IR 05000280/1981007
| ML18139B271 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/17/1981 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139B270 | List: |
| References | |
| 50-280-81-07, 50-280-81-7, 50-281-81-07, 50-281-81-7, IEB-79-13, IEIN-81-04, NUDOCS 8104300304 | |
| Download: ML18139B271 (7) | |
Text
Report Nos. 50-280/81-07 and 50-281/81-07 Licensee:
Vi rgi ni a" E.l ectri c and Power Company.
. Richmond,. VA 23261 Facility. Name:
Surry *
Docket Nos. 50-280 and 50:-281 License. Nos.. DPR-32 and DPR-37 Inspection at.Surry site near Williamsburg, Virginia
. Inspector: 811&~
Approved* by.: * *1clt..
SUMMARY
. A. R. Herdt, Section Chief Engineering I'n spect ion Branch
- Engineering and Technical Inspection Division Inspec.ted on March z;..5, 1981 Areas Inspected Date Signed
. ifti~ned This: routine-, unannounced. inspection involved 24-inspector-hours on site in the areas of steam generator replacement (Unit 1); IE Information Notice 81-04, Cracking in Main Steam. Lines (Units 1 and 2); and IE Bulletin 79-13, Cracking.in Feedwater Lines '(Unit 1).
Results, Of the three areas inspected, no violations~or dev*iations were, identifie s 1 o. 4 a o o :,ot/
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REPORT DETAILS Li,.r, Persons Contacted
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Li censea Employees,
- J... * L.. Wi 1 son,. Stat.ion-Manager
- R. F: Saunders-,. Assistant Statfon Manager
- F. L... Rentz:, Res*; dent QC: Eilgi neer*
- J. W~ Patrick, Maintenance,.Superintendent
- T. W. B.rombach,_. NDT Superv.i sor
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H-. C. *. Gant:, Resident* Engineer, Construction L. E. Creech, Construe.ti on* Supervisor, Construction R~ F. Driscol T,. Resident QC Engineer (Construction}
C. Emb 1 e.r,, We.J ding:* Eilgi neer**
J. Dal torr, NDT Mechanic
H. L., ~rifflths, Level IIT Examiner
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Other* licensee' employees. contacted included. construction cra-ftsmen, techni-cians:, security force members,. and office personnel.
Other-Organi'zatfons F.. D.. Forres.t~. Level IT Exam.i ner,. Pittsburg Tes.ting Laboratory ( PTL)
W; J". Pender-,. Project. Manager-, Chicago Bridge::-and, Iron Company (CB&I)
J*. Edgar,. We 1 ding: and: QA Superintendent,. Chi cage. Bridge and Iron Company (CB&f)i
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NRC~ Resident Inspectors;.
- D... J. Burke
- M:-. Davi s,
- Attended. exit intervie '.
Exit Interview, The.- inspection scope, and. findings, were, summarized. on March S', 1981 with those-persons indicated** in paragraph* r above
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Licensee Ac.t.ion on Prev.iou.s.Inspection Findings.: Not i'nspecte Unresolved Items Unresolved i terns, were.. not i dent i fi ed during this inspection.
2 Steam Generator Replacement - Review of Welding Activities (Unit 1)
The inspector observed/reviewed the pipe welding activities and procedures, described. below. to determine whether these activities re-lative to steam generator replacement ar,e being accomplished* in accordance with regulato.ry requtrements, applicable. codes, standards,. and licensee commitment The applicable: code, for this we-lding: is the, original construction code, USAS B31.1.0~196 ' CB&I WPS E70S-2/E7018#1/91534, Revision 2 and. the associated general procedure, 11General W~lding Procedure Specification For* The Gas Tung-sten Arc Process Nuclear Power Plant Components
were-reviewed, a-lthough the procedures had: not been-final issued for* production us During this review:, the inspector* noted that the qualified thickness for each process was; not adequately defined: in the WP The WPS was revised during the. inspectfon,. prior to issue\\, to define.-the qualified thickness for each proces Two CB&I welders, HGB. and DJS,. were observed in the process of quali-fy; ng on heavy wa 11 carbon stee 1 pip The* inspector* dfscuss-ed the status of major pipe welding. with site personne:l __
Thee following, is: a, summary.. of the status:
( 1)
11AII Generator (2)
118 11 * Generator (3)
11C 11* Generator-
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Main steam (MS) piping.has been machined ready for*-fitup in containmen Feedwater (FW) piping is. fit and being inspected Spool EP-5 reactor coolant (RC) piping is*
welded out and being prepped for in service inspect.ion (IS I)
Spool EP-4 RC piping* i,s being machined in the shop:
MS piping is irr the process.of being shop fit FW.piping is in the process of being shop fit Spool EP~s RC. piping. is welded out and being prepped for ISL Spool EP;...4 RC p.ipi ng. is ready to take. a template in the.. containment for shop machining:
MS piping is fitup ready for*welding FW pi p.i ng must be cut out and rewe. l ded due to rejected. we 1 ds Spool EP-5 RC: piping has been installed and final accepted Spool EP-4 RC. piping is in process being fitup Within the a.reas inspected, no viol at.ions or deviations were identifie t
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- IE Bulletins (IEB)(Unit* 1)
(Closed) IER 79-13,. Cracking in Feedwater System Piping*.
