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| issue date = 07/24/1978
| issue date = 07/24/1978
| title = LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent
| title = LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent
| author name = Schmidt A D
| author name = Schmidt A
| author affiliation = Florida Power & Light Co
| author affiliation = Florida Power & Light Co
| addressee name = O'Reilly J P
| addressee name = O'Reilly J
| addressee affiliation = NRC/RGN-II, NRC/IE
| addressee affiliation = NRC/RGN-II, NRC/IE
| docket = 05000335
| docket = 05000335
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIBS)DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: OREILLY J P NRC ORG: SCHMIDT A D FL PWR 5 LIGHT DOCDATE: 07/24f78 DATE RCVD: 08/01/78 DOCTYPE: LETTER NOTARIZED:
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIBS)
NO COPIES RECEIVED  
DISTRIBUTION FOR INCOMING MATERIAL                                 50-335 REC: OREILLY       J P                     ORG:   SCHMIDT A D                 DOCDATE: 07/24f78 NRC                                        FL PWR  5 LIGHT                DATE RCVD: 08/01/78 DOCTYPE: LETTER           NOTARIZED: NO                                         COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-024)
LTR 1   ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-024) ON 06/25/78 CONCERNING DURING PLAN1 STARTUP FROM A SHORT MAINTENANCE i DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC 3. 4. 8. A LIMIT OF i. 0 UCI/QRAM DOSE EQUIVALENT I-131... W/ATT.
ON 06/25/78 CONCERNING DURING PLAN1 STARTUP FROM A SHORT MAINTENANCE i DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC 3.4.8.A LIMIT OF i.0 UCI/QRAM DOSE EQUIVALENT I-131...W/ATT.PLANT NAME: ST LUCIE Si REVIEWER INITIAL: X/M DISTRIBUTOR INITIAL: QQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++4<<+4<+<<<+4<<+
PLANT NAME: ST LUCIE         Si                                       REVIEWER INITIAL: X/M DISTRIBUTOR   INITIAL:QQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++4<<+4<+<<<+4<<+
INCIDENT REPORTS (DISTRIBUTION CODE A002)FOR ACTION: INTERNAL: EXTERNAL: BR CHIEF ORB84 BC++W/4 ENCL F L~ENCL u+~W/2 ENCL I 8.C SYSTEMS BR++W/ENCL NOVAK/CHECK++Wf ENCL AD FOR ENG~4W/ENCL HANAUER~~W/ENCL AD FOR SYS 8c PROJ++W/ENCL ENGINEERING BR+4W/ENCL KREGER/J.COLLINS++W/ENCL K SEYFRIT/IE++W/ENCL LPDR S FT PIERCEi FL++W/ENCL TICi LIZ CARTER~~%W/
INCIDENT REPORTS (DISTRIBUTION CODE A002)
ENCL NS I C+~W/ENCL ACRS CAT B~~W/16 ENCL NRC PDR44~W/ENCL MIPC+~W/3 ENCL EMERGENCY PLAN BR>~W/ENCL EEB4+W/ENCL PLANT SYSTEMS BR+4W/ENCL AD FOR Pl ANT SYSTEMS+<W/ENCL REACTOR SAFETY BR>~W/ENCL VOLLMER/BUNCH%4W/ENCL POWER SYS BR++W/ENCL DISTRIBUTION:
FOR ACTION:           BR CHIEF ORB84 BC++W/4 ENCL INTERNAL:                    F L ~       ENCL                NRC PDR44~W/ENCL u   +~W/2 ENCL                      MIPC+~W/3 ENCL I 8. C SYSTEMS BR++W/ENCL            EMERGENCY PLAN BR>~W/ENCL NOVAK/CHECK++WfENCL                      EEB4+W/ENCL AD FOR ENG~4W/ENCL                      PLANT SYSTEMS BR+4W/ENCL HANAUER~~W/ENCL                        AD FOR Pl ANT SYSTEMS+<W/ENCL AD FOR SYS 8c PROJ++W/ENCL              REACTOR SAFETY BR>~W/ENCL ENGINEERING BR+4W/ENCL                  VOLLMER/BUNCH%4W/ENCL KREGER/J. COLLINS++W/ENCL              POWER SYS BR++W/ENCL K SEYFRIT/ IE++W/ENCL EXTERNAL:            LPDR S FT PIERCEi FL++W/ENCL TICi LIZ     CARTER~~%W/ ENCL NS I C+~W/ENCL ACRS     CAT B~~W/16 ENCL DISTRIBUTION:         LTR 45         ENCL 45                           CONTROL NBR:  782140106 SI ZE: iP+ 1 P+3P
LTR 45 ENCL 45 SI ZE: iP+1 P+3P%%%%0f 0f%%%Sf%%%%%%%4 0f%%%%4 4%8/%Sf SHt%%%%CONTROL NBR: 782140106 THE,END%%%%%%%%%%%%
%%%%0f 0f %%%Sf %%%%%%%4 0f%%%%4 4 %8/ %Sf SHt %%%%   THE,END %%%%%%%%%%%% H w4%%%%%%%%%%%%%%M 0%4.
H w4%%%%%%%%%%%%%%M 0%4.
p q r W 4 4 N$I P/1 k t 4~i 1 4 k~AI t 8, u , I'-E4 FLORIDA POWER:Iry Q q'J LfY 5 LIGHT COMPANY July 24, 1978 P RN-L I-78-198 Mr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Corrmission 230 Peachtree Street, N.N., Suite 1217 Atlanta, Georgia 30303 I


