ML18127A670: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 36: | Line 36: | ||
Reportable Occurrence 335-78-13.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION | 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 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) | =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) | ||
Region 5-11521.31)Region 6-12117.92)Region 7-11453.26)Region 8-12212.59)Total Core Average Burnup-11822.35 MWD/MTU | Region 5-11521.31)Region 6-12117.92)Region 7-11453.26)Region 8-12212.59)Total Core Average Burnup-11822.35 MWD/MTU | ||
[ASE PRINT AU.REGUIRED INFORMATION) | [ASE PRINT AU.REGUIRED INFORMATION) | ||
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 | 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 |
Revision as of 11:24, 25 April 2019
ML18127A670 | |
Person / Time | |
---|---|
Site: | Saint Lucie |
Issue date: | 04/27/1978 |
From: | Schmidt A D Florida Power & Light Co |
To: | O'Reilly J P NRC/IE, NRC/RGN-II |
References | |
PRN-LI-78-121 LER 1978-013-00 | |
Download: ML18127A670 (9) | |
Text
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:
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 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
'5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY
<t'II)E 10.1 ISTRIBUTION:
LTR 45 ENCL 45 S I ZF: 2P+3P K%%%4%%%%4
%%%%%%%4M%%%%%%%%%%%%%%%4'HE END CONTROL NBR: 781300092
':.,<~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
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)L 7813000P2 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 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)
Region 5-11521.31)Region 6-12117.92)Region 7-11453.26)Region 8-12212.59)Total Core Average Burnup-11822.35 MWD/MTU
[ASE PRINT AU.REGUIRED INFORMATION)
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
[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).
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 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 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 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