IR 05000237/1985004
| ML17195A745 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/11/1985 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17195A743 | List: |
| References | |
| 50-237-85-04, 50-237-85-4, NUDOCS 8503260412 | |
| Download: ML17195A745 (5) | |
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U.S. NUCLEAR.REGULATORY COMMISSION REGION Ill Report No. 50-237/85-"DRS)
Docket No. _50-23 License No. DPR-19 Licensee:* -C-0mmonwealth Edison Company P:. o. Box 767 Chicago, IL 60690 Facility Name:
Dresden.Nuclear Power Station,. Unit 2 Inspection At:
Morris, IL Inspection Conducted:
Februaryl, 1985 k~
Inspector:
. Approved By:
.W. J. Key D. Dani~lson, Chi~f Materials & Ptocess~s Section Inspection Summary
. Inspection on February 1, 1985 (Report No. S0-237/85.:..04(DRS))
- /o/rr Date Areas Inspected
Review* of Reactor Water Cleanup System pipe replacement program and.pr:ocedures, rev.few o.f welder qual ifi cat i ans, observation of pipe *
spool. -fabrication and welding, review of weld radiographs and traveler Resul~s:
No items of noncompliance or deviations.~ith NRC r~gulation~ ~ere i dent i fi e,,.-------*- -
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DETAILS Persons Contacted Commonwealth Edison company (CECo)
- *- Hy~ka,* ISl Coordinator
- 0. Schildgen, ~C Engineer C. Anderson, QC Engineer William A. Pope C.onstructi on Comp_any (Pope)
J. Tay"lor, QC Foreman
- Identifies those attending the entrance and exit meeti.
Augmented Inspection As a result of inspections performed in accordance ~ith IE BulletiMs 82-03,
- Revision 1, an.d 83-02, and the NRC Order *dated August. 26, 1983, the NRC in Generic Letter 84-11 directed all ~icensees o~ -Operating BWR's to develop a reinspection program of certain stainless steel piping.welds suscepti-ble to intergranuiar :s.tt;ess corros.ion-cracking (!GS.CC}~ * The -
. reinspect ion program w~s ~req.uired to. inspect st~inless st.eel_ reactor: 1 _: *..
pressure boundary we 1 ds * i ri piping with diameters *greater than or equa*l to 4 inches in -systems with operating temperatures greater than 200°. The inspections are required out to the second. isolation valv During this Unit 2 refueling outage, (see NRC Report 50-237/84..;.21) the litensee de~el6ped an augmented inspection program in actordance with NRC Generic Letter 84-11 that included welds in the systems listed belo This program was deve1oped utilizing a sampling appro~th with various criteria applied including multiple systems, piping sizes, corifigurations, and known crack Augmented Inspections (1)
UT furnace sensitized safe ends and welds (2 ea.-12 11/l ea.-28
/
2 ea.-4 11 )
(2)
UT Recirculation inlet thermal sleeve welds (2 ea.-12 11 )
(3)
UT Feedwater nozzle bores, inner rad. and safe ends per NUREG-0619
.(4 ea. -12u)
. (4) 'NRC Generic Letter 84-ll: Recirculation system (3 ea.-4 11/12 ea.-12 11/6 ea.-22 11/7 ea.-28
) Control Rod Drive (CRD) system (5 ea.-4 11 ) Shutdown Cooling system (2 ea.-14 11 and 3 ea.-16
) Reactor Water clean-up system (1 ea~-6 11 /7 ea.-8 11/4 ea.-10
) I sol ati on Condenser syst~m (6 ea>12 11 and 4 ea. -14
)
0 A 11 Low Pressure Coolant Injection (LPCI) system (3 ea.'-16 11 )
g.. *
116 11 LPCI system (4 e.a. *16 11) Rea<:tor head vent (3 ea. -4 11 ). *Unrepaired cracked welds (2 ea:.. -12 11 and 1 ea.-;-28 11 ) Jet p~mp instrumentation (10.ea.)
