ML20237E039
| ML20237E039 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/09/1987 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8712280106 | |
| Download: ML20237E039 (26) | |
Text
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NUCLEAR REGULATORY COMMISSION C
WAsHINo TON, D. C. 20555
(-
e December 9,1987 j
Docket No. 50-368 LICENSEE: Arkansas Power and Light Company FACILITY: Arkansas Nuclear One, Unit 2-(ANO-2)
SUBJECT:
SUMMARY
OF MEETING BETWEEN ARKANSAS POWER AND LIGHT CCMPANY (AP&L) AND THE STAFF REGARDING PERMANENT REPAIRS TO THE ANO-2 PRESSURIZER - OCTOBER 26, 1987
Background
During a containment entry on April 22, 1987, the licensee noted indications of a leak in the area of the pressurizer.
The unit was shut down and an investigation ensued.
It was determined that the leakage source was a pressurizer heater sleeve.
The licensee concluded that a permanent repair of the pressurizer, in accordance with the approved ASME Code editions, was impractical to perform with the available tooling.
In letters dated May 12 and 18, 1987, AP&L proposed a temporary repair and requested Cev.ission a;prosal to use certain orevisicts of ASME Section III that were more recent tnan the approved edition referencec in 10 CFR 50.55a(D).
The staf f approved me eauett in +he Sa'ety Evalu? tion (SE) of May 22. 199'?
In **e SE, the staff also requested that the licensee submit his plans for e percanent repair of the pressuri::er by Novembe-1,1987.
Current Status At an October 26, 1987 meeting the licensee presented to the staff its proposed plans for the permanent repair to the pressurizer. is a copy of the licensee's handouts.
The repairs are to be done during the next refueling outage scheduled to begin in mid February 1988.
A Iist of the meeting attendees is presented in Enclosure 1.
The permanent repair will entail removal of the temporary plug, grinding, and preparation of penetration area.
A " buttering" weld will be made on the outside of the vessel.
A machined Inconel nozzle will be inserted into the penetration and a structural weld perfomed betwen the nozzle and the buttering.
Using a remote control welding technique, a seal weld will be made on the inside of the vessel between the nozzle and the Inconel cladding.
The seal weld joining the nozzle to the cladding will preclude exposure of the vessel shell to borated water.
Also the weld material to be used is not subject to hydrogen embrittlement and stress corrosion cracking.
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8712280106 871209 DR ADOCK 05000368 p
1 4
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1 l 1 A mockup will be constructed to simulate the pressurizer lower head area.
It will be used for welder qualification as well as for training the installation personnel in the entire repair process. After evaluation of the repair I
technique on the mockup, it will be officially sent.to the staff.
i George F. Dick, Jr., Project Manager Project Directorate - IV Division of Reactor Projects - III,
)
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IV, V and Special Projects
Enclosures:
l As stated j
i cc w/ enclosures:
See n<;xt page I
1 1
i I
I DISTRIBUTION Tocket File NRC PDR Local PDR PD4 Reading i
J. Calvo G. Dick OGC-Bethesda E. Jordan J. Partlow F. Litton I. Bukulmez W. Hazelton K. Wichman B. Elliot J. Rajan ACRS (10)
PD4 Plant File D4/PM PD4/D /N
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ick:sr JCalvo 12/cf /87 12/01/87 l
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1 F.r. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 I
cc:
l Fr. J. Ted Enos, Manager Mr. Charlie E. Brinkman, Manager l
huc' ear Engineering and Licensing Washington Nu: lear Operations A-kansas Power and Light Company C-E Power Systems F. :. Bcx 551 7910 Woodmon: Avenue L4 ttle Rock, Arkansas 72203 Suite 1310 Bethesda, Maryland 20814
- . 1 ares.M. Levine, Director Si e Nuclear Operations I kansas Nuclear One P. O. Box 608 i
ussellville, Arkansas 72801 r
hicholas S. Reynolds, Esq.
Eishop Liberman, Cook,
- urcell & Reyr, olds 1
- 20 Seventeenth Street, N.W.
l
)
E :e 700 n-d rgton, D.C.
