IR 05000810/2010010
| ML17228B350 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, 05000810  |
| Issue date: | 11/28/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17228B349 | List: |
| References | |
| 50-335-95-20, 50-389-95-20, EA-95-222, NUDOCS 9512110371 | |
| Download: ML17228B350 (49) | |
Text
Docket Nos.
50-335 and-389 License Nos.
DPR-67 and NPF-16 EA 95-222 NOTICE OF VIOLATION Florida Power and Light Company
't.
Lucie Units
and
During an NRC inspection conducted on August 10 through October 10, 1995, a
violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
CFR 50, Appendix B, Criterion XVI, "Corrective Actions," requires, in part, that measures be established to assure that conditions adverse to quality are promptly identified and corrected.
Contrary to the above, conditions adverse to quality, involving relief valve setpoint and blowdown values, identified on February 20, March 2, and March 10, 1995, did not receive prompt corrective actions and led to a repeat of previously identified problems on August 10, 1995, when Unit 1 relief valve V-3439 lifted and failed to reseat without operator intervention.
The subject event resulted in approximately 4000 gallons of reactor coolant accumulating in the Unit 1 pipe tunnel.
Evaluations performed after this event revealed the need to replace, or establish new setpoints for, several relief valves in safety systems in both units.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
-If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Under the authority of Section 182 of the Act, 42 U.S.C.
2232, this response shall be submitted under oath or affirmation.
Enclosure
9512110371 951128 PDR ADQCK 05000335
Notice of Violation Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without reduction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Atlanta, Georgia this 28th day of November 1995 Enclosure
LIST OF ATTENDEES Florida Power and Li ht Com an W. Bohlke, Vice President, Nuclear Engineering and License D. Denver, Engineer Manager, St.
Lucie J.
Goldberg, President, Nuclear Division D. Sager, Vice President, St. Lucie Plant C.
Wood, Operations Supervisor, St.
Lucie Nuclear Re ulator Commission J. Beall, Senior Enforcement Specialist, Office of Enforcement S. Ebneter, Regional Administrator, Region II (RII)
C.
Evans, Regional Counsel, RII J.
Hannan, Acting Deputy Director, Division of Reactor Projects (DRP), RII K. Landis, Acting Chief, Reactor Projects Branch 3, DRP, RII E.
Lea, Project Engineer, Reactor Projects Branch 3, DRP, RII E. Herschoff, Director, DRP, RII R. Prevatte, Senior Resident Inspector, St. Lucie B. Uryc, Enforcement and Investigation Officer; RII D. Verrelli, Technical Assistant, Division of Reactor Safety, RII L. Watson, Enforcement Specialist, Region II Russion GAN Visitors L. Slepnev, Deputy Head of Department for License Processing and Regional Operations Coordination V. Outkine, Deputy Head of Volga Regional Office V. Shvedkov, Deputy Head of North European Office 0. Larina, Interpreter Enclosure
NRC CLOSED PREDECISIONAL ENFORCEMENT CONFERENCE ST. LUCIE NUCLEAR PLANT NOVEMBER 14, 1995 Enclosure
PREDECISIONAL ENFORCEMENT CONFERENCE AGENDA ST. LUCIE NOVEMBER 14, 1995, AT 1:00 P.M.
NRC REGION II OFFICE, ATLANTA,GEORGIA OPENING REMARKS AND INTRODUCTIONS S. Ebneter, Regional Administrator NRC ENFORCEMENT POLICY B. Uryc, Director Enforcement and Investigation Coordination Staff SUMMARY OF THE ISSUES S. Ebneter, Regional Administrator STATEMENT OF CONCERNS / APPARENT VIOLATIONS E. Merschoff, Director Division of Reactor Projects LICENSEE PRESENTATION W. Goldberg, President, Nuclear Division Florida Power and Light BREAK / NRC CAUCUS NRC FOLLOWUP QUESTIONS CLOSING REMARKS S. Ebneter, Regional Administrator
ISSUE TO BE DISCUSSED 10 CFR 50, Appendix B, Criterion XVl, "Corrective Actions,"
requires, in part, that measures be established to assure that conditions adverse to quality are promptly identified and corrected.
The failure to take prompt corrective action for the conditions adverse to quality identified on February 20, March 2, and March 10, 1995, led to a repeat of the anomalous behavior on August 10, 1995, when Unit 1 relief valve V-3439 lifted and failed to reseat without operator intervention.
