IR 05000237/1990024
| ML17202U943 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/10/1991 |
| From: | Danielson D, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17202U942 | List: |
| References | |
| 50-237-90-24, NUDOCS 9101150103 | |
| Download: ML17202U943 (7) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION_
REGION III'
Report No. :. 50-237/90024(DRS)
Docket No.:
50-237 License No.:
.Licensee:'
Commonweal th Edison Company
. Opus West II Opus Place Downers Grove, IL 60515 Facility Name:
Dresden Nuclear Power Station - Unit 2 Inspection At:*. Dresden Site,. Morris, IL.* 60450 Inspection Conducted:
October 9-11, 23, November 20-21, 28-29,.
December 19-20; 1990, *and January 8, 1991 Inspector: ~"-1,~G~~
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_F.. Schapker
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Approved By:
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I D_ate D. H. Danielson, Chief Raterial~ and Process~s Section Inspection Summary
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Inspection on October 9-11. 23;.November 20-21. 28~29. December 19-20. 1990 and January 8. 1991 (Report No. 50-237/90024(DRS))
Areas Inspected:
Routine announced.inspection of 'inserv:ice inspection activities including review of p"rograni (73051)' procedures (73052)...
observation of work activitfes (73753),.data review. and evaluation (73755)-,
review and inspection of the licensee's.response.t.oJ~ener-ic Let;tei;_,88*01 a:nd *. *.
related activities (92703) and licensee event reports (92700)'">:'*.;;.:_ --
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- Results:
Of the areas inspected, no violations or deviations were identified:
During the course of.the inspection, the following were _noted:~_.:-~.:... *
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Based on the areas inspected, the lice~see<appea~~--~~;}u~ve -ari_:ef,:fP.S,Fi~e ISI progra The licensee contracts for ISI s*e"rvices" and performs-*~.
selected IS ISI is performed Jn ~ccordance wit1!. ASl'.{E ~o~e *-',-#'*c*},;~!:_~>:. *
requirements' utilizing state of the art equipment and procedures.....
O The licensee's inspection program for intergranular stress corrosion cracking (IGSCC) susceptible piping does not include.-the reactor water cleanup (RWCU) piping beyond the second isolation yalve as *required in
- Generic Letter 88-0..... -.- _.,,. --.
9101150103 q10111 PDR ADOCK 65000237 Y":':.\\:*
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DETAILS Persons Cohtarited Commonwealth Edison Company (CECo)
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E. Eenigenburg*, Station Manager D. Howenstein, Regulatory.Assurance
- .. *L.' Gerner, Technical Superintendent M. Horbaczewski, Technical Staff, ISI
.+*_G. Whitman,. *Te_chnical Staff,. ISI
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- M.. Strait, Tech~iCal Staff _Supervisor
- ~* Peterman, Regulatory Assurance Supervi_sor_
- K. Ya.tes, Nuclear Safety Administra_tor *
- S. Vercelli, *Nuclear Quality Programs Engineer e*
- K. Kociuba, Nuclear Quality Programs Superintendent
- D.. Lowenstein, -.Regulat;:ory Assurance Analyst*
B. Wilson,.Level III SMA.
., K. Beverly, Regulatory.Assurance*
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Lambert. McGill and Thomas. *Inc. '(LMT)
- E.. Thomas, Supervisor,: Level III.*
D.* Richey... NDE ExaminE!r; Leve{ II R. *May, NDE Coo.rdinator R. Lester, NDE Exam~ner, Level II
Hartford' Steam So{ler Inspection (HSB)
G. Bosley, ANII U. S. Nuclear'- Regu_latory Commission (NRC)
D. Hills, Sehior Res{dent Inspe6tor*
M~ Peck,_Resident in~pector
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- Denotes those present.at the exit meeting conducted*. Decemb_er 20, 199 +Deno.tes those participating in the telecon conducted January 8, 199 The NRC inspector also contacted and interviewed other licensee and contractor employee.
Followup on Licensee Event Reports (LERs) (92700)
Through review of ISI data, observations of NDE examinations, and overlay repair welding, the NRC inspector determined.that the reportability requirements were fulfilled and corrective actions were appropriate and adequat.:
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(Close'd)
LER 90014-00 (237/90024-00):
Indication of Through-Wall Crac on Shutdown Cooling Piping Weld 16-8 Due to Intergranular_Stress Corrosion.Cracking (IGSCC) (92700)
The licensee.identified IGSCC indications utilizing ultrasonic ex~ination on thre~ 28" Catego-ry "D" welds _(Gerierfc Lett.er (GL) 88-01).
