ML20155F469
| ML20155F469 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/02/1988 |
| From: | Gears G NRC OFFICE OF SPECIAL PROJECTS |
| To: | NRC OFFICE OF SPECIAL PROJECTS |
| References | |
| GL-88-01, GL-88-1, TAC-62263, NUDOCS 8806160398 | |
| Download: ML20155F469 (16) | |
Text
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June 2, 1988 i
Docket No. 50-260 LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Power Station, Unit 2
SUBJECT:
MAY 11, 1988 MEETING WITH THE TENNESSEE VALLEY (TVA) TO DISCUSS THE BROWNS FERRY RESPONSE TO GENERIC LETTER 88-01 AND INTERGRANULAR STRESS CORROSION CRACKING (TAC NO. 62263)
On May 11, 1988, members from the Office of Special Projects met with the staff of Tennessee Valley Authority (TVA or the licensee) to discuss TVA's response to Generic letter 88-01 (GL 88-01) and the Browns Ferry, Unit 2 restart item identified as Intergranular Stress Corrosion Cracking (IGSCC). is the list of individuals that attended the meeting. Enclosure 2 provides a copy of the TVA sunnary slides used at this meeting.
The following issues were highlighted during the meeting:
TVA's response to Generic Letter 88-01 will include additional welds as suggested by the OSP staff.
The staff indicated that TVA's response per GL 88-01 should include a connitment to provide a Technical Specification amendment request. This amendment should be submitted prior to restart.
The approximately 70 welds which were not post-lHSI inspected, while correctly classified by Generic Letter guidance as Category G, should be reinspected on an expedited schedule, when and where possible.
TVA comitted to factor in the above issues as part of the GL 88-01 response scheduled to be submitted to NRC by July 1988. The staff will need to review this submittal prior to completing its review of IGSCC restart item for Browns Ferry, Unit 2.
Original Signed by Gerald E. Gears, Project Manager-TVA Projects Division Office of Special Projects
Enclosures:
1.
Attendance List 2.
TVA Slides Used in Presentation Distribution Docket File NRL PDR Local PDR Thr.se on Attached List OSE'TVA/PM TV
/P GGhrlas SBlack 6/4/81 6/)-/88 8806160398 880602-PDR ADOCK 05000260 P
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ENCLOSURE 1 MEETING ON MAY 11, 1988 IGSCC Name Organization G. Gears OSP/TVA R. E. Shewmaker OSP/TVA Ed Harting TVA Patrick Carrier TVA James East TVA Ernia Crane TVA Martha Meadira TVA David Smith OSP/TVA B. D. Liaw OSP/TVA R. Hermann OSP/TVA
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STRATEGY FOR RESPONDING TO GL 88-01 LIgg ERQPOSED RESPONSE
- 1. MITIGATION PL ANS A.
GIVT HITIGATION STATUS OF EACH UNIT B.
DESCRIBE MITIGATION AND REP AIR PL ANS C.
DESCRIBE OPTIONS BEING CONSIDERED IN AREAS WHERE DECISIONS HAVE NOT BEEN MADE:
UNIT 1 REPLACEMENT UNIT 1 AND 3 SAFE ENDS PENETRATION WELDS D.
COMMIT TO INFORMING NRC OF MITIGATION PLANS FOR UNITS 1 AND 3 WHEN THE DECISIONS ARE MADE 2.
Is! PROGRAN PLANS A.
DESCRIBE PROCEDURAL CHANGES BEING MADE TO COMPLY WITH METHODS AND PERSONNEL REQUIREMENTS B.
DESCRIBE ISI PL ANS FOR UNIT 2, CYCLE 6 RF0 C.
COMMIT TO INFORMING THE NRC OF ISI PL ANS FOR UNITS 1 AND 3
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BEFORE INSPECTIONS ARE INITI ATED AND INFORMING THEM OF THE RESULTS BEFORE UNIT STARTUP
ARE SUFFICIENT WITHOUT TECH SPEC CHANGE 4.
