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{{#Wiki_filter:a fm/~~REGULATORY INFORMATION DISTRIBUTION SYSTEl'1 (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC'REILLY J P NRC ORG: SCHMIDT A D FL PIJR 8(LIGHT DOCDATE: 04/27/78 DATE RCVD: 05/09/78 DOCTYPE: LETTER NOTARIZED:
{{#Wiki_filter:a         fm/~~
NO COPIES RECEIVED  
REGULATORY INFORMATION DISTRIBUTION SYSTEl'1         ( RIDS)
DISTRIBUTION FOR INCOMING MATERIAL                                 50-335 REC'REILLY J       P               ORG: SCHMIDT A D                         DOCDATE: 04/27/78 NRC                              FL PIJR 8( LIGHT                        DATE RCVD: 05/09/78 DOCTYPE:   LETTER     NOTARIZED: NO                                               COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-335/78-i3)
LTR i       ENCL i FORWARDING LICENSEE EVENT REPT (RO         50-335/78-i3) ON 03/28/78         CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC
ON 03/28/78 CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC 3.4.8...W/ATT.PLANT NAME: ST LUCIE 8i INCIDENT REPORTS (DISTRIBUTION CODE A002)REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS FOR ACTION: INTERNAL: EXTERNAL: BR C~N/4 ENCL R G FILE~~~W/ENCL I~~W Ne SCHROEDERf I PPOL I TO%4M/ENCL NOVAK/CHECK44W/ENCL KNIGHT++Wf ENCL HANAUER~~~l J/ENCL EI SENHUT+~N/ENCL SHAO~~~W/ENCL KREGER/J.COLL INS++Wf ENCL K SEYFR IT/IE+4FW/ENCL LPDR S FT PIERCE(FL++W/ENCL TIC4s>W/ENCL NSIC++Wf ENCL ACRS CAT B4l~W/16 ENCL NRC PDR+>W/ENCL MIPC++W/3 ENCL HOUSTON+>W/ENCL EEB4+W/ENCL BUTI ER4+Wf ENCL TEDESCO~~W/ENCL BAER~~~N/ENCL VOLLMER/BUNCHwwW/ENCL ROSA%+ltJ/ENCL
: 3. 4. 8... W/ATT.
'5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY
PLANT NAME: ST LUCIE     8i                                       REVIEWER       INITIAL: X JM DISTRIBUTOR         INITIAL:
<t'II)E 10.1 ISTRIBUTION:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)
LTR 45 ENCL 45 S I ZF: 2P+3P K%%%4%%%%4
FOR ACTION:       BR C             ~N/4 ENCL INTERNAL:        R G   FILE~~~W/ENCL                  NRC PDR+>W/ENCL I     ~~W     Ne                   MIPC++W/3 ENCL SCHROEDERf I PPOL I TO%4M/ENCL      HOUSTON+>W/ENCL NOVAK/CHECK44W/ENCL                  EEB4+W/ENCL KNIGHT++WfENCL                      BUTI ER4+Wf ENCL HANAUER~~~l J/ENCL                  TEDESCO~~W/ENCL EI SENHUT+~N/ENCL                    BAER~~~N/ ENCL SHAO~~~W/ENCL                        VOLLMER/BUNCHwwW/ENCL KREGER/ J. COLL INS++WfENCL        ROSA%+ltJ/ENCL K SEYFR IT/IE+4FW/ENCL EXTERNAL:        LPDR S FT PIERCE( FL++W/ENCL TIC4s>W/ENCL NSIC++WfENCL ACRS CAT B4l ~W/16 ENCL
%%%%%%%4M%%%%%%%%%%%%%%%4'HE END CONTROL NBR: 781300092
                                                                    '5   POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY <t'II)E 10. 1 ISTRIBUTION:     LTR 45     ENCL 45                           CONTROL NBR:            781300092 S I ZF: 2P+3P K%%%4%%%%4 %%%%%%%4M%%%%%%%%%%%%%%%4'HE           END