These ~ndications *were sized to be 10-40% -through:-w.~11 with
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circumferential *and* axial indications..The detec-t_ion of these*
inqicatlons'result:ed in sample expansions to included seven'4",* fourteen 12", one 16", two 22", and n~ne 28" recirculation welds.. Subsequently, -
a weepin*g indication_ was visually observe_d during preparation*.for.
ultrasonic examination. (UT) of the 16" shutdown cooling weld 16-8. --_ With
- further evaluation by the licensee-, it was confirmed that two weeping --
through-wall cracks we.re con'tained ih the -wel UT -examinatiC>n. 'revealed two circumferential IGSGG indications in the wel The first indiCation-w~s 16,5 inches in length and 33% through-wall with-100% thtough:wall in the two areas fc;>und to be. leakin Tqe se*cond indication was 3. 5 *inches-in length and 16% through-wan*. *, ;
All welds with confirmed IGSCC. _indications -we~~ rep-aired with. overlay *
welds-.
Each* of these repairs 'was fabricated to the GL 88~01 _criteria--
for -weld oyerlay repair The NRC insp_ector ob'served weld overlay,.
__ repairs in progress; reviewed 'Weld Procedure Specifications (WPS) -*and
- Procedure Qualification Records (PQR), and confirmed -the essential.
va~iables of the weld procedure.were being ~dhered to.. Oyerlay repairs are non-Code repairs which require approval from the NRG' s --Office of
- Nuclear Reactor Regulation. (NRR) *prior to *-application.. The licens_ee~.
contacted NRR a:nd.submitted thf required information conc:erning the overlay repair The licensee subsequently UT examined the weld overlays using'the EPRI technique for overlay ultrasonic examinatio All overlays were found to have sound overlay :material of sufficient*
thickness for Gate~or.y ~"E"- weldment The UT examinati6n of the overlay repair to weld 16~8 was.~limited'.due to the as-built weld configuratio On the "-Tee;,- ~:l.d~;~C)f': th~ -wet'J,'/th.e -
baseline UT which covered 100% of the affected weld overlay.material and the upper. 25% ~f the affected base ~aterial could,?~l>'ie~~:~.perform~:~}n *
one (1) direction (.toward the tee) due to the piping confi_guratio On the elbow side of* the weld, the baseline UT covered lQ.OX of the ov.er:lay materfal in two (2) _directions. - However, the ;-upp-er:;tsi~~bf--tne7f-fe-c 1ted base material (as required by GL 88-01) could on~y be examined for \\lP to SOX. of the weld circumference -due to the as-hll'ilt weld overlay *:i
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configuratio The NRC inspector discussed this devi~tio-n from* GL 88-01 requirements with NR NRR will review this examination limitation and advise the licensee of necessary modifications of the overlay repair to
. assure adequate UT examination, if require The NRG inspector
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contacted the licensee* on January 8, 1991, and informed the licensee that*this is an open item pe'nding review by the NRC (237/90024*01).
The iicensee' s cor.rectiv'e action was sufficient to weld was repaired with.industry acceptable methods growth in the wel assure this IGSCC
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to mitigate the crack
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Inservice Inspectio~ (ISI) Unit 2 (73051. 73052; *73753. 'and 73755)
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... General (73051)
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This 'was 'the fir$t outage of the third-period in the.second te year.Pla The ~icensee *contracted with Lambert., McGill,,.an Thoinas, *Inc. (IBT) to perform ultrasonic (uT) ;-. magnetic particle
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liqu.id*pen~trant* (PT), and visual ex.amination (:VT).:.
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Examinatfons were performed in accordance with ASME Section XI, 1977 Edition, Summer. 1979 Addenda.*.