20036
- e:'eral Administrator, Region IV f;bclear Regulatory Ccerission
'#'-.e of Executive Directer for
' erations
..,2-P i a n E ri', e, S t. i te ' CCC ngton, Texas 76011 l
)
.s-'nr Fesidert !nspector
. 5. Nuclear Regulatory Comission
- %ciper Plant Read
- ussellville, Arkansas 72801
'9 Greta Dicus, Directcr
- '. 'sier of Environmental Health
- -etection iriensas Department of Health
!.8'.5 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum i
Babcock & Wilcox Nuclear Power Generation Division i
Suite 220 j
79:0 Woodmont Avenue Bethesda, Maryland 20814
)
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Arkansas Nucleac One-1 Unit 2 -
at Pressurizer Repair Process t.
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AP&L/NRC MEETING AGENDA l
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PRESSURIZER REPAIR 1
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I INTRODUC TION......................... D. BA XTER l
PURPOSE-
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II HIS TORICA L SUMMA R Y.................... L. TA YLDR
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PROBLEM CURRENT CONFIGURA TION 1
III PERMANENT CONFIGURA TION..............B.
BELL APPLICABLE CODES h
REMOVAL OF TEMPORARY PLUG R
I SP TI N0ZZLE INSERTION AND WELD TECHNIQUE F
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SEAL-WELD STRUCTURAL-WELD POST-INSPECTION QUALIFICATION WORK DEBRIS CHARACTERIZE TION
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IV WELDING AND MA TERIALS................ D. SPOND 0
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MA TERIAL CONSIDERA TIONS.
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WELDING & MATERIALS
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PURPOSE:
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. MA Y 22, 1987 SAFETY EVALUA TION REPORT a
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PRESENT THE ANO-2 PRESSURIZER REPAIR PLAN i
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THE ^ SCOPE OF THE PLAN WAS TO DESIGN A 7~
PERMANENT REPAIR PROCESS TO INCLUDE:
APPROVED CODES ISOLA TION OF LOW-ALLOY STEEL FROM RCS 1
ADDRESS HYDROGEN EMBRITTLEMENT CONCERNS 1
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SCHEDULE:
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CONCEPTUAL DESIGN. COMPLETE 9/24/87.
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'NRC PRESENTA TION 10/26/87
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APGL DESIGN' REVIEW
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12/29/87 DESIGN CHANGE PACKAGE COMPLETE 1/6/88.
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-MOCKUP DEMbNSTRA TION 1/11/88 1
o FINAL DESIGN REVIEW 1/13/88 o
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i N-h LEAKAGE DISCOVERY o'
BASED ON CONTROL ROOM, INDICA TIONS, X SMALL SIT ' LEAK WAS SUSPECTED ~
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o DUE TO. CONCERNS FOR EFFECT OF LEAKAGE ON RCS, CONTAINMENT ENTRY WAS MADE TO. INSPECT AND EVALUA TE (4/22) n o
SIT LEAKAGE LOCA TED -- VAL VE PACKING LEAKOFF TO DRAIN LINE
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O ADDITIONAL' GENERAL WALKDOWN CONDUCTED A T THIS TIME
'l TO IDENTIFY ANY ADDITIONAL RCS LEAKAGE.
1 AND WA TER OBSERVED ON CONTAINMENT BASEMENT FLOOR n
UNDER PRESSURIZER o
ADDITIONAL ENTRIES (4/23) WERE MADE TO FURTHER U
EVALUA TE THE LEAKAGE, PRESSURIZER HIGH POINT VENT LEAK (100 DPM) OBSERVED AND CAPPED.
BORIC ACID ALSO OBSERVED ON PRESSURIZER LOWER HEAD l "
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.I o-ENGINEERING'EVALUA TION AND AN ADDITIONAL ENTRY ON.
4/24 CONCLUDED A SECOND SHALL LEAK EXISTED.
LOCA TED
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AND EVENT REPORTED PER '90 CFR 50.-72
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DAMAGE ASSESSMENT i
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o FOLLOWING INSULA TION REMOVAL, VISUAL INSPECTIONS IDENTIFIED LEAKAGE SOURCE AS Xi HEA TER SLEEVE.