==Dear Mr.O'Reilly:==
p q r W
REPORTABLE OCCURRENCE 335-78-24 ST.LUG IE UNIT 1 DATE OF OCCURRENCE:
t 4 4 4 N$ I P
JUNE 25, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE E UIVALENT I-131 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
                / 1 k
Very truly yours, 2 A..c mi t Vice President Power Resources MAS/cpc Attachment cc: Harold F.Reis, Esquire Doctor, Office of Inspection and Enforcement (30)director, Office of Management Information and Program Control (3)782l40106 PEOPLE...SERVING PEOPLE S NRC FORM Saa I7.771 LICEIXScc EVCI'4T REPORT U.S.NUCI.EAR REGULATORY C SIMISSICiN CONTROL, BLOC:<: I I I I I.Ql IPLSASE PRINT OR TYPP AL RSCUIRcO INFORN'IATIONI I 0's 1 3 i.iCENSca COOE Q.LIE I LI 111 0 01-101 0101 010 I-I I Q~ll ll 11 11 Q~IIQ LICmslsa NIUAISER'S 26 L;Cc<SE TV?E 40!1~1!a CON'T~o 1!Q 1 i~a I I In I I QE IS Rc?QAT 0*, 3!0":.'*i ML'Q'''!0 6)CCCKET NVAISEs!~63 sa EVENT QATE EVENT OESCRIPTION
                            ~ i 1
'NO PROGABLZE COVSECUENCES QIO-Durin lant startuo from a sh r 16-hour m i tenance shutdown Dose~03 E uivalent DE Iodine exceeded the Technical S ecification
4     k
.3.4.8.a limit of 1..0 Ci ram DOSE E UIVALENT I-131.The DE Iodine was first measured~os above this limit at 1900 on'6 25 78 while the lant was at 97/ower.The!0 1 ifi atio~o~.4.8.a.A revious occurrence of this t e is described in LER 335-78-13!
                                  ~ AI t
~oa 1 3 9!0 SYSTcal CAUSc CAUSE C>l.vALv E C OE COCE SVSCCQE C NPONENT OOE svaccca svacoQE QC LZZZS WNS WZG~00 0 Zl NS mic ZZNS 1 6 9 Is)Il 12 la IS I9 SECVENTIAI CCCVAAEiICE REPORT REVISIQNN LSR/Ao VE'IT YEAR R EPOA T 40.CQQE tvPE"IO, Qr ENIEN r.~yg~~02 4~m~03~L 2 I 22 22 24 26 21 29 20 32 ACTION CUTVAE E?RECT SIIUTOQWN AT,ACHMENT 4PROR PRIMPC MP.COAIPON cN 4 TAKE44 ACTION'I CN Pr&NVT,MET)soo HOURS~22 SVSMI 4~ao PCRM)Ua.SVPPl,lcR UANVPACTVRPR MlsL2Js Lz'Q LcQL~0~0~YQ~NS MNIQ~c4 i tl w)2 24 S 26 JP 4 I 42 43 44 41 CAUS" OESCRIPTIO I ANO CORREE 0 IVE ACTIONS Q2i o Af P ri f w r i i h nmina v 1'of fuel e 1 ant shutdown nd s s t s sufficient to cause Iodine build u Iodine s ikin nenomenon and exceed the urification ca acit for a short eriod of time..METNCO QP OISCQVPRY+AQO: 4$4$A NA'IAL O P-R R N.A.Scho man~I 9 P ACILI~sr 3~ATVS'S~?QvlcR QTIIERSNATVS Q LJS 0-''0 S~N 1 3 9 tp I 2 la 44 ACTIVITY CONTENT RELEAsco OP RELEASE AMOUNi'QP ACTIVITY QSS CZ L~J Q" L~JQS'A 1 lp It?SRSONNEE XirQSVRES~IVMSER TYPc QESCAIPTIQN QM CZ~~Q2'I Z lO 3 I I 12 Is PERSONNEL Iiv)UR)ca 0 I00 0ci i0 0 iiQN EZ L>~Q42 1 a 1 lp P''6LIC,'.Y CH)LEQAA 1 3 1 lp QISCQV SAY OESCRIPTICN Q4-r tor Observation LOCATION oP RPLEAsc QSS 30 30 NRO''SE C ILY!!I!!I,!I!!I!I ,..(305)552-3802
 