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- Is{ Pr*ocedu~e Re_;iew (73052. 737532 The NRG inspec't.or' tevie:wed the/following NDE procedures:
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. CECo, Nondestructive Testipg. (Inservice.*Inspection.) DAP 11~8., Revi~ion'3.*
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CECo, "rreservice arid Ins~~i'ce. Ultras.oniC. *Inspection of
. Sim:il'ar *anc;l. Dissimilar. Metd.,Pipe Welds.. * a,t.~uciear*' * *
Stel;tions; ", NDT~C-2, * Reyisi6n 1 '*:.-
GEGo,
"Ut~rasonic. Inspect.ion of th~ Vess.ei: N,ozzle. Inner*
Radii.at' Nuclear: Stations," NDT-G-10, Revi:sion 10..
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CEGo, * "Ulti:as*onic Inspe~tion 'of; Flange Ligaments Between
.* Thre 0aded.* Bolt Ho~es," NDT~C-11',. Revision-.12.,
CECo, "Ultr~~onf~ Examination qf:Reactor Vessel W~lds to NRG
- Reg.: Guide 1.150 for Boiling* Water Reactors,"* NDT-G-30-79,
- Revision 0..
CECo,."Beam Spread and Refr~c
.. !ie4J~Afig;1e)rl~bemlhation ;t:~:'iNR:c Reg. Guide 1.150 for Boilirig.Wate'F'Reactor!i,.*.. NDT-C-'31-7:9, Rev~sion CECo,. "Nonaqueous Red Dye Liquld ~~~et~a~~::~~~in~~,i~n *f~~ *..
Section XI Class IW'B and IW'C. Cogipgnents.~or::J~ucJea~:,~..:.*.': :...
Stations," NDT-b-2, Revision 4: *.. c***,-" *-***
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CECo;*. "Visual Examination -. liJ'elds, *Pressure Retaining Bolting; and Co~ponen~_Internals,~ VT-1-1, Revisio CECo~ "Visual Examination - System Hydrostatic and Leak Tests," VT-2-1, Revision.
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0 0 CECo, *Visual Examination - Component Supports," VT-3-1, Revision CECo,
"Magn~tie Particle Examination for ASME Section XI Class IWB and !WC 'Components for Nticlear S~ations," NDT~B-!,
Revision. LMT, "UT Auto Sca-q Procedur~,' Operation,of the LMT 'Adam'
System for Pipe Weld Exams," iJIT,iuT-50, Revision LMT, "Eyaluation of the UT Data Using the urt:Adani.System with Remote Auto Scanners," )liT/bT-5, Revision * '
LMT, ""Written Practice,"* llfi/QA-6,' Revi_sion 2L
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, GE, ""Ove_rlay *Layout*,"'- 88~190; Revision, 2.".*.
GE; "Ferrite check," FM 8S--15~0D, Revision GE, "Weld Overlay," *srs-88-.!)02,, -Revision..
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'Review of IS'I Data I Material.. Equipment. NOE Pe~sorinel *..
'Certifications and Audits (73753, '73755).
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The NRC inspector review~*d the following documents* and determined.
. tha.t* the appliC:ab"le' QA/QC reqtiirem~nts were* n\\et:.
IS! Data Reports;
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Ultrasonic instruments, transducers,., and coupia.nt : *:.
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~ertitications;
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Liquid penetrant, ciean~r, and,<leveloper certifications;
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- Magnetic particle materials and equipment; NOE personnelcertifications",._compliance to SNT-TC-lA requirements*. and EPRI *certifications for IGSCC examinations_;
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Audits cif !SI activities:. QAA-12-90~04; QAA~l2-89-33, and*.
12-88-33*.
Observations of "Work and"Work Activities 03753)
The NRG inspector** observed the following work activities in
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progress:
Ultra*sonic examination (UT) of:
Reactor ves's.el (RV) flange to shell weld*, isolation' con'denser piping welds, recirculation piping and overlays including manua.l and 4-.
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- e automatic methods**, jet pump nozzle-to-safe-end weld, and RV head nozzle vent ~el Liquid penetrant examination (PT) of isolation condenser weld Magnetic particle *examination (MT) of* shutdown* cooling piping welds:*
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Repair welding (overlays) of recirculatio'Q. piping welds.*
Visual examination of RV internal *'nte tfr of.th~ RV flange *to shell weld *detected Ut ind~cations.on *
or. near the cladding and base metal. interface... These. indications
~ere sh~llow and appeared tO *be crack~ like reflector The
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licensee expanded the scope. of 'the examination 'to. 360*
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suspect weld (initial examination scope was *120°). *To evaluate the indications, the licensee performed PT of the clad surface and UT from the inside diamet.er (ID) ciad surfac No indications cif
. cracks were* idet1tifi.ed.. The NRG.inspector reviewed the UT and PT
"data and concluded the.indications werE:! contained within the cladding and were* geometric* r~flectors resulting in beam redirection; a UT phen~meha caused by changes in m:etallurg-ical
.grain structure which commonly.oc;curs in the UT examination of austeni tic stainless steel. welds...