(5)
Scram discharge volume modification.baselln The sampling *plan for the augmented program included.84 weld During inspection of the Reactor Water Cleanup {RWCU) system new crack indica-tions were identifie No.new c~acks were found in any other systems examine Due to the i.ndi cat ions i dent i-fi-ed in the RWCU system, a 11 accessible welds i-n this system were uitrasonically examined, increasing the sample size to 102 weld The total welds examined included:
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weld, 24-8 11 welds, and 5-10 11 weld Crack indications were reported in 15 of the 30 welds examine Ten were located outside bf the containment and 5 were inside the containmen Ultrasonic examination of welds scheduled for this refUeling outage,.as well as those identified in the augmented inspection program, were performed by.Leve 1 II and II l pe.rsonne 1 who were quali-fied by hav.ing successfully completed the practical examin-ations required by IE Bulleti.n 83-0 During a previous exit meeting, NRC Report 50-237/84~21, the licensee informed the inspector that their plan was to -replace all RWCU system piping outside of the containment and overlay the welds i_nside containmen That plan was subsequently changed to inclu.de the. replacement of piping insid.e containment from MOV-2-1201-1 through penetration 1201-G-.107, leaving only -one weld in the containment to.be overlaye No items of noncompliance or deviations were identifie ~
Repair Program A repair program, N.o. M-12-2-164, for replacement of the RWCU system piping and containment penetration flued head froni MOV-2-120.1-1 through penetration Xl13 up to MOV-2-1201-2, and MOV-2-1201-.3 was developed for the licensee by Nutec Purchasing, fabrication of spool pieces, and installation is being performed by the William A. Pope Construction Company (Pope).
Repairs to the RWCU system are being mad~ in accordance with the ASME Code Section XI ~980, including the Winter 1981 Addend The 10 11 diameter section of pipe from MOV-2-.1201-2 to the 10 11 x 8
diameter reducer has been replaced with 8 11 diameter pip A safety evaluation performed by Nutech states that "pipe stresses* are to be kept within the ori gi na l code. for loading.Conditions i denti fi ed in the FSA All.single event failures and.LOCA events described fo the FSAR still apply.
No items of nontompliante br deviations were identified:
.* Material Certification The inspector reviewed Pope purchase orders (PO), receipt inspecti~n report~ (RIR), a~d certified material test reports (CMTR) for materials befog ins ta 11 ed i.n the RWCU system as fa 11 ows:
Purthas~ Order N SA~158 schedule 80, BW Tees, 304L SA403 heat code F0395, RIR 123
11 schedule 80, elbows 45°, 304L SA403.heat code F0404, RIR 123
11 schedule 80, elbow 90°, 304L SA-403 heat code F0400, RIR 123 8-" *x 1 11 3000# so 1, SA182-F316 heat code 131 BN, RIR 123
11 schedule 80 pi~e, SAj12-TP304L heat code C7521, RIR 113 Purchase Order No: 843SR-162 u schedule 80 pipe and elbows, heat code 467951, RIR i35 Purchase Order No. 843SR-161 * 8 11 * ~,chedute 80 el qow,. heat code "F0500, RIR 12~
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Purchase* Order 84JSRi.587:
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sche(j~le-*eibow, h.eat *code F0412; RIR 11..
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t* Weider and Procedure Qualification.
During the in~~ector 1 s review of weld travelers, the welders and welding procedures listed below were selected tor r.eview of qualification records.. Procedures No. GT-SM-8-8-CI, Rev. 3, PQR-IV-A No. GT.:.SM-1-8-CI, Rev. 0, PQR-Welders StamE N Method L. Weaver AG GT AW/SMAW c. Wells AJ GTAW/SMAW T. Jurgens y
GTAW/SMAW L. Craven w
GT AW/SMAW M. Swindeman H
GT AW/SMAW 0. H.igdon
.F GT AW/SMAW No items of noncompliance or deviations were identifie., Radiographic Review
- Radiographs -of welds *in *the *RWCU system identified.below were reviewed by the inspector for radiographic techni-qll **and acceptance to the ASME Cod Weld N A 8..,.19""A 8-7A 8-lGA.-Rl 8-2A
- 8-3A 8-5A Line N.1-8
2-1201-8
2-1201-8
2-1202-8
2-:i20.2-8
2-1202-8
No items of noncompliance or deyiations were identifie.
Exit ~eeting*
An.exit meeting was held with *licensee representatives identified -in the Persons Contac:ted * paragrap The scope and f-i ndi ngs of the inspect: ion were* discusse The *inspector also -discussed the likely,informational content of the inspection report ~ith regard to documents or processes reviewed by ~the inspector during the inspecti-o The li cehsee.did not identify any such documents/processes.as proprietary.
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