IR 05000249/1976027
| ML17252B135 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/30/1976 |
| From: | Fiorelli G NRC/RGN-III |
| To: | Brian Lee Commonwealth Edison Co |
| References | |
| IR 1976027 | |
| Download: ML17252B135 (8) | |
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UNITED STATES NUCLEAR. REGULATORY COMMISSION
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REGION 111 799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137
. OtC 3o1976 CENTRAL flLES (!ommonwealth Edison Company ATTN:
M:t. Byron Lee, J Docket.No. 50~249 Vice President P.O. Box 767 Chicago, Illinois 60690 Gentlemen:.
This refers to the inspection cop.ducted by Mr. R. J. Cook of this office on December 7-.9,. 1.976, of activities at Dresden Nuclear. Power Station, un*it 3 authorized by *NRC Op,erating Licens-e No. DPR-25 and to the discussion of our fihdings t*l!'...th Mr. Abel at the conclusion of the inspectio The enclosed copy of our inspection report identifies areas examined during the inspectio Withinth~se areas, the inspection consisted of a selective examination.of proc~dures and representative records, observations, and interviews with personne No items of noncompliance with NRC. requirements were identified during the course of this inspectio In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, copy of this letter and* the.enclos.ed inspection repo~'t wil be placed in the-~RC's Public Dociiment Room, except as follow If this report contains information.that you or your contractors believe. to be proprietary, you must apply in writing to thi office, within twenty days of your receipt of this letter, to withhold such information from public disclosur The application must include a full statement of the reasons for which the information is considered proprietary, and should be prepared so that proprietary inforll!ation identified in the appli.cation is contained in an en.closure to the applicatio /
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Commonw~aith Edison Coinpany
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.. ___,,/ ":.1*21!:.. -. DtC 3 *O 1976 We will gladly diseuss any questions.you have concerning this inspectio Enclos'::ire:.
IE Inspection Report*
No. *os0-249/76-27 cc w/encl:
Mr. B. B. Step,henson Station Superintendent
- TIC Anthony Roisman, Esq.,
Attorney
. Sincerf71Y yours,
~aZn0* :::<~<~~
Gaston Fiorelli; Chief Re~ctor Operation~*~nd Nuclear Support Branch* *'
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UNITED STATES NUCLEAR REGULATORY COMMISSION
._ OFFICE OF INSPECTION AfID ENFORCEMENT
REGION III
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. Repc>rt of Operations Inspection IE Inspection Report No. 050-249/76-27 Licensee:
Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
'Dresden Nuclear Power Stati0n
.Mor~i~~ Illinois Type*of Licensee:
BWR (GE)* 200 /and* 810 HWe Type of Inspection:
Announced, Spe;cial Dates of Inspection:_
December 7~9, 1976
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Principal Inspf!ctor: ~R!
J. Coo _. _
Accompanying Inspectors:
None Other Accompanying Personnel-:
None
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Reviewed By: '. lrittle, Chief Nuclear Support Section Lic~nse No.. DPR-25.
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I SUMMARY OF FINDINGS Inspection Summary An inspection was perfoi.med' on December* 7:-9*, 1976., (Unit" 3, 76-27):
regardin,g the review of high energy.pipe break and impingement restraint Construction prints were reviewed for compatibility of design intent and accessible HPCI turbine steam and feedwater line restraint installations were physically examine Enforcement Items Non I Licensee Action on Previously Identified."Enforc.ement Items None.dnspec te Other Significant.. Items Systems and Components Non Facility Items (Plans and Proced~res)
None inspecte Managerial* Items Non Deviations Non Status of Previously Reported Unresolved Items Non Management Interview A manag"ement* int:erv:i.kw was conducted with Mr. Abel, Administrative Assista_nt and: o'ther members_ of the staff on ri.ece_mber 9-;*.1976, at the comple{ion**bf *the i~spe~t'ion. Mr. Steptie~s;n, Station *:Supe:rintendent,.
was' contacted by teiecommunic.ation subseque_nt_,to_ th? cdmpJ.~tion of the, inspecti.o The following items were discussed:
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. ;.. -... * The adequacy of the U-bolt restraint fo~ liPci 1 to withstand a postulated. pipe break load:~ng was discusse The licensee stated,,
that more engineering evaluations-would be performed and-any necessary co.rrective*action taken_.* (Par"!graph 3, Report Details)
The instalTation of the*' correct bolt leri:gtli and material impingement protection restraint JiCV-1 was discussed.. * The liCepsee stated that the designed bolting wouJci be* procured and install~d~
(Paragraph 4, Report Details): The absence of impingement protection for Essential Service Cable Pan ESS-2 from a postulated HPCI turbine steam line break was
'discussed._. The licensee stated that _it would.be documented in a Phase II report tha:t the ESS-2.cables are hot required to -mitigate.