As discussed' in NRc* letter* dated* August 27, 1979, the* licensee committed* to re-inspection of the feedwate.r nozz.l e-to-reducer we.Td: areas at the next. refueling outage:
after replacement of the. reducers.. This inspection has: been performed during: th*e current steam generator replacement outage afte-r* approximately five months o"f plant operation..
The. inspector* reviewed* the radiographic film for this inspection. The. nozzle to; reducer weld. film, are" identified as*
follows:
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Line: 1411 WFPD;..lT.;.601 FW-18-A
- L; n e 14.n* W.FPD.;.9:...60 FW-18-Line 14 11 WFPD...-13.-6 FW-7-The, RT was, performed in accordance: with VEPCO Procedure NDJ-10.1, 11 Radio,-
graphic. Inspec.tion o.f Pipe*and. Plate We-ldsu**,. except that evaluation was to the 197T Edition of ASME,Section III, Subsection NC, paragraph NC;...5000 to the: 2T quality 1 e.ve-Ba-sed on the. above. review, pre_vi ous IE: II i nspec.ti ons (IE:.II. Reports. 280/79-50,. *280/79-45 and 280/79-37), and. licensee*: letters of response dated July 13,. 1979, July. 18, 1979, July 23.,. 1979*, August 21, 1979,.
September 5:, 1979:, April 8,. 1980, April 2~, 1980 and November 7, 1980, this lEB-. is closed..
Within the-areas' inspected, no. violations or* deviations, were ident.ifie.
LER Review* (Units, land: 2}
LER 80-067 ( Unit l}
Indjca_tions. were-found. in* the MS elbows at the steam generator outlet nozzle duri n.g* removal of.these-e-1 bows. for steam* generator* replacement... The-i ndi ca-tions were: determi'ned to be original construction weld defects and no service induced*.
The licensee: performed. a records review for* MS system welds; and found that for welds FW-10 on loop. 11A11* and FW-18 on* Toop 11 811' the, radiographic. (RT) film couJd not be0 locate In addition., the. film density was out of code, requirements, for two. othe.r welds on loop 11A11 and the repa.ir film could not: be. located for* another weld on loop 11A11 ** At this time, weld FW'.:'"'~, FW,...S. and; FWr--10 were! RT inspecte Linear indications were* noted in the' base material adjacent to FW-10 ( the upstream* weld on the i n-1 i ne tee fitting. connecting: the vertical run or 30 11 piping to the safety relief valve header and.. the: 30 11 MS: line-of steam generator 11A11 ). The weld at the other end of the tee: and. weJ ds at. both* ends of i den ti cal tees in 1 oops 118 11 and 11C11 l
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4-were* RT inspected and revealed similar linear indication The NRC wa notified and issued Information Notice 81-04,_ "Cracking in Main Steam Linesl The in spec.tor' made the.. follow:i ng observat.ions/revi ews relative to thi S:
problem:
- As part: of the* LER' acti ans the. Ti censee reviewed a. number of MS-origi naJ cons*tructi on fi Tm.* which were determined to be. acceptab 1 e,.