~LXCENSEE EVENT REPORT PAGE T'tiO~.C4.C SUPPLEHENTARY INFORMATION TECHNXCAL SPECXFICATION PURPORT DOSE E UIVALENT IODXNE V Reactor power histor startin 48 hours rior to the first sam le in , which the limit was exceeded.DATE 6/23/78 6/24/78 6/24/78 6/24/78 6/24/78 6/25/78 TLilE 1900 to ,.2000 2100 2200 2300 to 1400,-k AVERAGE REACTOR POHER ,97.1%(steady state)61..0%20.0%r 0-0%(plant outage)6/25/78 6/25/78 6/25/78 6/25/78 6/25/78 1500 1600 1700 1800 1900%%38.5%66.3%90.0%95.0%*97.0%Additional Power History: 20%-80%from June 1 to June 12, 1978 98%-100%from June 13 to June 24, 1978 (DEQ I-131;2.0-4.5 E-I pCi/gram)~~'.'.---="--':First DEQ Iodine Sample'>I.O uCi/gram;:
8, I             :Iry u
"~'E QEPORTABLE OCCURRENCE 335-78-24 LIC~~']SEE EVENT REPORT'AGE THREE SUPPLEMENTARX INFORMATION (Cont)2.Fuel burnu b core re ion.Fuel burnup by octants: Region 1 Region 2 Region'3 , Region 4'egion 5 Region, 6 Region 7 Region 8 10945.0'0893.7 10781.0 10876.5 10783.6 ,, 10798.3 10752.0 10868.8 Average Burnup in t Megawatt Days per Metric Ton Uranium (I'O'D/HTU) a Total Core Average Burnup-10837.4 N\3.Clean-u flog histor~startin
Q
<>S hours rior to the tirst sample in which the limit was exceeded.Prom 1900 on 6/23/78 until 2100 on 6/24/78, purification flow rate was<82 gpm (two charging pumps).At 2300 on 6/24/78, purification flow rate was reduced to 52 gpm.~From 2400 on 6/24/78 until 0300 on 6/25/78,'urification flow rate was~iO'gpm (onc charging pump).At 0400 on 6/25/78, purification flow rate was increased to 58 gpm.'From 0500 on 6/25/78 until 1900 on 6/25/78, purification flow rate vas w86 gpm (two charging pumps).NOTE: Clean-up demineraliration consisted of a mixed bed at a 1:1~ratio, cation to anion, with a bcd volume of 36 cubic feet.~~4.::-:.-His tor of de-assin o eration s tar tin 48 hours rior.to the f irs t sam le in which the limit was exceeded.No degassing operations vere performed within the above 48-hour time span.
                                                                        '- E4        q'J LfY FLORIDA POWER 5 LIGHT COMPANY July 24,    1978 P RN-L  I-78-198 Mr. James P. O'Reilly, Director, Region  II                                            2 Office of Inspection     and Enforcement U. S. Nuclear Regulatory Corrmission 230 Peachtree Street, N. N., Suite 1217
REPORTABLE OCCURRENCE 335-78-24 LICENSEE EVENT REPORT ,'+AGE IOUR SUPPLEHENTARY XNFORi~fATXON (Cont)5.The time duration when the s ecific activit of the rimar coolant exceeded 1.0 uCi/ram DE X-131.6.Iodine 131 Dose Equivalent was greater than 1.0 uCi/gram from 6/25/78 at 1900 until 6/26/78 at 0030.The total time above 1.0 uCi/gram was 5.50 hours.~" Results of S ecific Activit Anal sis (uCi/ram).DATE TINE 6/25/78 0215.6/25/78 1900 6/25/78 2010 6/26/78 0030 6/26/78 0615.I-131 2.249 E-1 1.024 E-0 1.120 E-0 7.736 E-1 4.708 E-1 1-132 9.66 E-2 8.12 E-2 7.38 E-2'.01 E-2 1.93 E-2 I-133 3.322 E-1 6.963 E-1 7;500 E-1 4.724 E-1 2.393 E-1 1-133 DE/1.311 E-1 3.291 E-1 9.04 E-2 1.222 E-0 9.33 E-2 1.333 E-0 4.92 E-2 9.064 E-1 3.01 E-2 5.386 E-1 I~~I I~}}
: Atlanta, I
Georgia 30303
 