CORROSION WAS. OBSERVED ON PRESSURIZER SURFACE g.,j
(~1 1/2" DIAMETER x 3/4" DEEP CA VITY) o A TTEMPTED TO REMOVE FOUR HEA TERS C1
- ALLOW DRAINING OF LOWER HEAD Xi
- LEAK LOCA TION AA A - PREVIOUSL Y FAILED HEA TER T4
- FAILED HEA TER FOUND DURING ~ ELECTRICAL CHECKS n
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Xi AND T4 COULD NOT BE REMOVED (STUCK IN SLEEVE) ln
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REMOTE VIDEO INSPECTION OF Xi VIA AA1 SLEEVE REVEALED RUPTURED HEA TER SHEA TH AND DAMAGE TO 1ii SLEEVE (4/30) i.'
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1m OPENED PRESSURIZER MANWA Y (UPPER HEAD) - OBSERVED
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SIMILAR TO Xi BUT DAMAGE TO SLEEVE OT AS EXTENSIVE i,
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REMOVED Xi AND T4' SLEEVES CUT ~3/B" BELOW J GROOVE WELD AND o
LOWER PORTION REMOVED, VISUAL INSPECTION OF PRESSURIZER WALL NO APPARENT DAMAGE 'TO PRESSURIZER EXCEPT ON OUTER SURFACE NEAR Xi CARBON STEEL PLUGS INSERTED INTO Xi AND T4 HOLES AND u
o WELDED TO OUTSIDE OF VESSEL USING TEMPER BEAD WELDING REPAIR PROCESS NDE PERFORMED ON PLUGS AND WELD AREAS (PT AND UT) l o
NRC SER REQUESTED PERMANENT REPAIR PLAN BY i,
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OUTAGE IN JOL Y 1987.
RESUL TS INDICA TED NO SIGNIF-ICANT DIFFERENCES FROM THE EXAMS PERFORMED IN MAY li 1987.
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CONTINUED WITH DEVELOPMENT OF' PERKRNENT REPAIR PLAN
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APPLICABLE CODES ORIGINAL PRESSURIZER DESIGN ' CODE:
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ASME SECTION III 1968' EDITION THROUGH SUMMER 1970 ADDENDA I
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DESIGN CODE:
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1980 EDITION THROUGH WINTER 1981 ADDENDA RECONCILED TO ORIGINAL DESIGN CODE l.
o REPAIR CODE:
ASME SECTION XI 1980 EDITION THROUGH WINTER 1981 ADDENDA f
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_ REPAIR PROCESS OUTLINE l
5?EMOV5L F TEMPORARY PLUG:
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(Con t. )
5 PREPARA TION AND ' PRE-INSPECTION:'
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-PT OR MT WELD PREP IN ACCORDANCE WITH NB-5000 i
o MEASURE G' RECORD DIMENSIONS OF FINAL WELD PREP o
' CA VITY INSTALL HEA TERS & THERMOCOUPLE AS REQUIRED FOR o
PRE-HEA TING THE VESSEL HEAD
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PREHEA T REPAIR AREA, PERFORM BUTTERING WELD, AND NDE IN ACCORDANCE WITH ASME CODE ^ REQUIREMENTS sa GRIND OR REAM PENETRA TION TO REMOVE ANY WELD METAL k
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.i N0ZZLE INSTALL A TION:
'1 MACHINE N0ZZLE AS-REQUIRED TO ACHIEVE DESIRED FIT
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o INSERT NOZZLE 'IN PENETRA TION G VERIFY POSITION G
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.1 PERFORM SEAL WELD 'AND STRUCTURAL WELD O
O PERFORM REQUIRED NDE PERFORM PRESSURE TEST AS REQUIRED BY ASME SECTION o
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A MOCKUP WILL BE CONSTRUCTED TO SIMULA TE THE
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PRESSURIZER LOWER HEAD AREA 1
1 THE MOCKUP WILL BE USED FOR WELDER QUALIFICA TION IN ACCORDANCE WITR THE APPLICABLE REQUIREMENTS OF ASME SECTION IX G SECTION XI THE MOCKUP WILL ALSO BE US$D TO DEMONSTRA TE THE ENTIRE REPAIR PROCESS & TO TRAIN THE INSTALL A TION PERSONNEL I
MOCKUP TRAINING & WELDER QUALIFICA TION WILL INCLUDE ALL ANTICIPA TED PROTECTIVE CLOTHING WHICH MA Y BE REQUIRED, INCLUDING RESPIRA TORS
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MOCKUP TESTING (Con t. )
i DEBRIS CHARACTERIZE TION:
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THE AMOUNT OF DEBRIS GENERA TED INSIDE THE PRESSUR-IZER WILL BE MINIMIZED AS MUCH AS PRACTICAL.