':.,<~F;j (j 9:-:-FLORIOA POWER III LIGHT COMPANY ,April 27, 1978 Mr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S.Nuclear.Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, Georgia 30303 PRN-LI-7~\A (Cl-<ChC 1'(1 C7 Cfk 8+~21 (C (A fll~WP1 Rc7 Pl CP~C(7 C7
                                                      ':.,       <~F;j (j 9:-:-
FLORIOA POWER   III LIGHT COMPANY
                                                    ,April       27, 1978 PRN-LI-7 8+~21                (C (A
fll~
WP1
                                                              \A                Rc7
                                                        ~
(                    Pl C(7 CP~
Mr. James P. O'Reilly, Director, Region   II           Cl
                                                        -<ChC 1
                                                          '(1 Office of Inspection and Enforcement U. S. Nuclear. Regulatory Commission                       C7                      C7 230 Peachtree Street, N.W., Suite 1217                     Cfk Atlanta, Georgia 30303


==Dear Mr.O'Reilly:==
==Dear Mr. O'Reilly:==
REPORTABLE OCCURRENCE 335-78-13 ST.LUCIE UNIT 1.DATE OF OCCURRENCE:
 
MARCH 28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT 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'ccurrence.
REPORTABLE OCCURRENCE 335-78-13 ST. LUCIE UNIT 1
Very truly yours, A.D.Schmidt Vice President Power Resources MAS/mb Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)L 7813000P2 PEOPLE...SERVING PEOPLE P
                  .DATE OF OCCURRENCE: MARCH   28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT I-131                   ,~
Reportable Occurrence 335-78-13.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION
The attached Licensee Event Report is being submitted in accordance .with Technical Specification 6.9 to provide 30-day notification of the subject'ccurrence.
=TECHNICAL SPECIFICATION REPORT"DOSE EQUIVALENT IODINE 1.Reactor power history starting 48 hours prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200 until 3/28/78 90900, the plant was at.an average steady state power of 99.5%, at, which time preparations.for refueling shutdown were begun:.3/28/78 3/28/78'/28/78 3/28/78 3/28/78 81000 81100 91200'81300 92245*Rx Power 92.4%Rx Power 69.0%Rx Power 30.0%Off-line (Hot.Standby for S/G Safety Valve Testing)Off-line (Hot Standby for S/G Safety Valve Testing)'First Iodine Sample>1.0 yCi/gram DEQ 2.Fuel burnu b core re ion Puel burnup by octants: Region 1-11291.08)Region 2-12256.19)Average Burnup in.Megawatt Days R 5-11521 31)per Metric Ton ,'Uranium'(llHD/MTU)
Very truly yours, A. D. Schmidt Vice President Power Resources MAS/mb Attachment cc:   Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement         (30)
Region 5-11521.31)Region 6-12117.92)Region 7-11453.26)Region 8-12212.59)Total Core Average Burnup-11822.35 MWD/MTU
Director, Office of Management Information and Program Control (3) 7813000P2 L
[ASE PRINT AU.REGUIRED INFORMATION)
PEOPLE... SERVING PEOPLE
CONTROL BLOCK: 1 UCENSEE NAME 01 F L S L S LCENSE EVENT TYPE TYPE d 1 1 1 1~03 26 30 31 32 LCENSE NUMEEA 1 0 0-0 0 0 0 0-0 0 7 89 14 15=25 AEPOAT SOURCE AEPOAT CATEGORY TYPE'OD1]OON'T
 