==Dear Mr. O'Reilly:==
 
REPORTABLE OCCURRENCE    335-78-24 ST. LUG IE UNIT    1 DATE OF OCCURRENCE:      JUNE  25, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE E UIVALENT I-131 The  attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
Very    truly yours, A.    . c mi t Vice President Power Resources MAS/cpc Attachment cc:    Harold F. Reis, Esquire Doctor, Office of    Inspection and Enforcement (30) director, Office of      Management  Information and Program Control (3) 782l40106 PEOPLE... SERVING PEOPLE
 
S NRC FORM Saa                                                                                                                                          U. S. NUCI.EAR REGULATORY C SIMISSICiN I7.771 LICEIXScc EVCI'4T REPORT CONTROL, BLOC:<:                      I      I      I      I    I     .
Ql                  IPLSASE PRINT OR TYPP AL RSCUIRcO INFORN'IATIONI I
1 0  's 3
LIE        I i.iCENSca COOE LI        111 Q. 0                   01  101          0101 010 LICmslsa NIUAISER I -  I      I
                                                                                                                                          'S Q~ll ll 26 11 L;Cc<SE TV?E 11 40 Q~IIQ !~1!a CON'T
  ~o                      ":.'*i ML'Q                        '                          '            '                                                    i~a        I      I    In    I      I      QE 1          !                          !0             6)               CCCKET NVAISEs!            ~      63      sa        EVENT QATE                            IS       Rc?QAT    0*, 3          !0 EVENT OESCRIPTION 'NO                      PROGABLZE COVSECUENCES QIO Q  1          -Durin                  lant startuo from a sh r 16-hour m i tenance shutdown Dose
  ~03               E     uivalent DE Iodine exceeded the Technical S ecification .3.4.8.a limit of      1..0          Ci        ram        DOSE E          UIVALENT                I-131.            The        DE        Iodine            was      first measured
  ~os                above            this limit at                          1900 on'6 25 78                      while the                  lant        was      at 97/ ower.                      The!
0                                                                                                                                                                  1                    ifi atio
  ~o~                   .4.8.a.                A        revious occurrence of this                                        t        e    is described in                        LER      335-78-13!
  ~oa                                                                                                                                                                                                          !0 1         3 9 SYSTcal                  CAUSc            CAUSE                                                                C>l .            vALvE C OE                    COCE          SVSCCQE                    C NPONENT OOE                            svaccca          svacoQE QC 1        6 LZZZS WNS 9            Is)            Il WZG ~00 12                la 0              Zl      NS IS mic I9 ZZNS SECVENTIAI                              CCCVAAEiICE              REPORT                          REVISIQNN Qr LSR/Ao ENIEN ACTION CUTVAE r
VE'IT YEAR
                                            .~yg 2I          22 E?RECT
                                                                      ~
22 SIIUTOQWN
                                                                                        ~02 24 R EPOA T 40.
4 26
                                                                                                                    ~m 21
                                                                                                                                    ~03 AT,ACHMENT CQQE 29 4PROR tvPE
                                                                                                                                                                ~L 20 PRIMPC MP.
                                                                                                                                                                                                "IO, 32 COAIPON cN 4
                                                                                                                                                                                          ~c4 i TAKE44        ACTION'I             CN Pr&NVT,MET)soo                                  HOURS ~22          SVSMI ao            PCRM )Ua.          SVPPl,lcR              UANVPACTVRPR w
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                                                                'Q            LcQL 26
                                                                                                ~0          ~         0 JP
                                                                                                                                ~YQ ~NS 4I                  42 MNIQ 43                44 tl 41 CAUS" OESCRIPTIO I ANO CORREE                            0 IVE ACTIONS Q2i o          Af                        P                              ri            f        w                r i                i    h        nmina                    v  1'of fuel e        1 ant shutdown                      nd s            s            t    s sufficient to cause Iodine build u Iodine s ikin nenomenon                                                                                                            and exceed the urification ca acit for a short eriod of time.
  ~I 1
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                  ~ ATVS LJS
                          ~
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                                'S ''0 RELEAsco OP RELEASE L~J Q" 0
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QISCQV SAY OESCRIPTICN Q4-r tor        Observation LOCATION oP RPLEAsc          QSS 30
                      ?SRSONNEE            XirQSVRES TYPc CZ ~~Q2'I Z lO
                      ~ IVMSER                                QESCAIPTIQN QM A
3                        II      12              Is PERSONNEL Iiv)UR)ca 0         I00 0cii00 iiQN EZ 1        a L>~Q42 1              lp NA 30 P''6LIC,'.Y                                                                                                                                                  NRO ''SE C ILY CH)            LEQAA                                                                                                                                                      !! I!! I,! !! I!      I            I 1        3    1              lp
                                  'IAL      O    P    -      R    R        N. A. Scho                    man                                        ,.. ( 305 )            552-3802
 
