 NDD 4
ZONE 2 A-12-33 50%
1800 NDP 1
13-42 86 240 80%
2 9-43 97 180 45%
3 12-27
<20 90 NOD b
ZONE 3 A-24-39 69% 1200 NOD 1
24-43 64 150 NOD 1
24-42 83 120 NOD 2
17-63 96 180 NOD 3
17-48 94 210 NOD 4
ZONE 4 A-35-47 55%
900 NOD 1
38-51 88 210 NOD 2
38-53 91 180 33%
3 39-58 96 150 NOD 3
29-73 96 360 NOD 4
ZONE 5 A-34-76 NDD NOD 5
43-59 NOD NOD 5
40-34 NOD NOD 5
28-18 NOD NOD 5
12-13 NOD NOD 5
8-90 NOD NOD 5
ZONE 6 A-15-54 NOD NDD 5
28-52 NOD MOD 5
ZONE 1 -
S/L Accessible Manway TYPE 1 -
<80.
2 -
S/L Accessible Nozzle 2 90 Large Arc Length 3 -
Quiet Centre 3 -
90-100 Small Arc Length 4 -
Active Zone R34-40 C40-60 4 -
194% Large Arc Length 5 - Outer Periphery 5 -
20 or NOD 6 - Central
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BASIS FOR DEFINING ACTIVE/INACTIVE ZONES
- 1)
Plot RPC and bobbin EC data. Define zones encompasing all indications at top of tubesheet -
SG-A.
- 2)
Validate zone boundaries with results of tube pressure tests and tube pull results.
- 3)
Obtain RPC data for B and C and repeat step 1).
1.) Establish zone boundaries with similitude arguments from SG-A tube pressure tests and tube removal results
- 5)
Confirm by results of primary hydro tests.
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czpptoximat elyI 1 tube be~yond aU pluggable Lnditcation apptLe to SG A,8, and C 7/30/80
Conditions for Power Operation
-Sleeves Icev e, Zones are Znes no SDe-fined Defined Fo f-i.Con~d it ions Opera IOn-Irt Plug/Plat~e Reduced Maxtimum Plug/Plate Operate
--r..Operating Con itior Conditions Condito Establish Plug Establish Criteria Plug Crit.
DECON PRCESS IEVELCPMNT FOR STEA1 GENERATOR CHANNELHEAD MAINTENNCE ACTIVITIES HIGH PPESSURE WATER QEEMICAL DRY GRIT HYDRO/GRIT
HYDRO/GRIT GRIT OPTIONS PORIC ACID MAGNETITE ALUI NA EXPECTED SURFACE DF BORIC ACID 5 - 10 MAGNETITE 20 - 50 ALIfIMA 20 - 50
MAGNETITE GRIT RE~lifENIED PROCESS HI 1)F -
10 OR GREATER RECYCLE MINIMIZE WASTE VOLUW
--- 'LEVEL CONTROL VALVE PLOYYCLON
-rRWSM
)rLOANZr WASE SURG HIGH SEPARATOR
. SHIP LDED PRESSU RE WoZZLES FE-ED.PUMP CASK PUMP PUMP SUCTION M8 PUMP I LTDER.
PI P
Pi Pi GR IT GRIT.
apor 2
Perf Ii X. A I P FLOW VENT
- 'FIGURE I : DECOM REcC.CLE 5MEM
DPERIFNCE BORIC ACID GRIT - (CE THRU SYSTEM IEVELOPtEff PROGPAM OUALIFICATION COMPLETE POINT BEACH, ONE CHANNEL HEAD - NO SIGNIFICAT Dr TAK I, SIX CHPNNEL HEAD - 2.5 DF.
MAGNITATE GRIT - RECYCLE SYSTEM OUALIFIED DURING RETUBE PRGRAI HOT TEST SURFACE DF OF GREATER THAN 1.0 AJFVED
TECHNICAL ISSUES
- 1.
CLAD CONDITION AFTER IECON
- 2.
RESIDUAL GRIT (HEMISTRY C(FPATIBLE R.C. UPP SEALS/CRfl
- 3.