~7 8 57 58 59 OOCKET NUMecA 0-0 3 3 5 0 68 69 EVENT OATE AEPOAT OATE 3 2 8 7 8 0 4 2 7 7 8 74 75 80 L 0 5 60 61 EVENT OESCRlPTION QO 2 Durin shutdown for re'fueling, Dose Equivalent (DEQ)Iodine exceeded the Technical' 69 tOD~]first measured above the limit at 2245 on 3/28/78 while the plant was in hot standby 7 8 9 60 g for required surveillance testing prior to continuation of the cooldown.The attached 7 8 9[OD~}sheets contain the information required by (Continued-under ADDITIONAL FACTORS)7 8 9 SYSTEM CAUSE CODE COQE CorrtPONENT COOE[Og7]~@Q~E 7 0 E L I I I 7 8 9 10 11 12 17 CAUSF OESCRIPTION Qg After an extended eriod of ower 80 COMPONENT MANUF~iFER VIQLATIC N C 4 9 0 N 44 47 FAME CCMPQ RENT SUPPUM N a8 o eration with a nominal level of fuel leaka,e, the 7 8 9 gg lant sbutdornr ttansient was sufficient to cause Iodine to build up (Iodine spiking eo 7 8 9~10 i a i ca acitv for a short: eriod of time.7 BS FACIUTY STATUS POWE'A OTHER STATUS Qi r~H~0 0 0 gee Event oesc.8 S 10 12 13 FORM OF ACTMTY CO/TENT AELcckSEO OF RELEASE AMOUNT OF ACFiVITY~z~z 7 9 9 10 11 PERSONNEL EXPOSURES NUMia'EA TYPE OESCRIPTIQN
P Reportable Occurrence 335-78-13
[iran]~oo o~z E//t 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER CESCAIPTIQN Irr4j~oo o N/A~7 89 11 12 80 McTHQO OF OISCOVERY oiscovERY oescaipnioN N/A 45 dt6 80 LOCATION OF A~OSE N/A 80 80 PROpdLSLE CONSEGUENC S N/A 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPnQN 89 10 PUBLICITY N/A 80 N/A 7 8 9~80 AOOITIONAL FACTORS CG Technical Soecification 3.4.8.a.This was the first event of this type.(335-78-13).
.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION
7 89 80 fr19J 7 89 60>f.A.Schoppman PHONE'057 552-3802 CI'0 dd'I 4 d dT 7 8 9 80 I S ecification 3.4.8.a limit of 1.0 pCi/gram DOSE EQUIVALENT I-131.The DEQ Iodine was page three Re: Reportable Occurrence 335-78-13 3.Clean-up flow history starting 48 hours prior to the first sam le in which the limit was exceeded From 3/26/78 92200 until 3/28/78 81400, purification flow rate was-88 gpm (two charging pumps).At 1400 on 3/28/78 a third charging pump was started, thereby raising purification flow rate to-132 gpm.The purification flow rate was maintained at-132 gpm until the start of Shutdown Cooling (SDC)at 0430 on 3/29/78.NOTE: Clean-up demineralization consisted of a mixed bed at a 1:1 ratio, cation to anion, in series with a straight anion bed.Bed volumes were 36 cubic feet each.4.History of de-gassing operation'tarting 48 hours prior to the first samole in which the limit was exceeded DATE 3/20/78 3/21/78 3/23/78 3/24/78 3/26/78 3/27/78 3/28/78 3/28/78 3/28/78 3/28/78 3/29/78 LOCATION VCT gas space RCS dissolved gas Shifted to H2 regulator on VCT cover gas.RCS dissolved gas VCT purged several times with N2'.VCT gas space RCS dissolved gas 90045 RCS dissolved gas 90930 VCT gas space 91800 Purged VCT with N2 92000 VCT gas space H2%,95 6 1.0 H2 (cc/k)12.1 16.9 2;.6 1.7 Page four Re: Reportable Occurrence 335-78-13 5..The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/qram DOSE EQUIVALENT I-131.Iodine 131 Dose Equivalent was greater then 1.0 pCi/gram from 3/28/78 92245 to 3/29/78 gll30.The total time above 1.0 pCi/gram was 12.75 hours.6.Results of S ecific Activit Anal sis (pCi/ram)DATE TIME I-131 I-132 I-133 DEQ 3/28/78 3/28/78 3/29/78 3/29/78 3/29/78 3/29/78 1500 2245 0100 0420 0730 1130 6.7 E-1 1.6 E-0 1.13 E-0 1.23 E-0 9.87 E-1 4.99 E-1 6.7 E-1?,.6 E-1 9.1 E-2 6.5 E-2 3.03 E-2 6.7 E-1 1.2 E-0 8.15 E-1 7.8 E-1 5.84 E-1 2.37 E-1 3.1 E-1 3.2 E-1 1.9 E-1 1.5 E-1 8.9 E-2.89 1.91 l.37 l.46 l.15.56 0}}
                  =TECHNICAL SPECIFICATION REPORT "DOSE EQUIVALENT IODINE
: 1. Reactor power history starting 48 hours prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200       until 3/28/78 90900, the plant was at. an average steady state power of 99.5%, at, which time preparations
.for refueling shutdown were begun:
            .3/28/78                   81000            Rx Power 92.4%
3/28/78                   81100            Rx Power 69.0%
          '/28/78                     91200            Rx Power 30.0%
3/28/78                   '81300             Off-line (Hot.
Standby   for S/G Safety Valve Testing) 3/28/78                    92245*            Off-line (Hot Standby for S/G Safety Valve Testing)'First Iodine Sample     > 1.0 yCi/gram DEQ
: 2. Fuel burnu     b   core re ion Puel burnup by octants:
Region 1     11291.08)
Region 2     12256.19)
Average Burnup in .Megawatt   Days Region R       5   11521.31) 11521 31)     per Metric Ton ,'Uranium'(llHD/MTU)
Region   6    12117.92)
Region   7   11453.26)
Region   8   12212.59)
Total Core Average Burnup           11822.35 MWD/MTU
 