. the consequences of that s:tea'.m f}ne* breaR; or t~ bring the r'ea,ctor' *
to cold shutdown. * (Paragraph 3, Report Details)
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REPORT DETAILS
- 1. * Persons.contacted J. Abel,-Administrative Assistant F. Willaford, Q~ality ~ssurance Enginee~
R. Zentner, Station Construction Engineer J. Kolanowski, Unit2 Lead.Engineer D. Maxwell, Qualit.y Control Inspector G. Reimers, Technical Staff Engineer P. Donnelly, Sargent and Lundy Field Engineer H. Kirstein, Sargent and Lundy Structural Design Engineer General !/
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During the Fall 1976 Refueling Outage, the licensee installed add;itional pipe whip resuraints and' impingement prdteetion at criiical locations to reduce the ~ostulated consequences. incurred from high energy pipe break An in'spection was performed: to verify that the additional res~r~ints were iµstalled as per intended desig Main steam pipe and feedwater pipe restraints in the vicinity of the pipe tunnel a:,nd ff; P. feedwater heater* bay were not examined.,
At the time of the inspection, the plant was
- operating and limited stay time was permitted in these area An inspection is planned to examine main steam and feedwater*pipe restraints at a later time when the plant is shutdow Steam to the HPCI Turbine High ene.rgy pipe restraints and impingement protection for the steam line to the HPCI turbine. were exam_ined and compared to the*
construction print Prior to this examination.:the construction prints were reviewed with particular*attention to those locations
. with obvious breaker destg H..
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. ig energy pipe restraint esignate
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consists o rest:rairiing the pip-e with a high, st:rength alloy steel. (ASTM-A-193-B7) U-bolt ~
Exami!iations of this restraint reve'aled that the.HPCI turbine steam line.was not geometrically centered within the confines of the U-bolt as designated by the construc-tion prints. It could not be determined whether the U-bolt restraint was centered at the time of constructio Because of the large demands placed on the,. U-bolt during_ postulated* steam
- .. line break, the. ltcensee plans. to have their Engineering Depart-
.nient ievalucite wI:iether' the present design iSiadequaj:e with the pipe :in' close. p~oximity to one leg' of. the ff-bc;>lt artd/ or" whether any :com{>licatioIJ.s inay be de,ri;veci' from;; potellt:i~i' obstruction of* HPCI
- t:uribme steani line mot.ion. *
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Dre.sclen 'Station Units 2 and 3.Speciar Report No. 37, Revis'fon* 1,.. *
dt:d February, 197 Lt:r., IG. A. Abrell to D. L. Ziemann dtd 9/f6/7 Desiigna*t:ed PWHP-1 '!.On: Sargent and Lundy Drawing No. B-88 : *-*... -*-:-:;";-**--*.-*~ -*-~-* -:--:-:--****** *.*:*******-*--:-";~*---***.
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_,.. Hi~h.~n~y :pipe.restraint designated HPCrc/-1l/ had the. vertical
- member:.. (one.of *:two anchor points) anchored at the ceiling with' a plate*. 3:.Wll four nominal 1/2 inch diameter wedge;* anchor bolts*
Dis-cussions With~Sargent and' Lundy engineers revealed that th postulated force from pipe rupture at this location. would be in a horizorir.al -direction and t-he ceiling support plate would be loaded in comp.iressio The anchor bolts appear adequate to s\\:;pport the restram:t:.we.igh Installalt.i.on of impingemen5
~yotection restraints designated HPCIL1, HPCIL2,.and HP~r~3- -
was ex~mined and appear to b:
adequat:e *t:o,protect ceiling, suppression chamber and LPCI lin During ltihe e}Camination of pipe whip restraints on the steam line to the:HI>.CI turbine,. it was noted that an essential service cable pan in c.'ih~e proximity to the first 45° bend up.stream of the. south wall was afforded no protection from postulated pipe ruptur Thro~~h print comparisons, the cable. pan was identified as ESS-This i4entification could not be established from the cable pan marking The.. licensee stated that the cable pan did not require protection as 'these cables are not required, to* "mit1gate the consequences -of that steam lin31break accident and place the reactor in a co.1.-d <shutdown condition."-
The licensee stated that. redun-dancy coul*d be lost *but* not function for those systems controlled (and/or powered) from cab:J.es contained in the above.referenced cable pan. 'The licensee has agreed to confirm in a Phase II Ana-lysis o:f :Effects of Pipe Break Outside the Primary Containment Suppl5Re.Utal;Report (due early 1977) that these cables meet the above ctiteria.'
Feedwat:er *Piping During !the :,examination of high energy pipe break and impingement.
proteci:fuon restraints, it was noted that two nuts \\Vere missing from a bolted structure steel fitting for impingement protection from eondensa.te booster lin This impingement protection restraint is. designated as JICV-1 on. Sargent and Lundy Drawing B-886.. * *Further investigation revealed that the fitting was intended to 'he assembled using high strength bolts (ASTM-A-325)
rather t:han :the studs which were installe The licensee indicated
- that they *wer;e :aware of the situation anci that delivery of high
- strength bt:>1its ;;was expected in. the immediate.futur During.the inspect:im!l,,-* !:h.l,gh :strength bolt;s were received and* in~tailed'.;
._However:!> t:he ibol;t-s were, not-of the proper len:gth, and a full! nu ti Jb Designat:ed JP,1.\\1HP_:2,on Sargen~ and Lundy,Drawing No. B-88 Ibi Designated.l".'.filIP-.1.~ JIHP-2 and JIHP-3 on Sargent and Lundy Dra~ing Ibid>> Ap'pendff:x';A~
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I width could not be engaged in the final aslembl Th~ license~
- is attempting*to procure the proper length high strengthbolts and* will* finish the installation upon receip The compatibility of material for 4-foot rock bolts used to anchor'.
feedwate'r pipe whip restraints was verified from. shipping order from the supplie The material and size of bolts received agreed'
with,the design specificatio.
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