ML20138F714
| ML20138F714 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/26/1991 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20138D008 | List: |
| References | |
| NUDOCS 9610180043 | |
| Download: ML20138F714 (4) | |
Text
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( Carolina Power & Ligfit Company ' mm. - ROBINSON NUCLEAR PROJECT DEPARTMENT s POST OFFICE BOXf 790 HARTSVILLE, SOUTH CAROJ INA 29550 S t 'mJUN26 % . , ' 1:k , - y.gl ,,.RNPD/91-1523 Robinson File No.: , 1351,0E.y, , q ,., , 9. f-
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1M L+,, - United States Nuclear Regulatory Commiss, gion %;f.:g g-4,"F.;/ ,g ! M re ?g ; ,
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.i' UNIT NO.T2.~ S " .70% T" "M '
d DOCKET No? 509-261 U.WY ' ' /II F ^ '
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@h b NRC INSPECTION
. 50 26,1/91 REPOR[MTCEN5E 05VR&B UPP'EEHeNTAt1TSPONSE' "' " # ' 8 " NODR'
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% (' Carolina Power and Light Company hereby provides this revised response to the i 5
T)M l Notice of Violation. identified in Inspection" Report'50-261/91-05. This . c-response sdpersedes the ' original l response'9ated'May (13',"1991', 'and'provides additional information to address the < corrective' actions'tiaken"vith' regard to , p' ' i, 4 .s the thtee causal . factors ' identified in'the'RNP Fire I Inves[til,gation' Report. The < f M .,
$. revised portions 'are identified,by's vertidaFline"in'thefright hand margin of J/
'the report.
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Severity Level IV Violation f RII-91-05101Y1', CI @p- N " d -
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10 CFR 50 Appendix'.B. Criteria [V?requiresjactivities ,affecting quality be prescribed by ' documented instructions '{ procedures,I or"diavings 'of a, type appropriate'tothecircumstancesT' Establishing'a'meth$tomaintainthe'" reactorvesselheadflangetemperature'is'an,activityjAffectingquality. ., - a
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- m res .n aq: gqta.cga, Contrary to the above, ~ documented, instructions, prourdttres, or drawings were not provided, in that, dscumented instructions'verehn'ot"provided for'the method to establish tempmary heating equipment to adi'ntain the reactor vessel '
head flange temperature. i' l d in 'an#electr12al fire 'inside > containment on February 10,Th ,' '1991." s resu
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- 1. The Reason for the Violation, , ,, e.g .
CP&L acknowledges that. the. violatIonIoccurr d $s" described. The requirement to maintain the reactor. vessel; head
- flange within five i degrees of the vessel flange, studs,was< identified during a previous I reactor heac' stud. tensioning evolutionlinl January..' 1991. . Although Plant proceduresradbeenrevisedtoreflectithis)re'quirement, no formal'
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I defined process had been identified'as# to how this task could bethe ~ best i accomplished. ;In order.to meety thelt decision as to what process would b'elemperature;requ rement,used"to through discussions with the, individuals, involved with the process on an informal basis, Other options.vore discussed [ bht were eliminated due to fire protection concerns.: As the need for,;a defined process was not - recognized, no formal review was performed,togevaluate the. conditions that would be created using temporary. heating , equipment. l
- 2. The Corrective Steos That Have Been Taken m , .a and the Results Achieved
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At the time of the fire,, an investigation team was established in accordancewiththePlants'. Corrective. Action; Program.to.conductaroot cause assessment. Several short term corrective'. actions were taken to t facilitate the investigation process,.phichl included limiting access to , , the containment building, and. preserving evidence via video tape for l root cause assessment. Also, other, temporary; power configurations were inspected at that time.to. determine if additional fire hazards existed, g andsomechangesweremadeasaresultof.;thisinspection, m a r ., g n . - , y e, , and a final The investigation team completed'the root'cause' assessment, Fire Investigation Report was issued., Thist report identified the following three primary causal i factors;that contributed.to the fire: r.s o , g ~, y.f a , 1) Lack of a formal, process,for;accomp ishing the. reactor head heating; o > J..-- . 2) Overloaded temporary _ power; hookups . supplying light bulbs used for heating; + ' g,#, g y . ,; =
- 3) Quantities of combustible taterials had been allowed to accumulate in thenhead(st,orage;.ayea.