CONTROL BLOCK:
[     ASE PRINT AU. REGUIRED INFORMATION) 1 UCENSEE                                                                                                   LCENSE                  EVENT NAME                                               LCENSE NUMEEA                                          TYPE                    TYPE 01        F     L   S   L   S               1        0    0    0      0    0    0  0    0        0          d   1   1     1   1     ~03 89
                    ~
7                                              14    15                                                =25      26                       30     31     32 AEPOAT               AEPOAT CATEGORY                          SOURCE               OOCKET NUMecA                              EVENT OATE                          AEPOAT OATE TYPE'OD1]OON'T L        0  5    0   0         3   3   5         0   3     2   8     7     8       0     4   2   7   7       8 7      8        57      58            59            60       61                                   68    69                            74    75                          80 I
EVENT OESCRlPTION QO 2       Durin shutdown for re'fueling, Dose Equivalent                                             (DEQ)     Iodine exceeded the Technical' 7    8 9                                                                                                                                                                      80 S  ecification 3.4.8.a limit of 1.0 pCi/gram                                        DOSE EQUIVALENT              I-131.        The  DEQ      Iodine    was 69 tOD~]        first measured                      above the        limit at      2245 on 3/28/78          while the plant was in hot standby 7     8 9                                                                                                                                                                       60 g           for required surveillance testing prior to continuation of the cooldown. The attached 7     8 9
[OD~}       sheets contain the information required by (Continued -under ADDITIONAL FACTORS) 7     8 9                                                                             FAME                                                                                    80 SYSTEM     CAUSE                                                       CCMPQ RENT            COMPONENT
[Og7] ~@
CODE Q
COQE
                          ~E                       7 CorrtPONENT COOE 0     E   LI  I I             SUPPUM N            C MANUF~iFER 4    9    0 VIQLATICN N
7      8 9 10             11                 12                           17                     44                    47            a8 CAUSF OESCRIPTION Qg8          After     an extended                     eriod of ower             o  eration with        a    nominal      level of fuel leaka,e, the 7         9                                                                                                                                                                   eo gg             lant   sbutdornr                 ttansient         was   sufficient to         cause     Iodine to build up (Iodine spiking 7 8       9
  ~10 7 BS ia i         ca   acitv for         a   short:     eriod of time.
FACIUTY                                                                       McTHQO OF 80 STATUS                   POWE'A                       OTHER STATUS           OISCOVERY                            oiscovERY oescaipnioN Qi r         ~H           ~0             0     0         gee Event oesc.                                             N/A 8       S             10                       12 13                                     45      dt6                                                                  80 FORM OF ACTMTY       CO/TENT AELcckSEO     OF RELEASE                       AMOUNT OF ACFiVITY                                                   LOCATION OF    A~OSE
                ~z           ~z                             N/A 7     9       9               10                 11                                                                                                                           80 PERSONNEL EXPOSURES NUMia'EA       TYPE                 OESCRIPTIQN
[iran]     ~oo         o     ~z                                           E//t 7 8 9                   11     12               13                                                                                                                           80 PERSONNEL INJURIES NUMBER           CESCAIPTIQN Irr4j     ~oo         o                                                   N/A   ~
7     89               11   12 PROpdLSLE CONSEGUENC S N/A 7     8 9 LOSS OR OAMAGE TO FACILITY TYPE     OESCAIPnQN N/A 89           10                                                                                                                                                           80 PUBLICITY N/A 7    8 9                                                                                                                                                                     ~ 80 AOOITIONAL FACTORS CG Technical Soecification 3.4.8.a.                                               This was the         first     event of       this type. (335-78-13).
7     89                                                                                                                                                                         80 fr19J 7     89                                                                                                                                                                       60
                                    >f. A. Schoppman                                                                     PHONE'057 552-3802 CI'0 dd'I 4 d dT
 