CONFORMANCE ON LEAX DETECTION DESCRIBE HOW TECH SPECS HAVE BEEN CHANGED TO MEET THESE REQUIREMENTS REQUIREMENTS
- 5. PLANS TO NOTIFY THE NRC DESCRIBE HOW THIS WILL BE OF NEW FLAWS OR CHANGES ACCOMPLISHED TO EXISTING ONES
l NUREO-0313, R.2 SCOPE Or IOSCC SUSCEPTIBLE PIPING ALL AUSTENITIC STAINLESS STEEL PIPING 14" DI AMETER' WHICH OPE 1.
AT A TEMPERATURE 1 200'P ALL CREVICED AUSTENITIC STAINLESS PIPING COMPONENTS 2.
SCOPE OF BFN SUSCEPTIBLE P! PING RECIRCULATION - INCLUDING OUTLET SAFE ENDS RESIDUAL HEAT REMOVAL - TO THE FIRST ISOLATION VALVE OUTSIDE OF THE DRYWELL PENETRATION REACTOR WATER CLEANUP -
TO THE FIRST ISOLATION VALVE OUTSIDE OF THE DRYVELL PENETRATION CORE SPRAY - STAINLESS STEEL SECTIONS INSIDE THE PENETRATION RECIRCULATION INLET S AFE ENDS JET PUMP INSTRUMENTATION S AFE ENDS CRD RETURN, AND RECIRC DISCHARGE VALVE BYPASS EITHER HAVE BEEN HEAD SPRAY, REMOVID OR WILL BE BEFORE STARTUP, AND So ARE NOT INCLUDED IN SCOPE 8
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SUMMARY
OF BROWNS FERRY UNIT 2 GL 8 4-11 RESPONSE LMSPECTTQN
SUMMARY
FALL 1984: INSPECTION OF ALL ACCESSIBLE, INSPECTABLE WELDS AS MANDATED BY GL 8 4-11 SPRING 1985: POST-IHSI INSPECTION OF 25% OF WELDS TREATED BY IHSI JUNE 1986: INSPECTION OF RECIRCULATION INLET AND CORE SPRAY S AFE ENDS OCTOBER 19 8 6 : INSPECTION OF ALL REACTOR WATER CLEANUP WELDS SUMMER 1987: INSPECTION OF ALL NEW WELDS RESULTING FROM S AFE END REPLACEMENT AND ALL WELDS RECEIVING IHSI IN SECOND EFFORT y
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DISPOSITI_0N_OF FLAWED WELDS:
IHSI:
WELDS KR-2-14, KR-2-36, KR-2-37,.KR-2-41 OVERLAY: WELDS GR-2-15 AND DSRWC-2-5 REPLACEMENT:
JP-2-1 A AND JP-2-1B REPLACED WITH 316HG DRWC-2-4 REPLACED WITH HEAT SINK WELDED 304 ALL RECIRCULATION INLET SAFE ENDS REPLACED WITH NON-CREVICED DESIGN S AFE ENDS OF 316HO RISERS ALSO REPLACED WITH 316NG 0,THER HITIGATIONS:
IHSI APPLIED TO 149 WELDS DECEMBER 1984-MARCH 1985 IHSI APPLIED TO REPLACED S AFE END AND RISER WELDS MAY-JUNE 19 87 TOTAL' 0F 161 VELDS TREATED BY IHS!
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l BFN UNIT 2 DISPOSITION OF CR ACXED VELDS _
WELD GR-2-15 APPLICATION OF FULL STRUCTUR AL OVERLAY 0.35" THICX DESIGNED 70 REQUIREMENTS OF GL 84-11 FRACTURE MECH ANICS FLAW EVALUATION INDICATES DESIGN BASIS S AFETY MARGIN MAINTAINED FOR 2 CYCLES OF OPERATION WELD DSRWC-2-5 APPLICATION OF FULL STRUCTURAL OVERLAY 0. 20" THICX DESIGNED TO REQUIREMENTS OF NUREG-0313,R.2, DRAFT FRACTURE MECHANICS FLAW EVALUATION INDICATES DESIGN BASIS
. S AFETY MARGIN MAINTAINED FOR MULTIPLE CYCLES OF OPERATION WELDS XR-2-14, XR-2-36, KR-2-41, XR-2-37 WELDS TREATED BY IHSI SHORT AND SH ALLOW INDICATIONS 1 26% THROUGHWALL DEPTH 1 10% CIRCUHFERENTI A1, LENGTH FR ACTURE MECH ANICS FLAW EVALUATION PERFORMED IN ACCORDANCE WITH IWB-3640 AND GL 84-11 EVALUATION INDICATED DESIGN BASIS S AFETY MARGIN HAINTAINED i
BY A LARGE MARGIN INDEFINITELY DUE TO EFFECTS OF IHSI l.'