The subject event resulted in approximately 4000 gallons of reactor coolant accumulating in the Unit 1 pipe tunnel.
NOTE The apparent violations discussed in this predecisional enforcement conference are subject to further review and are subject to change prior to any resulting enforcement decisio NRC PRE-DECISIONAL ENFORCEMENT CONFERENCE NOVEINBER 14, 1995
~nclosure
AGENDA
~Pa e
I.
INTRODUCTION D. SAGER II.
REVIEW OF EVENTS IDEN'IlX'IEDIN INSPECTION REPORT 95-20 A.
EVENTS, CAUSES AND ACTIONS D. DENVER B.
DESIGN ASSESSMENT AND SAFETY SIGNIFICANCE W. BOHLKE
III. QUESTIONS AND ANSWERS IV.
CLOSING REMARKS J. GOLDBERG pled
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.. I ANALsYXED.RESEAT, hGLRGINS
.,
- -DEXERIMINEDTHE.SLOWDOWN VALUE.BY 5GJETIPI'YING'.THE SPECIFIED'I BLOWDOYVN=
'.; PERCENTAGE. BY"THE.'NOMlNAL'1FI.':::PRESSURE:
-,':-- NIIETEIIINIIGSI',INE--:MINIMtMSRRSE!T: PRESSURE::.:
';-'-'".=-;;XY'..'SUBXRACTING.".TKKE;>KOWDO%5:VALUE":~0M..
. ':TGE INtltttMIMTPL.RDIStlRE:::,
- '.'.-:--'C>A'L'CUEA'KKDRESEAT';MARGINFROMNOLUHDMG::
- OESRATISIC:.PRESSURE MIDMUUMUURRSKLt!!i'i!,,
P ",
A4,
,
V L
~
D '
, +
A I ', I ZI.
A '"Q T,
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,
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y
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Pt
-18-
OVERALLRELIEF VALVEDESIGN ASSESSMENT'continued)
ASSESSMENT OF 114 SAFETY.:.RELATED RELIEF VALVESDO VALVES'AVE ADEQUATE.DESIGN MARGIN?
YES NO.;-
FURT.HER.
ASSESSMENT REQUIRED FOR 100 VALVES, h
NO hl a-Cr.
PRE5Ã50CSOfSRP)
-'
hMODIFY,';14VALVES
=
FOR. DESIGN 'MARGIN
- lMPROVhEMENTS E
r
- .
h r
h ERR 95-"006 '=.-
'S',
'
h, '*r
.hr
.;.'~r';; DISCUSSIONS %VITE.CROSBY'VAX'VE',,COMPA2K:,-;-,-.";;.';;.:.,:,"; ';:,;
-19-
~
RELIEF.. VALVEFUNCTIONS AND FAILURE CONSEQUENCES
~"
OVERALL;SAFETY ASSESSMENT OE RELIEF;VA'LVES-
~'ETAILED.SAFETY. ASSESSMENT.,OF. LIFTINGV3439
~
CONCLUSXONS
- I-20-
s~zrv sromnCmCz.
(contiaued)
r" RELIEF VA'LVE'-FUNCTIONSAND"FAILURECONSE 'ENCES:
'.
~
FUNCTIONS N
V
- PRO,-TECTS: ST STEM PROM OVER I'RESSPIRE'STION BY-.OPENING Wl'EHXNSPECEPIIH) PRAENGE. OF DESIGN.LIFT.SETPOINTS, AND hBQNTA'INS SYSTEM PRESSURE: BOUNDARY,.BY::"
CLOSING WHZGbt-=SPECI%X%3)'RANGE,OF DESIGN'ESEAT SETPOINTS LOSS;OF,.FUNCTION CONSEQUENCES
'I I
!'".
- '..'INM<22ITORYLOSS':TEAT,'ZOTEÃXKAIJ-Y-"COULD'".t
,ADVERSELY:A%ZZCT>>THE'FUNGTXONOF-:THE
'. '-.ESYPSTEM OR'OTHER'.SA'EEPTY. RELYXKD...SYSTEMS
'-:
'i:,: '-'-:;-'::::;i;INVSNTORTE!tlOSSTINT'.I!0~X!COIPTSI,'
':,:::::::,i.;::,'"-'.::,.:i,'SO!EOET 1NTEEERt1ESISOTSM'IITOECISVTETTO'::
'I
'I I
J S",'; ',( 'I-21-
e'
SAX'KTY;SIGNIFICANCE
- (con6nued)
d d
'ASSESSMENT OF 114
~
SAFETY RELATED'
RELIEFVALVES
, DO VALVESHAVE ADEQUATEDESIGN MARGIN?