page  three Re:  Reportable Occurrence 335-78-13
: 3. Clean-up flow history starting 48 hours       prior to the     first sam le in which the limit was exceeded From 3/26/78 92200     until 3/28/78 81400,   purification flow rate was -88 gpm (two charging pumps).
At 1400 on 3/28/78 a third charging pump was started, thereby raising purification flow rate to -132 gpm.
The purification flow rate was maintained at -132 gpm until the start of Shutdown Cooling (SDC) at 0430 on 3/29/78.
NOTE:   Clean-up demineralization consisted of a mixed bed at a 1:1 ratio, cation to anion, in series with a straight anion bed. Bed volumes were 36 cubic feet each.
: 4. History of de-gassing operation'tarting       48   hours prior to the first samole   in which the limit was   exceeded DATE         LOCATION                          H2%      H2 (cc/k  )
3/20/78       VCT gas    space                ,95 3/21/78       RCS  dissolved gas                          12.1 3/23/78       Shifted to H2 regulator on VCT cover gas.
3/24/78       RCS  dissolved gas                          16. 9 3/26/78       VCT  purged several times with    N2'.
3/27/78       VCT gas    space 3/28/78       RCS  dissolved gas 90045                      2;.6 3/28/78       RCS  dissolved gas 90930                      1.7 3/28/78       VCT gas    space 91800              6 3/28/78       Purged VCT    with  N2 92000 3/29/78       VCT gas   space                 1.0
 
Page  four Re:    Reportable Occurrence 335-78-13
: 5.  .The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/qram DOSE EQUIVALENT I-131.
Iodine  131 Dose Equivalent was greater then 1.0 pCi/gram from 3/28/78 92245 to 3/29/78 gll30. The total time above 1.0 pCi/gram was 12.75 hours.
: 6. Results of   S ecific Activit  Anal sis (pCi/ ram)
DATE      TIME    I-131     I-132    I-133            DEQ 3/28/78     1500    6.7 E-1   6.7 E-1  6.7 E-1  3.1 E-1  .89 3/28/78      2245    1. 6 E-0  ?,. 6 E-1 1.2 E-3.2 E-1 1.91 3/29/78     0100    1. 13 E-0 9.1 E-2  8.15 E-1.9 E-1 l. 37 3/29/78      0420    1.23 E-0 6.5 E-2  7.8 E-1   1.5 E-1 l. 46 3/29/78      0730    9.87 E-1 3.03 E-2 5.84 E-1  8.9 E-2 l. 15 3/29/78      1130    4.99 E-1           2. 37 E-1           .56
 
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Latest revision as of 06:29, 21 October 2019

LER 1978-013-00 for St. Lucie Unit 1, on 03/28/78 Concerning During Shutdown for Refueling, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8
ML18127A670
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 04/27/1978
From: Schmidt A
Florida Power & Light Co
To: O'Reilly J
NRC/IE, NRC/RGN-II
References
PRN-LI-78-121 LER 1978-013-00
Download: ML18127A670 (9)


Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEl'1 ( RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC'REILLY J P ORG: SCHMIDT A D DOCDATE: 04/27/78 NRC FL PIJR 8( LIGHT DATE RCVD: 05/09/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-335/78-i3) ON 03/28/78 CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC

3. 4. 8... W/ATT.