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BFN UNIT 2 HITIGATiON BThTUS NUMBER CATEGORY DESCRIPTION PIPING WELDS R E S I S T AN T WE L D S............................... 2 6........... A
.C WELDS WITH SI AFTER 2 YEARS OF OPER ATION...... 55.......
N ON RE S I S T AN T WEL D S.................., S.......... D l ch.
INSPECTED, 6..........E CR ACXED WELDS WITN IHS! CR OVERL AY.............
UNIN SPECTED, NONRES I STANT WELDS *.............. 7 3 *......... G TOTAL.........................................
168 70 WELDS THAT WERE NOT INSPECTED FOLLOWING IHSI
- INCLUDES RECIRCULATION INLET SAFE ENDS R E S I S T AN T COMP O N E N T S.......................... 10.......... A JET PUMP INSTRUMENTATION SAFE ENDS
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R E S I S T AN T C O M P O N E N T S........................... 2.......... A MrTIGATION/ REPAIR PLANS INSTALLATION OF HYDROGEN WATER CHEMISTRY 1.
APPLICATION OF CRC, LEAX DETECTION OR REMOVAL OF PENETRATION WELDS 2.
(INCLUDES 3 CATEGORY O WELDS AND 2 CATEGORY D WELDS)
DFN UNIT 3 HTTICATION STATUS NUMBER CATEGORY DESCRIPTION PIPINO WELDS WELDS WI TH S I AFTER 2 YE ARS OF OPER ATION...... 4 2..........C INSPECTED, N O N R E S I S T AN T WEL D S................. 11.......... D NONINSPEC1%D, N ONRE S I S T AN T WELD S *............ 12 0.......... C T 0 T AL......................................... 1 7 3 DINCLUDES 106 WELDS THAT WERE NOT INSPECTED FOLLOWING IHS,I RECIRCULATION INLET SAFE ENDS CRACKED, UNMITIGATED COMPONENTS................
4..........F UNINSPECTED, NONRESI ST ANT C0HPONENTS........... 6......... 0 o
JET PUMP INSTRUMENTATION S AFE ENDS i
CRACKED C0HPONENTS OVERLAYS....................
2..........E MITIGATION / REP AIR PL ANS 1.
IN3TALLATION OE HYDROGEN WATER CHEMISTRY 2.
IHSI 0F 3 CATEGORY 0 WELDS AND 11 CATEGORY G VELDS 3.
APPLICATION OF CRC, LEAX DETECTION, OR REMOVAL OF PENETRATION VELDS (INCLUDES 3 CATEGORY G WELDS AND 2 CATEGORY D VELDS)
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1 SFN UNIT 1 M2TIGATION STATUS _
NUMBER CATEGORY DESCRIPTION PIPING WELDS CR ACX E D WEL D S WI T H OVER L AY.................... 4 2....... E O R F CRACKED WELDS WITH No MITIGATION...............
4..........F 8NSPECTED, N ON R E S I S T AN T WEL D S................ 118.......... D UNINSPECTED, NONRESISTANT WELDS...............
19..........G T 0 T AL...................,..................... 1 8 3 RECIRCULATION INLET S AFE ENDS CRACKED, UNMIT! GATED COMPONENTS................
5..........P UNI NSPECTED, NONRES I ST ANT COMPONENTS...........
- 5.......... G JET PUMP INSTRUMENTATICH S AFE ENDS i
UNINSPECTED, NONRESIST ANT COMPONENTS...........
- 2.......... G l
MIT!GATION/ REP AIR PLANS OPTIONS BEING CONSIDERED:
,1.