NO NO RJRTHER ASSESSMENT REQUIRED FOR'I00
.
VALVES DO VALVESHAVE..
ADEQUATEACTUAL MARGIN'
- YES REQUIRED
, 'FOR11 VALVES NO.
I DOES'
LOSS OF INVENTORY.
.(',ADVERSELYAFFECT z.'
'YSTEMS'OR.RELEAS(E RADIOACTIVITYV"-
YES'..-
, RJRTHER"
- NO('.,'ASSESSMENT
"i'REQUIRED
',", 'FOR'2 VALVES
'JRTHER ASSESSMENT-'EQUIRED FOR
(
P%ESQS04RHF440J (
I h
d
- 22-
~
~ 1 ggi8,,;(j'~,":,i.;";:.'.'!"'-"'=':,.-'-,"--'.,"jj::.,::-'.'.;-.',.".'.i.:*:SAFETY.:;SIGbjIFICA'NCE.'
I i~)'i(~ eggy'c~Qpvj!4@AcVQP~~~ggg'
'W~~~j+5'~> <<'i>.~~ "~A)'M~~D"@Y'~('
3 ':IJNITj -~%='-':=:=.-j =VALVPi.':.:
- "'~
.
", -'="~A'DVERSELY~A'FFECTING'::'
S
"]~++I,.g ":~~!LETDOPgg'lLINE".='I;""'""-""'--:.-,"":-:jw'-~",'DIS( HARGES.".<<TO. TANK-. '
I
" 8~+~~-'"'~ <<>~+>"-<<~~~:!4=-!';-.".+:.";"-'.":"-.-',"'-;=.::-'".*'-<<:-'".~+!EASllY='-:DETECTABI'E='---';..---;
"9
'
."
-" ':": "':-, l""
'"4j-'..";~T', I-.""=:"~4~8-':HPSBBISCiHA'RGE:;"-::"':: "-='-i=-"='DISCHARGES'-TO.-TANK-S P
I P
II
"~ gg~'-'+~~/ HPS(.'-.ISCHjLRGE '! ':.-'; "--"j':~DISCHARGES.TO,TANK,
'+g~w>:,:. IWh,-t,'!:,':,-'..~*4,,'.""";.":ii-'i:.'.'.-..!--'.l',"..-::::::--,'-;;=:!;":!ALT.:";.CHARGING.LIMITED:.,
t
".-" 'POTENTIAL'L',FOR";RELIEASE':"
-,- ---,, OF:,:RA'DIOA'CTIVITiYP..,",'=:. ".,
":-."-..".
NO",.'. ',:-
- -!;:;-'.DISCHA'RGES:.'fO. TANK'."-;
::
'-' ~
DISCHA'RGES-TO,.TA'gK "':
NO"
,""':j. DISCHPARGES'TO-TANK.'....
I I
P
- +P',
. ~ '"=,.- "-.72324,"g?23/8;",&,72326,,;:;,=::
NO+=.=..',=-,.='-'"-..;,.;::',;.":, "-.'.:.",.".-'=;-'=';
NO!'"-" '.-
.;:: -',",
(
'","'.. j,-'i, %'PIGRGINGjPPgPI'SCH'AIRGE'-'-:
-"-*-""!!DISCHARGESlTOISUCTION ""
";:.". DISClgRGES:*'TO SUCTION P: i-,@+~~I""."~"'.~=':-"-:.",iBIK'I :"'::iNO'L'OSS:.OFllNVENTORY::::.,:.::..iNQ,LOSSI OF'INVENTORY:.',"4~~
"45 4~
3~el%1',
.
Oi,". ":...,'...,.,
",:,, *
.