PLANT NAME: ST LUCIE 8i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR C ~N/4 ENCL INTERNAL: R G FILE~~~W/ENCL NRC PDR+>W/ENCL I ~~W Ne MIPC++W/3 ENCL SCHROEDERf I PPOL I TO%4M/ENCL HOUSTON+>W/ENCL NOVAK/CHECK44W/ENCL EEB4+W/ENCL KNIGHT++WfENCL BUTI ER4+Wf ENCL HANAUER~~~l J/ENCL TEDESCO~~W/ENCL EI SENHUT+~N/ENCL BAER~~~N/ ENCL SHAO~~~W/ENCL VOLLMER/BUNCHwwW/ENCL KREGER/ J. COLL INS++WfENCL ROSA%+ltJ/ENCL K SEYFR IT/IE+4FW/ENCL EXTERNAL: LPDR S FT PIERCE( FL++W/ENCL TIC4s>W/ENCL NSIC++WfENCL ACRS CAT B4l ~W/16 ENCL

'5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY <t'II)E 10. 1 ISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781300092 S I ZF: 2P+3P K%%%4%%%%4 %%%%%%%4M%%%%%%%%%%%%%%%4'HE END

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FLORIOA POWER III LIGHT COMPANY

,April 27, 1978 PRN-LI-7 8+~21 (C (A

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Mr. James P. O'Reilly, Director, Region II Cl

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'(1 Office of Inspection and Enforcement U. S. Nuclear. Regulatory Commission C7 C7 230 Peachtree Street, N.W., Suite 1217 Cfk Atlanta, Georgia 30303

Dear Mr. O'Reilly:

REPORTABLE OCCURRENCE 335-78-13 ST. LUCIE UNIT 1

.DATE OF OCCURRENCE: MARCH 28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT 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'ccurrence.

Very truly yours, A. D. Schmidt Vice President Power Resources MAS/mb Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and Program Control (3) 7813000P2 L

PEOPLE... SERVING PEOPLE

P Reportable Occurrence 335-78-13

.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION

=TECHNICAL SPECIFICATION REPORT "DOSE EQUIVALENT IODINE

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200 until 3/28/78 90900, the plant was at. an average steady state power of 99.5%, at, which time preparations

.for refueling shutdown were begun:

.3/28/78 81000 Rx Power 92.4%

3/28/78 81100 Rx Power 69.0%

'/28/78 91200 Rx Power 30.0%

3/28/78 '81300 Off-line (Hot.

Standby for S/G Safety Valve Testing) 3/28/78 92245* Off-line (Hot Standby for S/G Safety Valve Testing)'First Iodine Sample > 1.0 yCi/gram DEQ

2. Fuel burnu b core re ion Puel burnup by octants:

Region 1 11291.08)

Region 2 12256.19)

Average Burnup in .Megawatt Days Region R 5 11521.31) 11521 31) per Metric Ton ,'Uranium'(llHD/MTU)

Region 6 12117.92)

Region 7 11453.26)

Region 8 12212.59)

Total Core Average Burnup 11822.35 MWD/MTU

CONTROL BLOCK:

[ ASE PRINT AU. REGUIRED INFORMATION) 1 UCENSEE LCENSE EVENT NAME LCENSE NUMEEA TYPE TYPE 01 F L S L S 1 0 0 0 0 0 0 0 0 0 d 1 1 1 1 ~03 89

~

7 14 15 =25 26 30 31 32 AEPOAT AEPOAT CATEGORY SOURCE OOCKET NUMecA EVENT OATE AEPOAT OATE TYPE'OD1]OON'T L 0 5 0 0 3 3 5 0 3 2 8 7 8 0 4 2 7 7 8 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT OESCRlPTION QO 2 Durin shutdown for re'fueling, Dose Equivalent (DEQ) Iodine exceeded the Technical' 7 8 9 80 S ecification 3.4.8.a limit of 1.0 pCi/gram DOSE EQUIVALENT I-131. The DEQ Iodine was 69 tOD~] first measured above the limit at 2245 on 3/28/78 while the plant was in hot standby 7 8 9 60 g for required surveillance testing prior to continuation of the cooldown. The attached 7 8 9