      ~
LXCENSEE EVENT REPORT PAGE T'tiO
    ~  .C4  .C SUPPLEHENTARY INFORMATION TECHNXCAL SPECXFICATION PURPORT DOSE E UIVALENT IODXNE V
Reactor power histor startin            48 hours  rior  to the    first  sam  le in ,
which the limit was exceeded.
DATE                      TLilE                      AVERAGE REACTOR POHER 6/23/78                    1900    to                    ,97.1%    (steady state) 6/24/78                ,. 2000 6/24/78                    2100                            61 ..0%
6/24/78                    2200                            20.0%
r 6/24/78                    2300    to                      0-0%    (plant outage) 6/25/78                   1400,-     k 6/25/78                    1500                            38.5%
6/25/78                    1600                            66.3%
6/25/78                    1700                            90.0%
6/25/78                    1800                            95.0%
6/25/78                    1900%%                      *
: 97. 0%
Additional  Power History:      20%  80% from June 1      to June 12,      1978 98%  100% from June 13        to June 24, 1978 (DEQ    I-131; 2.4.5 E-I pCi/gram)
~ ~ '.    '.-  -= "--':First DEQ Iodine Sample '>I.O uCi/gram;:        "
                ~
E
 
QEPORTABLE OCCURRENCE              335-78-24 LIC~~']SEE EVENT REPORT
'AGE THREE SUPPLEMENTARX INFORMATION        (Cont)
: 2.         Fuel burnu      b    core re ion.
Fuel burnup by octants:
Region 1              10945.0 Region 2            '0893.7 Region'3              10781.0      Average Burnup in t
                , Region 4              10876.5      Megawatt Days per
                  'egion    5            10783.6     Metric Ton Uranium                            a Region,  6         ,, 10798.3      (I'O'D/HTU)
Region  7            10752.0 Region  8            10868.8 Total Core Average Burnup              10837.4 N                        \
: 3.          Clean-u flog histor~startin <>S hours                  rior  to the  tirst  sample in which the limit was exceeded.
Prom 1900 on 6/23/78 until 2100 on                6/24/78, purification flow rate was <82 gpm (two charging pumps).
At 2300 on 6/24/78,          purification flow rate      was reduced    to 52 gpm.
            ~ From 2400 on 6/24/78 until 0300 on                6/25/78,'urification flow rate was ~iO 'gpm (onc charging pump).
At 0400    on  6/25/78, purification flow rate            was  increased    to  58 gpm.
From 0500 on      6/25/78      until 1900 on 6/25/78,    purification flow rate vas w86    gpm  (two charging pumps).
NOTE:    Clean-up demineraliration consisted of a mixed bed at a 1:1
                      ~
ratio, cation to anion, with            a bcd volume of 36 cubic feet.
                                  ~    ~
4.::-:. -  His tor    of de- assin o eration s tar tin            48 hours    rior. to the  firs t sam  le in which the limit was exceeded.
No  degassing operations vere performed within the above 48-hour time span.
 