The inspector* re.viewed. ac sample of these film con s.i sting,* of the'. fa 11 ow-i ng:.
we.*l ds:::
(1)
Unit r Line 30~'\\- SHP-2-601.-10 to 21 FW-16-Line* 3011' SHP;..2-601-29-to 30*
FW.-41 Line. 30 11' SHP:....2-:-60I-23A to va Tve *
FW::--262 ( 2)
Unit. 2 line: 3011' SHP-R-103:--601 FW:--7 Line. 30 11* SHP;..R-lOI-601 FW-6~
Line:- 30" SHP-S:-101-6 FW-fo,
. Thes:inspector reviewedresults-of recent re-R-T inspection of welds FW-4 and FW-8 on line: 30" SHP-l-601. (Unit 1, Toop "A") which revealed no rejectable,: indications... The* RT was. performed in accordance* with-procedure QC.-RT-1,.
Rev.i*s*icm* 0,.-
"Rad.iographic: Examin-ation 11,
with acceptance.- in accordance'. wtth ANSI. 831. L-1967, the original construc:-
ti on code.-.
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As-- indicated above*, once indications were.- found. in the base material near FW-10 in* loop 11A11 *, the 1 icensee, re:-radiographed the. weld areas* on*
both ends:, of the tees*. on a*ll three loops. of Unit L This RT was to the same procedure and code requirements as stated in b. abov All w~ld areas exhibited the same indications to various degrees. The inspector
. reviewed: the.s.e RT fi 1 ms.which covered the fallowing we 1 d. areas:
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Line 30 11 SHP-l-60I (Loop*
11A11 }
FW-10 FW-40I Line 30'1* SHP;...2:-601 ( Loop 11811 )'
FW:-36,
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FW:-402-Li nef 3011* SHP-3-60 {Loop "C")
FW-22.:
FW-403*
In general all weld areas exhibited similar indications. Inmost cases the, i ndi ca.ti ans. were at the, intersection of the counterbore and coun-terbore. taper.. In adcUtion", some., we:lds had* similar indications at the toe.- of the, root. pass-.
The, indications were continuous in* most* cases but intermittent in some, welds, generally-extend.ing. circumferentia*lly from the.~ O'clock tQ the 8 O'clock position_ This area corresponds tQ the. a reea-that. was found to be covered. in water during p Tant outages..
The indications* are broad and appear to be* sha Tl o A 1 so, in the general area;-- of the. i nd:i cati errs,.. which wou.l d be.. covered in water during:
outages,. the.re is. much evidence of corrosion pitting.. The inspector vi'sually observed the-inside, surfaces of a.ll six of th tee.- welds: noted above:.. One 11baat11 samp 1 e from the i nd.i cation area near*
FW:-22 and. 3;. 11boat!1* sample.s, from the indicat.ian. areas near FW:-401 had been removed fo.r metallurgica:l analysi Irr* addition, all other*
i-ndi cattan: areas had been ground ta same degree ta determine the: depth of the: defect. The, deepest. defect was approximately.. 100 11* dee The inspector* was able to. observe. some of the original indication. near FW:-22'.
The* indicatfon* area. showed corrosion pit.ting at. the surface of the, defec However,. the nature: of* the defect can* only be, determine from the* metallurgica-1 analysi General corrosion pitting was observed: at the 4: to a* O'c:.lack areas of all weld In addition, the indication at: the.. toe of the-weld in FW,-401, observed by RT, was also observed* vi sua rly. It had* the* same surface appearan*ce,. i.e., corrosion pitting:,,. as the i ndi ca:t.i ans at the. counterbore taper-...
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- The,. inspector* reviewed; the. u]trasanic. (UT) inspection repo.rt. for similar* Unit~ 2' tee., welds-.
The UT inspection was performed with an ASME Sec.ti'orr XT te.chn i q ue* using* a 10~ ca:li brat i arr notch and a 60°' ang*l e beam transducer*.
The. MS, 1 ines. were at opera.ting: temperature* during: the inspect.ion*. Prior to the UT i nspect.i an, the. UT setup was checked ou on.. known*- ind.ication areas in Unit L Discussions ~ith plant personnel revealed that due-to interference:- from the-inside, geometry at. the i ndi cation area, and the. depth* of the defects compared to the 10%
calibration* notch, the* known indication cou.ld~ not: be-define It should be. noted that the depth of the indications as noted by grinding are less than-the 10% calibration notch*.
The. UT revealed. no indica:-
ti'ans of defects*.
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The ltcensee made a commitment to visually or RT inspect Unit 2 tee we.l d areas during the upcoming outage-in April 198 Within-the areas inspected, no violations or deviations were identifie t
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