ML18127A652

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
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;: "

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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.

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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

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

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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 />.

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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

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