FULL REPLACEMENT OF PIPING, S AFE ENDS, AND PENETRATIONS 2.
A.
STRESS IMPROVEMENT OF ALL NON-0VERLAID WELDS B.
UPGRADING OF OVERLAYS TO MEET NUREG REQUIREMENTS C.
APPLICATION OF CRC, LEAX DETECTION, OR REMOVAL OF PENETRATION WILDS (INCLUDES 4 CATEGORY D WELDS)
D. RESOLUTION OF S AFE END CRACXING HYDROGEN WATER CHEMISTRY HAS BEEN COMMITTED TO FOR EITHER OPTION s
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PLANNED FLOW OF IOSCC REPORTINO FOR UNIT 1 DECISION MADE ON MITICATION STRATEGY V
V FULL SCALE REPLACEMENT ALTERNATIVES TO REPLACEMENT SUBMITTAL OF REPLACEMENT PL AN3 TO NRC REPLACEMENT IMPLEMENTED REVISION OF ISI PLAN FOR CYCLE 6 SUBMITTAL OF REVISED ISI PLAN AND MITICATION PLANS TO NRC i
INSPECTICH PERFORMED o.
MITICATION PL AN IMPLEMENhED i
V V
y V
DEVELOPMENT OF IS! PLAN FOR CYCLE 7 SUBMITTAL OF REPORT ON MITIGATION AND ISI PLAN TO HRC
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e COMPLIANCE WITH NUREG-0313,R.2 '-
FOR ISI METHODS AND PERSONNEL i
THE NUREG REQUIRES THAT:
"ALL LEVEL 2 AND 3 NDE EXAMINERS OR OPERATORS FOR FLAW DETECTION AND SIZING SHOULD DEMONSTRATED THEIR FIELD PERFORMANCE CAP ABILITY....THE PROGRAM BEING CONDUCTED AT EPRI N CENTER...IS CONSIDERED To BE ACCEPTABLE."
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THE FOLLOWING PROCEDURES ARE BEING CHANGED To REFLECT REQUIREMENTS NUREG-0313, R.
2.
N-UT-25 "UT EXAMINATION OF PIPING WELDS FOR THE DETECTION OF LOW LEVEL CRACKLIXE REFLECTORS ORIGINATING AT THE ID SURFACE" "UT EXAMINATION USING THE INTRASPECT 98 SYSTEM FOR THE N-UT-42 DETECTION OF INTERGRANULAR STRESS CORROSION CRACKING IN PIPING WELDMENTS" "UT EXAMINATION OF BACKLAY WELD REPAIRS" N-UT-28 BF-UT-29 "UT EXAMINATION OF BACKLAY VELD REPAIRED PIPING WELDS"
/ THE SIZING PROCEDURES, WHICH ARE CURRENTLY UNDER DEVELOPMENT, WILL ALSO INCLUDE THE NEW QUALIFICATION CRITERIA, 1
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PROPOS AL TO OMIT CHANGE OF TECHNICAL SPECIFICATIONS AS REQUESTED IN GL 88-01, P.
3, P AR AGR AP H 3 NRC REQUEST:
"To INCLUDE A STATEMENT IN THE SECTION ON ISI THAT THE INSERVICE INSPECTION PROGRAM FOR PIPING COVERED BY THE SCOPE OF THIS LETTER WILL BE IN CONFORMANCE WITH THE STAFP POSITIONS ON SCHEDULE, METHODS AND PERSONNEL, AND SAMPLE EXP ANSION INCLUDED IN THIS LETTER...."
TVA PROPOSES TO CHANGE !$1 PROCEDURES TO REQUIRE CONFORMANCE TO THE POSITIONS STATED IN THE GENERIC LETTER FOR THE FOLLOWING RSASONS:
- 2. SITE ADMINISTRATIVE PROCEDURES PROTECT PL ANT PROCEDURES WHICH S ATISFY COMMITMENTS FROM ARBITRARY CHANGES; THEREFORE, AS PART OF THE ISI PROCEDURES, THE REQUIREMENT FOR CONFORMANCE TO THE GL 88-01 POSITION WOULD BE PROTECTED UNTIL IT IS SUPERSEDED BY HEW NRC POSITIONS.