"., NO
'
":" ', -',", -..,;.";",-,;-",;- '"".'=,.'-z,
",'"'=;
=-.;<<@DISCHA'RGES:.TO.SUlgP-.':,-..;; " "",+';'I?ISCHARGES:TO.SUMP>i"";
- "P--~~<~;-kf4CKRUP,;WITH:CHA'RGING::..;i.<<,,";;". "'-'"";V.'--""";,'.:;;>>,';.':.",!';.":>'..;"-.=-"~,.;;ib t
t~
- %4 gI.'0)
V88if
SM'ETY SIGNIFICANCE (continued)
E
.DETAILEDSA:FETY ASSESSMENT OF LIFFINGV3439
~
.METHODOLOGY
'h REVIEWED UFSAR CHAPTER 15 ACCIDENTS'WITH SUSTAINED RCS PRESSURE )250 PSIG'%HEN
'WITCIGNG TO SHt:JTDOWN COOLING APPLIED PLANT,OPERATING HISTORY.AND USED'
"REASONABLEAND'CREDIBLE".
ASSUMPTIONS'.
CONSISTENT WITHLER.RULE AND NUREG-1022; STFAM GENERATOR TUBERIFIIJRE I~ANTS:,.
Y
= EXCEKLENTSTEAM-'.652K',RATORINTEGRITY'
t: " EVENT,'-DOES NOT'CAUSE'ZUI<Xi;;FAILURES.',"
,:,.'.;-;."; ',:,"<<KXC*ESS"STEAMDEMA'ND;EVENTS:.
'.
' '~'.;
. NO OPERATING'-'-HISTORY.WjlTEK',COÃEROL
'ODS
'FAILING.;TO3NSERT,ON EFFECTOR'MHP,';"
'
"'.'EROM POWER,
.'-':;:,;.:-:-":--:..=-
S - <<-"~~'.-="NO FUELFBI'URES>>..: '--'" "v~-- "
"-.';;.-"-..=;:,',',-.'i;e-.,NO".RETURN-TOP'OW1<&),',":.",,';;..;"..'."-'.-';.,;."="~: ";:;-;-'"
t
" ': -.',,;-'-'.."".,;,:-" ",'t-',-,-',.:,
.",~~"'.:
'.
"":, ', .g~','
-,::; '::,"~- ~r'+~'"'-
- 24-
!
SUETY SIGNIFICANCE-(continued)
!
- DETAILED'SAFETY ASSESSMENT, OF.LIFTING'V3439 METHODOLOGY (continued)
E SMALLBREAK.LOSS OF COOLANT A:CCIDENTS',
-MOST:SBLOCAs DO NOT RESULT'N FUEL,'AILURE I
CONSERVATIVPLY ASSUMER) 1% FAIL'ED FUEL (GAS GAP! RELEASE)
-~.
=.RESULTS PP '
P)
t-
'O INCR'.SES IN'UF!SAR%)OSES'"WITH:,
REA,SONABLEAI6) CREDIBLE.ASSUMPTIONS, I
iI, I,
-25-
':: '"-'":,'BESIGN='.A'NDSAPETY DESIGN ASSESSMENT:-;.." ';
',-'
" -.':.;SUINhfARYAM);-CONCLUSlONl".;.;:,;:,","",';;"':::.","';.'"'".'-,;.'.
'>>t'ai
.'.OVERALL"DESIGNASSESSMENT-IDENTIFIED;;
!.',"'j";;,j.100;:VALVES;"%iIXH:ADEQUATEDESIGNRNA'RGIN.;"AND.<.".',,",".",l
. ';,
" ~THUS;>0;"FURTHER"ACTIONS"WERE!REQUIRED~'!FOR"::"
C
.,--"
. OVERA'LL-DESIGNASSESSMENZ..REVjEWED! IN:.MORE".-
DETA'XL"-::14'VALVESWlTH:LIMIITED.-OR;-NEGATIVE
- ,.
- ';'
- DESIG¹MA'EGIN'
$.
'THESE: !VA'LVES;:!H'A.VEiEITHER,"BEEN'!MODIFIED;OR,'.:.'
-,', ';A'E".PLA'%WED.'FOR:MODIFXCA'TION-",TO;,<XMPROVE,';,:,;:,';,.";i',",,
~
'
.. '- ~
, ',.~;g.';"';;,',.;...'.",,",',",;;,,(",,, ",":":". (,
<<
'
.,"'.",.-,,,','"'--. ",'~ i.:;;.:"( ',; ',", >~.'.,'.. c,:."