[OD~} sheets contain the information required by (Continued -under ADDITIONAL FACTORS) 7 8 9 FAME 80 SYSTEM CAUSE CCMPQ RENT COMPONENT

[Og7] ~@

CODE Q

COQE

~E 7 CorrtPONENT COOE 0 E LI I I SUPPUM N C MANUF~iFER 4 9 0 VIQLATICN N

7 8 9 10 11 12 17 44 47 a8 CAUSF OESCRIPTION Qg8 After an extended eriod of ower o eration with a nominal level of fuel leaka,e, the 7 9 eo gg lant sbutdornr ttansient was sufficient to cause Iodine to build up (Iodine spiking 7 8 9

~10 7 BS ia i ca acitv for a short: eriod of time.

FACIUTY McTHQO OF 80 STATUS POWE'A OTHER STATUS OISCOVERY oiscovERY oescaipnioN Qi r ~H ~0 0 0 gee Event oesc. N/A 8 S 10 12 13 45 dt6 80 FORM OF ACTMTY CO/TENT AELcckSEO OF RELEASE AMOUNT OF ACFiVITY LOCATION OF A~OSE

~z ~z N/A 7 9 9 10 11 80 PERSONNEL EXPOSURES NUMia'EA TYPE OESCRIPTIQN

[iran] ~oo o ~z E//t 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER CESCAIPTIQN Irr4j ~oo o N/A ~

7 89 11 12 PROpdLSLE CONSEGUENC S N/A 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPnQN N/A 89 10 80 PUBLICITY N/A 7 8 9 ~ 80 AOOITIONAL FACTORS CG Technical Soecification 3.4.8.a. This was the first event of this type. (335-78-13).

7 89 80 fr19J 7 89 60

>f. A. Schoppman PHONE'057 552-3802 CI'0 dd'I 4 d dT

page three Re: Reportable Occurrence 335-78-13

3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sam le in which the limit was exceeded From 3/26/78 92200 until 3/28/78 81400, purification flow rate was -88 gpm (two charging pumps).

At 1400 on 3/28/78 a third charging pump was started, thereby raising purification flow rate to -132 gpm.

The purification flow rate was maintained at -132 gpm until the start of Shutdown Cooling (SDC) at 0430 on 3/29/78.

NOTE: Clean-up demineralization consisted of a mixed bed at a 1:1 ratio, cation to anion, in series with a straight anion bed. Bed volumes were 36 cubic feet each.

4. History of de-gassing operation'tarting 48 hours prior to the first samole in which the limit was exceeded DATE LOCATION H2% H2 (cc/k )

3/20/78 VCT gas space ,95 3/21/78 RCS dissolved gas 12.1 3/23/78 Shifted to H2 regulator on VCT cover gas.

3/24/78 RCS dissolved gas 16. 9 3/26/78 VCT purged several times with N2'.

3/27/78 VCT gas space 3/28/78 RCS dissolved gas 90045 2;.6 3/28/78 RCS dissolved gas 90930 1.7 3/28/78 VCT gas space 91800 6 3/28/78 Purged VCT with N2 92000 3/29/78 VCT gas space 1.0

Page four Re: Reportable Occurrence 335-78-13

5. .The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/qram DOSE EQUIVALENT I-131.

Iodine 131 Dose Equivalent was greater then 1.0 pCi/gram from 3/28/78 92245 to 3/29/78 gll30. The total time above 1.0 pCi/gram was 12.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.

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

DATE TIME I-131 I-132 I-133 DEQ 3/28/78 1500 6.7 E-1 6.7 E-1 6.7 E-1 3.1 E-1 .89 3/28/78 2245 1. 6 E-0  ?,. 6 E-1 1.2 E-0 3.2 E-1 1.91 3/29/78 0100 1. 13 E-0 9.1 E-2 8.15 E-1 1.9 E-1 l. 37 3/29/78 0420 1.23 E-0 6.5 E-2 7.8 E-1 1.5 E-1 l. 46 3/29/78 0730 9.87 E-1 3.03 E-2 5.84 E-1 8.9 E-2 l. 15 3/29/78 1130 4.99 E-1 2. 37 E-1 .56

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