REPORTABLE OCCURRENCE  335-78-24 LICENSEE EVENT REPORT
, '+AGE IOUR SUPPLEHENTARY XNFORi~fATXON    (Cont)
: 5. The time duration when the s ecific      activit of    the rimar coolant exceeded 1.0 uCi/ ram DE X-131.
Iodine 131 Dose Equivalent was greater than 1.0 uCi/gram from 6/25/78 at 1900 until 6/26/78 at 0030. The total time above 1.0 uCi/gram was 5.50 hours.
                              ~"
: 6. Results of  S ecific Activit    Anal sis (uCi/ ram).
DATE    TINE    I-131          1-132            I-133      1-133    DE/
6/25/78 0215    2.249  E-1    9.66 E-2        3.322  E-1  1.311 E-1 3.291 E-1
        .6/25/78 1900    1.024  E-0    8.12 E-2        6.963  E-1  9.04 E-2  1.222 E-0 6/25/78 2010    1.120  E-0    7.38 E-2        7;500  E-1  9.33 E-2  1.333 E-0 6/26/78 0030    7.736  E-1  '.01      E-2      4.724  E-1  4.92 E-2  9.064 E-1 6/26/78 0615. 4.708  E-1    1.93 E-2        2.393  E-1 3.01 E-2 5.386 E-1 I
                                                      ~ ~
I I ~}}

Latest revision as of 03:08, 3 February 2020

LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent
ML18127A652
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 07/24/1978
From: Schmidt A
Florida Power & Light Co
To: O'Reilly J
NRC/RGN-II, NRC/IE
References
PRN-LI-78-198 LER 1978-024-00
Download: ML18127A652 (7)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIBS)

DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: OREILLY J P ORG: SCHMIDT A D DOCDATE: 07/24f78 NRC FL PWR 5 LIGHT DATE RCVD: 08/01/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-024) ON 06/25/78 CONCERNING DURING PLAN1 STARTUP FROM A SHORT MAINTENANCE i DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC 3. 4. 8. A LIMIT OF i. 0 UCI/QRAM DOSE EQUIVALENT I-131... W/ATT.

PLANT NAME: ST LUCIE Si REVIEWER INITIAL: X/M DISTRIBUTOR INITIAL:QQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++4<<+4<+<<<+4<<+

INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHIEF ORB84 BC++W/4 ENCL INTERNAL: F L ~ ENCL NRC PDR44~W/ENCL u +~W/2 ENCL MIPC+~W/3 ENCL I 8. C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR>~W/ENCL NOVAK/CHECK++WfENCL EEB4+W/ENCL AD FOR ENG~4W/ENCL PLANT SYSTEMS BR+4W/ENCL HANAUER~~W/ENCL AD FOR Pl ANT SYSTEMS+<W/ENCL AD FOR SYS 8c PROJ++W/ENCL REACTOR SAFETY BR>~W/ENCL ENGINEERING BR+4W/ENCL VOLLMER/BUNCH%4W/ENCL KREGER/J. COLLINS++W/ENCL POWER SYS BR++W/ENCL K SEYFRIT/ IE++W/ENCL EXTERNAL: LPDR S FT PIERCEi FL++W/ENCL TICi LIZ CARTER~~%W/ ENCL NS I C+~W/ENCL ACRS CAT B~~W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 782140106 SI ZE: iP+ 1 P+3P

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Atlanta, I

Georgia 30303

Dear Mr. O'Reilly:

REPORTABLE OCCURRENCE 335-78-24 ST. LUG IE UNIT 1 DATE OF OCCURRENCE: JUNE 25, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE E UIVALENT I-131 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.