5:::K'j'o;~'"k~
tp~~':~'"'- g ~'~:"i" 'v.,"s
"'a..~'"'s,
~<:(6,~,,';t'w+~-.">~~le</~g.+wig'w~.,"~ ~ps~
g.,"'yq')k~$(y j~g', v~'4,f!~j~p
, g/~pg~g.<,<~o
!2!'; ". kj~ce'
.sg, L~~e~p~~8ck)( j<<k"1"cP(,~(c~Q Qc.3),~Q
~
~ ~~y p 'I
~
~
+pa'~
<W$x~ w4)'",+> '"'
,P6 ).
4,jf,
~jjg><~,Cgp~~
-26-
i i
I DESIGN AND-SAX'KTYDESIGN ASSESSMENT SUMMARYAND CONCLUSION" (continued)
SAFETYASSESSMENT DEMONSTRATED TERAT.
'.I3 VALVESI<XFHERHAVE.'SU*XTICIENT.1)ESIGNOR ACTUAL.LIFT.MARGIN,OR DO NOT.HAVE'TIHE P0 1SSOSSL POSE VEIIS EST APSE OE, SSPE1T SPSPESIS--
OR CAUSE THE: RELEASE OF RADIOACXIYITY,
~
-DETAILED-SAFETYASSESSMENT-CONCLUDED'THAT
'XXFTING,V3439 IN CONJUNCTION WECH.AFFECTED CHAPTER 15-UFSAR ACCIDENTS RESULTSIN NO:
'INCREASE.':IN UFSAR OFFSITE DOSES
~
THE.PAST.:AND CURRENT'-STAYUS OF THE RELIEF'ALVES.
ASSESSED IS NOT;SIGNIFIICANT:
WITE';RESPECT TO THE HEALTHAND SAFETY. OE,, THE;-
gUBLIICP PS P
t I
S
'I II'I 1'.
I c' -,
~
~
- ,, ~
-27-
I
~
SYSTFMAND COMPONENT ZNGINE%34ING
'
'TAR-PROCESS IMPROVE1NFATS,
~
OPERATOR. WORKAROUNDS I
I gj I
I I
II I
I k
,k I
(j' ',,I kk I $
,QN FFF5 I,
Fk <<
.
FF ~
'F
fFFF Cj l F)AFWFF F F+CIFF+Fjlkk KFFQ I,.
PIP $g'lk; 'I A 0 I F k '*+g M~'f 'FI~+gFFF'I'FF '
F-28-
- PRRSENTATlON SEMINARY',
. '
!",
'\\
4, '
A'TECIXNICAI'.
AND.'lCKX~NTENANCE",SXAPES'WORIHNG ONISSUES RELATED TO 'SYSTEM.OP392ATION ',=':
F= '4 E
~
'EOCUS 'ON SYSTEM.'AND'COMPONENT,.CONDITIONS
-':PVAS:-VAI:3D'-BOTH:THEN;AND,NOW..
E
'0N 8/10/95, V3439 TRIGGERED RECOGNITION:OF.'RELIEF'VA'LVES AS A:.~W'ISSUE s
..o'.....'-.'-BY 8/30/95, ENGINEERING 'XBLB COMPL'ETED
'- 'ASSESSMENTS".AND'IDENTl6XED'REQU>IRED"CHANGES
'
"j~l 8
,.i',"'<<'= q ~(j). ~~/ Vgg". lf,'W": ~"~@Qpi+~iPi'~" j("'"~+jgS8g, l'~'i)'")g"j'g4:~':~ ~gap~(gC,($ ~~~m."'"$ ~-: 'A~$g~Q.g ~g~'j""
-29-
I PRESENTATION SUVBCARY.-
(continued)
XXPECTIVK;CORRECTIVE. ACTIONINCL'UIF)ED, SO~
CRES B1'
RIVEVIS IIE I'
/
I t
SAFETY ASSESSMENT SHOWS NO INCREASE'D TH&MT TO PUBLIC HEALTHAND SAFETY
~
ENGINEERING HAS SOLVED RELIEF VALVE,PROBLEM ST.'-LUCIEHAS ELIhgNATEDOPERATOR.,;
WO@GLROUM)S-AFSSOCIATED=:WITHREXD~:F, VALVES
- 't
'k, I*
"I I
S
"I
/
I Fl'
2-.I'30-