3.
INSPECTION RESULTS WILL BE REPORTED 3EFORE EACH PLANT START UP, XEEPING THE NRC INFORMED OF BROWNS FERRY' S INSPECTION ACTIVITIES.
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CHANGE OF TECHNICAL SPECIFICATIONS TO ADDRESS LEAKAGE MONITORING AMENDHENTS 70 THE LICENSES OF BFN UNITS 1,2, AND 3 TO BRING THE LEAKAGE MONITORING PRACTICES IN LINE WITH THE NRC POSITIONS STATED IN OENERIC LETTER 84-11 WERE PROPOSED BY LETTER FROM J.
A.
DOMER, TVA, TO D.
R.
MULLER, NRC, DECEMBER 15, 1986 THESE AMENDMENTS WERE ACCEPTED AND ISSUED AS STATED IN JOHN A. ZWOLINSKI's LETTER OF AUGUST 26, 1987 THIS REQUIREMENT IS THEREFORE SATISFIED o
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l PLANS TO NOTIFY NRC OF NEW FLAWS, CH ANGES TO EXI STING FL AWS,
FLAW EVALUATIONS, AND REPAIR FL ANS 1.
SUPPLkMENTS TO TVA'S RESPONSC 70 GL 88-01 WILL BE SUBMITTED TO INFORM THE NRC OF THE ISI PLAN AND ICSCC MITIGATION PLANS FOR THE NEXT REFUELING OUTAGE OF BROWNS FERRY UNITS 1 AND 3 BEFORE WORK RESUMES ON THOSE UNITS.
2.
SUMMARIES OF THE INSPECTION RESULTS, FLAW EVALUATIONS, AND REPAIR OR MITIGATION IMPLEMENTATION WILL BE SUBMITTED FOR EACH UNIT BEFORE UNIT STARTUP.
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1 TOTAL P.'s
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Browns Ferry Nuclear Plant Units 1, 2, and 3 cc:
General Counsel Regional Administrator, Region II Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive 10~. Marietta Street, N.W.
E11 B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector / Browns Ferry NP Mr. R. L. Gridley U.S. Nuclear Regulatory Commission Tennessee Valley Authority Route 12, Box 637 SN 157B Lookout Place Athens, Alabama 35d11 Chattanooga, Tennessee 37402-2801 Mr. Richard King Mr. H. P. Pomrehn c/o U.S. GA0 Tennessee Valley Authority 1111 North Shore Drive Browns Ferry Nuclear Plant Suite 225, Box 194 P.O. Box 2000 Knoxville, Tennessee 37919 Decatur, Alabama 35602 Dr. Henry Myers, Science Advisor Mr. M. J. May Committee on Interior Tennessee Valley Authority and Insular Affairs Browns Ferry Nuclear Plant U.S. House of Representatives P.O. Box 2000 Washington, D.C.
20515 Decatur, Alabama 35602 Mr. D. L. Williams Mr. S. A. White Tennessee Valley Authority Manager of Nuclear Power 400 West Summit Hill Drive Tennessee Valley Authority 1
W10 885 6N 38A Lookout Place Knoxville, Tennessee 37902 1101 Market Street Chattanooga, Tennessee 37402-2801 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Claude Earl Fox, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130
OISTRIBUTION FOR MEETING
SUMMARY
DATED: June 2, 1988 Facility:
Browns Ferry Nuclear Plant, Units 1, 2 and 3*
,+0ccket File NRC POR Local PDR Projects Reading S. Ebneter J. Partlow J. Axelrad S. Richardson S. Black B. D. Liaw G. Gears M. Sims OGC J. Rutberg F. Miraglia E. Jordan B. Grimes D. Moran J. Kelly R. Shewmaker D. Smith R. Hermann ACRS (10)
Hon. M. Lloyd Hon. J. Cooper Hon. D. Sundquiest Hon. A. Gore Or. Henry Myers Mr. R. King, GAO P. Gwynn J. Scarborough G. Marcus C. Miller 1
T. Elsasser C. Ader TVA-Rockville Plant-specific file
- cc:
Licensee / Applicant & Service List