Very truly yours, A. . c mi t Vice President Power Resources MAS/cpc Attachment cc: Harold F. Reis, Esquire Doctor, Office of Inspection and Enforcement (30) director, Office of Management Information and Program Control (3) 782l40106 PEOPLE... SERVING PEOPLE

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LXCENSEE EVENT REPORT PAGE T'tiO

~ .C4 .C SUPPLEHENTARY INFORMATION TECHNXCAL SPECXFICATION PURPORT DOSE E UIVALENT IODXNE V

Reactor power histor startin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> rior to the first sam le in ,

which the limit was exceeded.

DATE TLilE AVERAGE REACTOR POHER 6/23/78 1900 to ,97.1% (steady state) 6/24/78 ,. 2000 6/24/78 2100 61 ..0%

6/24/78 2200 20.0%

r 6/24/78 2300 to 0-0% (plant outage) 6/25/78 1400,- k 6/25/78 1500 38.5%

6/25/78 1600 66.3%

6/25/78 1700 90.0%

6/25/78 1800 95.0%

6/25/78 1900%% *

97. 0%

Additional Power History: 20% 80% from June 1 to June 12, 1978 98% 100% from June 13 to June 24, 1978 (DEQ I-131; 2.0 4.5 E-I pCi/gram)

~ ~ '. '.- -= "--':First DEQ Iodine Sample '>I.O uCi/gram;: "

~

E

QEPORTABLE OCCURRENCE 335-78-24 LIC~~']SEE EVENT REPORT

'AGE THREE SUPPLEMENTARX INFORMATION (Cont)

2. Fuel burnu b core re ion.

Fuel burnup by octants:

Region 1 10945.0 Region 2 '0893.7 Region'3 10781.0 Average Burnup in t

, Region 4 10876.5 Megawatt Days per

'egion 5 10783.6 Metric Ton Uranium a Region, 6 ,, 10798.3 (I'O'D/HTU)

Region 7 10752.0 Region 8 10868.8 Total Core Average Burnup 10837.4 N \

3. Clean-u flog histor~startin <>S hours rior to the tirst sample in which the limit was exceeded.

Prom 1900 on 6/23/78 until 2100 on 6/24/78, purification flow rate was <82 gpm (two charging pumps).

At 2300 on 6/24/78, purification flow rate was reduced to 52 gpm.

~ From 2400 on 6/24/78 until 0300 on 6/25/78,'urification flow rate was ~iO 'gpm (onc charging pump).

At 0400 on 6/25/78, purification flow rate was increased to 58 gpm.

From 0500 on 6/25/78 until 1900 on 6/25/78, purification flow rate vas w86 gpm (two charging pumps).

NOTE: Clean-up demineraliration consisted of a mixed bed at a 1:1

~

ratio, cation to anion, with a bcd volume of 36 cubic feet.

~ ~

4.::-:. - His tor of de- assin o eration s tar tin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> rior. to the firs t sam le in which the limit was exceeded.

No degassing operations vere performed within the above 48-hour time span.

REPORTABLE OCCURRENCE 335-78-24 LICENSEE EVENT REPORT

, '+AGE IOUR SUPPLEHENTARY XNFORi~fATXON (Cont)

5. The time duration when the s ecific activit of the rimar coolant exceeded 1.0 uCi/ ram DE X-131.

Iodine 131 Dose Equivalent was greater than 1.0 uCi/gram from 6/25/78 at 1900 until 6/26/78 at 0030. The total time above 1.0 uCi/gram was 5.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.

~"

6. Results of S ecific Activit Anal sis (uCi/ ram).

DATE TINE I-131 1-132 I-133 1-133 DE/

6/25/78 0215 2.249 E-1 9.66 E-2 3.322 E-1 1.311 E-1 3.291 E-1

.6/25/78 1900 1.024 E-0 8.12 E-2 6.963 E-1 9.04 E-2 1.222 E-0 6/25/78 2010 1.120 E-0 7.38 E-2 7;500 E-1 9.33 E-2 1.333 E-0 6/26/78 0030 7.736 E-1 '.01 E-2 4.724 E-1 4.92 E-2 9.064 E-1 6/26/78 0615. 4.708 E-1 1.93 E-2 2.393 E-1 3.01 E-2 5.386 E-1 I

~ ~

I I ~