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DEBRIS IS EXPECTED TO CONSIST OF SMALL PARTICLES OF METAL FROM THE GRINDING & DRILLING OPERA TIONS, AND.
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o DURING THE MOCKUP DEMONSTRA TION ALL DEBRIS GENERA TED
.BY THE REPAIR PROCESS 'INSIDE THE l MOCKUP WILL BE
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COLLECTED AND CHARACTERIZED.
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THE EFFECT OF ANY DEBRIS, AS CHARACTERIZED DURING D
THE MOCKUP DEMONSTRA TION.
WHICH MA Y REMAIN IN THE PRESSURIZER AFTER COMPLETION OF THE REPAIR WILL BE Y
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MA TERIAL CONSIDERA TIONS
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. THE' PERMANENT REPAIR ~ WILL RESOL VE= THE MA TERIAL -
o CONCERNS WITH THE EXISTING TEMPORARY REPAIRS, AS FDLLOWS:
THE SEAL WELD JOINING THE N0ZZLE TO THE VESSEL ' CLADDING 'WILL _ PRECLUDE EXPOSURE OF' SA-533 Gr VESSEL SHELL TO BORA TED WA TER r
USE.0F ENiCrFe-3 WELD MA TERIAL WILL ELIMINA TE CONCERN WITH HYDROGEN EMBRITTLEMENT' AND 1
o, STRESS CORROSION' CRACKING OF EXISTING LOW ALLOY (E8018) WELDMENT ON PRESSURIZER OD SURFACE a
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MAKING THE BU'TTER WELD LA YER ON PREPARED CA VITY ij o
THE STRUCTURAL: WELD JOINING THE BUTTER LA YER' TO 0
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N0ZZLE WILL BE MADE PER ASME III l R o_
N0ZZLE WILL BE INCONEL 600 THERMALL'Y TREA TED A T I
1300 DEGREES FAHRENHEIT PLUS OR MINUS, 25 DEGREES FAHRENHEIT FOR 16 HOURS o
WELD MA TERIAL WILL BE ENiCrFe-3 (INCONEL 182) FOR.
THE HALF BEAD BUTTER ' WELD AND STRUCTURAL WELD
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o INCREASE PREHEA T TO 450 DEGREES FAHRENHEIT TO 550 DEGREES FAHRENHEIT FOR MINIMUM OF FOUR (4) HOURS L.
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COOL TO AMBIENT TEMPERA TURE FOR 48 HOURS: UT AND PT U
THE BUTTER L A YER l'
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INSTALL N0ZZLE AND COMPLETE THE STRUCTURAL WELD JOINING TH$ NOZZLE. TO THE BUTTER L A YER.
PERFORM PROGRESSIVE PT EXAMINA TION DURING DEPOSITION Or 1
STRUCTURAL WELD.
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WELDING PROCEDURE QUALIFICA TIONS l
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DISSIMILAR METALS (BUTTER LA YER ONL Y)
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MICR0 STRUCTURAL TESTS BGW PERFORMED ON FIVE 9'
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- HA VE DEMONSTRA TED THA T THE HALF
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BEAD TECHNIQUE HILL NOT LEAVE ANY UNTEMPERED MARTENSITE IN WELD HEA T AFFECTED ZONE
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BGW HAS THIS PROCEDURE A VAILABLE a
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BGW IS PRESENTL Y DEVELOPING THIS PROCEDURE
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