DILUTION
- 4.
WAS1TE HANDLING
EXPECTED WASTE PER STEAM GENERATOR
- THREE TONS Of MAGNETITE GRIT, (APPROXIMATELY 5 MICROCURIES PER GRAD
- EIGHT TO TWELVE, 55 GALLON DRJMS
- 600 GALLON CF RECYCLE WATER (0.5 MICROCURIES PER MILLILITER)
- 2000 GALLONS OF RINSE WATER
- MORE ABRASIVE GRIT
- TUBE DECON
- PIPE NOZLE SHIELD
- HAND CLEANUP
PRELIMINARY LICENSING INFORMATION SCHEDULE PRELIMINARY DISCUSSIONS W/NRC 6/18, 7/1, 7/10 PRESENTATION OF PROGRAM PLAN 7/22 NRC fEETING TO DISCUSS SLEEVING 7/31 NRC MEETING TO UPDATE INFORMATION 8/15 NRC FEFTING & SLEEVING REPORT 9/1 NRC APPROVAL TO INSTALL SLEEVES 9/10 FINAL 50.59 REPORT 10/7 NRC APPROVAL TO RESPvE OPERATIO 11/N
PURPOSE OF MEETING OPENING TECHNICAL DISCUSSION OF THE SCE SLEEVING PROGRAM
- DESIGN AND PROCESS DISCUSSION ALARA CONSIDERATIONS
- ESTABLISH CONTENTS OF 8/15 IEETING
SLEEVING PROGRAM PURPOSE TO DEVELOP A REPAIR PROCEDURE FOR A DEFECTIVE TUBE AS AN ALTERNATE TO PLUGGING, THUS EX1ENDING STEAM GENERATOR LIFE OVERALL TECHNICAL OBJECTIVE DEVELOP A LEAK TIGHT BOND BEIEEN SLEEVE AND TUBE DEVELOP A REMOTE TOOLING INSTALLATION SYSTEM POTENTIAL SEALING METHODS BRAZING MECHANICAL WELDING POTENTIAL EXPANSION METHODS HYDRAULIC ROLL.
SERIES 27 9991959394898 85838179117?513714.91.7151.5j1995755535I4941 45434S13533ts17tst3 Z1t9 111513t 11 q 5 s3 I COLUMNS too ? 19491I 088B&4B187 le74 7Z 7o0tokes GCSE56ks 5ZS04 441 tO31.343Z oll020 4zV 2C 1811614 1210 8
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ALARA ACTVITIS
- DECN BOIL AND TUBES
- REMOTE TOOLING
- SHIELDING e MOCK-UP TRAINING e V SURVEILIANCE
- ADMINISTRATION CUTROLS
- ENVI R(NMTAL CU14TROLS 0 MODEL AND MOlITOR EXPOSURES
Licensing Information Schedule Preliminary Discussions w/NRC 6/18, 7/1, 7/10 Presentation of Program Plan 7/22 NRC Meeting to Discuss Sleeving 7/31 NRC Meeting to Update Info 8/15 NRC Mtg & Sleeving Report 9/1 Including Zones to be Repaired NRC Approval to Install Sleeves 9/10 Final Revised Reload Safety Evaluation Report 10/7 NRC Approval to Resume Operation 11/1
SLEEVING REPORT LICENSING INFORMATION e
Design Concept Design Analysis Prototype Testing Pressure Testing Thermal Cycling Corrosion Testing Inspectability Installation Inservice e
Material Compatibility Installation Concept ALARA Criteria for Zones Repaired 10 CFR 50.59 Design Change Review
Revised Reload Safety Evaluation Report Description of Repaired Steam Generators Inspection Results Tube Removal and Examination Results Individual Tube Pressure Test Results Zones Repaired (Sleeved and/or Plugged)
Sleeving Report (Referenced)
Evaluation of Plant Performance Reduced Temperature, Pressure and Power T/H Effects of Sleeving LOCA Analyses Non-LOCA Analyses Functional Set Point Changes Licensing and Technical Specification Changes Operational Considerations Chemical Flushing Chemical Control Improvements