- ~Ultrasonic exa~ination of re~frculatibn piping (GL 88~Ul) is
. di_scussed in Paragraphs 2 and 4 of this repor.t*.
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, No. violation-? or deviations. were identifie *'
' Examination.of Intergram.ila'r Stress c~*rro-~don. Crack CIGSCC) Susceptible Welds (GL 88*01) (92703)
The. NRG.inspector reviewed the licensee's plan for examination"of* IGSCC susceptible welds *in accordance.with GL. 88-0 The licensee's plan follows the GL 88-01 guidelines with the exception of the.reactor wate cl.eanup (RWCU) piping beyond the second i'solation * v*a.1 v The licensee is currentiy evaluating the cost and ALAM *:benefit of replEi.cing versus examining this pipin Due to. the high radiation. doses to p~rform the*.
e*xaniinations, the licensee is consider~ing repl.acing the piping with
IGSCC resistant pipin The licensee requested arid ~obtained*relief.,from inspec_tion of* this piping for this refuelling outage pending* the **
completion of this evaluation..
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The total population of IGSCC susceptible welds excluding.the above RWCU. *
welds is 23 This outage's augmented inspection plan contained a total of 85 welds. *Additional welds were added due to previously applied leak barrier ove.rlays which were built up to full stru.ctural overlays this outage:
As a result of flaws* *observed i~ welds in the original sample, the licensee expanded t.o a total of 166 welds as described in Paragraph
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2 of this repor The NRC inspector observed UT *examinations throughout the *outage and confirmed detection and sizing capabilities of the UT examiner One 28" recirculation pipe weld (PSI-2/2bl-l).~a~ reported by the NOE contractor to have a small crack indication; further examination by the
- licensee's Level* III concluded.the indication was not a crack but ID
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root geometr The NRC inspector observed the examinations by the NDE contractor arid the licensee, s examiner and concluded 'that the.. indication. appeared to..
have crack-like signals, but was very small and difficult to interp~e Both the NOE contract examiner and the licensee *examiner. are. qualifie~
. to ASNT~TC-iA Level III and EPRI,IGSCC detection requirement *
Each. examiner utilized *:t~e * s~me procedure *and useci<the s~e type of....
- equipmen Due to the probability that the* indica,tion is IG.SCC,: the*NRC inspector re~~ested :th~ l'i'censee. to 'include this: weld in the nex.
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refueling outage examination pla The. licensee agreed to; inspect the..
aho..;,e referenced indiCC!tibn during the next re°f:ueling outage, but did
- not agree to expand.their sample if the weld is *cracked (as required.. by:
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'.The licensee w111***submit *this proposal to NRR for thefr* *
- . appr~va Tpe inspector will review. thi.s i'ssue d~ring the n~xt...
refueling outa~e inspe~ti '..
. No violations :or deviations were. identifie Open Items Open i terns.are.matters whic~ have been discussed with the licen*see, which will be reviewed further by the inspector, and which will*iri~olve some action on the *part of the NRC.or licensee* or both. *An open item disclosed.during the inspection is disctissed in P~r~graph. ~...
6. *. Exit Meeting*
The Region III inspector met with_ licensee representatives' (denoted in Paragraph 1-) at. the.conclusion.of" the-inspection or:i December.20,* 1990, and du:dng _.a telecori with. Mr-..- G. Whitman conducted on *January. 8, 1991..
The inspector 'summarized:, the purpose and.finding!; of ~he inspectio'n'..
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The licensee*. representatives acknowledged th.is information.. The
inspector also discussed the likely informational content of the inspection report with* regard to documents o.r -processes. r.eviewed during the inspection. *The licensee representatives did not identify any s'uch *
documents/proce.sses as proprietar.
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