Vith regard to the first causalg factor,. management expectations have been re-emphasized by the Plant General'Hanager to the Unit Management level on how procedures are to be utilized in the operation and These3 expectations include utilization of maintenance of Unit No. 2. the Special Procedure process for.. situations not. currently covered by e existing procedures,=and dictate;that 3procedure usage is neither ' 3 i optional nor a matter of convenience.: e .i 4 rrL.,
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i. 1.etter to United Statis. Nuclear Regulatory Commission' ' ' Serial: RNPD/91-1523 ' ' Page 3 Concerns with temporary power hookups. wore initially addressed to Fire Protectionpersonnelbyinformallinstructionsforirspectionof i ' temporary electrical devices,(suchtasiextension cords, six outlet This receptacles, drop lights 4 etc.):durin5snormal J shift rounds. i process has since been formalized <as;a apacial order to operations l personnel through the "Managar M operationsiDirective and Information Book" process. This^ process)will'continueLuntil procedural Q: , methods for l controlling such;eonfigurations?are4in(place ~f , T j t , wa$ Og7 ! The impact of utilization of combustibleimaterials.as 5 ya causal factor
' has been communicatedito'sitefpersonnelivia a'. variety of Plent i i
information systems. Noteworthy:amongsthese'icommunication= methods was a
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l detailed review of the event and~its causestbylaisite Fire Protect. ion
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&! specialistwitheachSiteSafety; Council $This!Processeffec '
control of
- combustible" materials,'Withithe'sajoritylof % Plant personnel.
.n, ; g:y ,4 In addition to tthe corrective < actions Etaken' to address each of the causal factors listed above, further: management; emphasis has been placed on ensuring appropriate proceduralfcontrols'are in place for quality This has been' accomplished. ..in part, . through the related activities.- OEF)feventireport publication process.
Operational Experience Feedbackj(hetthree# causal. factors and why they'
- An OEF event report, explainingit were a problem, has been issued.9 0EFireports:of this nature are widely^
distributed in order to communicatolimportant.information directly to all work levels at the Plant. , 4 G'M-zw l ?' ' 6
- 3. The corrective Steos That . Will:Be pA s Taken to Avoid'surther Violations TheFireInvestigat1onReportLeontainedseveralcorrective' action These, recommendations recommendations' applicable to:thistviolation.-
include development of methodology for controls of temporary po installations. determine the proper methods andJequipmentinecessary to maintain the five degree delta t:emperature"requirementsifor reactor vessel head stud tensioning. This processz will,be'. incorporated'into Plant procedures. ,
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- 4. The Date When Full Comuliance Vfil Be Achieved; q
Methods for the control of. temporary; power configurations will be in '
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place by March 31, 1992. J-
.. . . . 7 Appropriate methodology for maintaining < reactor vessel head stud j tensioning temperature requirements will'be incorporated into Plant procedures prior to reactor < -
vessel; -C head ~ reassembly activities during s refueling outage 14 -
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' Commission Letter to United States Nuclear Serial: RNPD/91-1.523
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ng - s Should you nave any questions regarding,,this matter,'please contact ~ Mr. J. D. Kloosterman at (803) .38321491. 2 f
,.Very truly yours, 3; / L
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..C.ar h l es R. Di etz Manago r 4 ,
Robinson Nuclear Project Department t M. Q* :., pp {, . ,
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ROBINSON NUCLEAR PROJECT DEPARTMENT POST OFFICE BOX 790 HARTSVILLE, SOUTH: CAROLINA 29550 o' E AY 1 8 1991 i 3 3 oc ..t .red Robinson File No.: 135,1,0 E ' , amT.,Yf^ aio Serial: RNPD/91-1116 , i
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< United States Nuclear Regulatory 'CommissiorP'#" '
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N, H. B. ROBINSON STEAM ELECTRIC PIANT '
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., ,,I NRC INSPECTION REPORT No. 50-261/91'-05',REPLiT0"A
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- i' Carolina Power and Light Company hereby provides this' reply to the Notice of 4, Violation identified ~in Inspection (m. v. :-, ,, u Report"50-261/w.1!05."
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. . u. . #,. h 10 'CFR 50 Appendix B,' Criteria'V',I raquires*hetih1Ne'aIYffeciting'qualitybe ' ')
7 i prescribed by documented' instructions.fprocedures, Tor drawings of a type appropriate to the circumstances. Establishing a method to maintain the ~ l reactor vesse1 head flange temperaturaq 7,uss,an i W M. activity c A 9.s affecting v W . quality.
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Contrary to the above, documented instructions, procedures, or, drawings were not provided, in that,7 documented' instructions were'not'provided for the [ method to establish temporary heatirg^ equipment'to" maintain the reactor vessel > head flange temperature.'" This' resulted' " *"#""* in'an elechrical'
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fire (inside containment on February'.14, ' 19 .p.,91.'. '% er c qu i p wt a n eu y > < ' '
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Serial: 'RNPD/91-1116
- l Page 2 REPLY
-1. The Reason for the Violation i
ym e, mg , i CP&L acknowledges that.the violation-occurred,ascdescribed. The requirement to maintain the reactorsvessel head t flange.within five degrees of the vessel. flange studs;was identified,during a previous reactor head stud tensioning-evolution in Janusry, 1991.Although Plant procedures had been revised to reflect lthis' requirement, no formal defined process had been identified 3assto how.y this= task could be best accomplished. InorderrtolmeetitheSpenparature.. requirement, the decision as to what process'would besusadito4heaththe<t head;was developed through discussions.with thel individuals? involved with the process on an informal basis. As the need~for a' defined' process was not recognized, no-formal review.was performedito<evaluatatthe' conditions;that would be created using temporary)heatingiequipment,; ~ s t
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- 2. 1he Corrective Stens That Have Been Taken'and the Results Achieved
. u yg ,w At the time of the fire, an'investigationiteam.was established in I
accordance with the Plante' CorrectivefAction> Program to conduct a root
' cause assessment. Several short term
- corrective' actions were taken to facilitatetheinvestigation'processTwhichtincibded-limitingaccessto the containment building, and preserving!avidene,e3via,videoitape for
, root cause assessment 4 Also,other; temporary!powerconfigurationswere inspected at that time to determina tif; additions.li fire hazards-existed.,
and some changes were made as a result.ofithisl inspection. '
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The investigation team completed'theTroot cause assessment, and a final 6 Fire Investigation Report was issued.b This report identifies that inadequate controls over the head heating ~ process' contributed to the-occurrence of the fire. Additional management 2 emphasis.has since been placed on ensuring appropriate procedural controls are placed on quality
. related activities; y se
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- 3. The Corrective Steos That Will Be Taken to Avoid Furth?r Violations
.v The Fire Investigation Report contained several' corrective action recommendations applicable to this" violation,':These. recommendations include development of methodology for controlstof temporary power installations. In addition, a technical analysis isLto be performed to determine the proper methods and equipment'necessary to maintain the five degree delta temperature requirements'fortreactor vessel head stud tensioning. This process will be' incorporated-into Plant procedures.
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- 4. The Date When Full Come11ance Will Be Achieved vi;6um As an interim measure, compensatory-actions which have been taken are inclusien of inspection of-temporary l electrical. devices in shift rounds until formal methods to control;such! configurations are developed and implemented. Formal methods for;the'controliof' temporary power configurations will be in place by March'31 M1992.f
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Appropriate methodology for maintaining" reactor vessel head stud tensioning tamperature requirements;will-be incorporated into Plant s ~ procedures prior to; reactor vessel head reassembly activities during ' refueling outage;14. < Should you have any questions regarding thin matter,'please contact ' Mr. J. D. Kloosterman at,(803) 383-1491. .
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d(7/112$ f M k..k. [ Charles R.,Dietz 4 - Robinson.. d Manager Nuclear Project Department
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