05000324/LER-1981-063-03, /03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased

/03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased

ML20009H485
Person / Time
Site:	Brunswick
Issue date:	07/28/1981
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009H481	List: 05000324/LER-1981-063, Forwards LER 81-063/03L-0 05000324/LER-1981-063-03, /03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased
References
LER-81-063-03L, LER-81-63-3L, NUDOCS 8108100173
Download: ML20009H485 (5)

LER-1981-063, /03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased

Event date:
Report date:
3241981063R03 - NRC Website

text

NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)g*

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIEN) 1 6

lo ltl l N l C l B l E l P l 2 l@l 0 l 0 l - l 0 l 0 l 0 l 0 l 0 l-l0 l 0 l@l 4 l 1l ll 1l 1l@l l

l@

7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO

$7 CAT 58 CON'T lolil S$R I b hl 0 l 5 l 0 l-l 0 l 3 l 2 l4 @] 0 l 7 l0 l3 l 8 l1 l@l0 l 712 l 818 l1 l@

7 8

60 61 DOCKET NUMBER 68 69 EV8NT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND F ROBABLE CONSEQUENCES h 10 l 2 l l During a reactor startup following a reactor scram from 9% power on July 2. 1981.

I l reactor coolant activity exceeded the technical specification limit of 0.2 pCi/gm.

l o 3 dose equivalent for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, with the highest recorded activity at.2589 pCi/gm.l [o l4 l l Iiy l This event did not affect the health or safety of the public.

l o s 10 l6 l l l

I O l 71 1 I

l 0 l81 l Technical Specifications 3.4.5, 6.9.1.9b i

80 7

8 9 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE g

l P l B l@ {@ {@ l Zl Zl Zl Zl Zl Zl@ l Z l@ y @

7 8

9 to 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION LE R /RO EVENT YEAR REPORT NO.

COO 6 TYPE N O.

@ gU l 8l 1l l_l l0 l6 3 l y

l0l3l lL l

[-J W

RE

_ 21 22 23 24 26 27 N

M JO 31 32 AK N AC 0 ON PL NT MET HOURS SB B FOR B.

SUPPLIE V N F CTUREH lxJ@LzJ@

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l0Iol010I LN_J@

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33 34 36 36 3/

40 41 42 s1 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h was a result of the scrnm uirh n ciih a n n ii nn e-innennco in cool;ht l1lOllThe hich coolant activity I

l1 l1[ lfission product inventory originatinn from a leakinc fuel element.

Ronernr nnune [was increased and the iodine act.ivity returned to within specifications.

The Unit No.12 i 2 i 3 l fuel bundles wil_1 be sipped during the next refueling otitage and ti:e leaking bundles l

l t 4 l removed from the core.

80 7

8 9 STA S

% POWE R OTHER STATUS Dis OV RY DISCOVERY DESCRIPTION NA l (A_j@l Coolant Sampling l

l115 l W@ l0 l 0 l1 l@l ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l l

NA l

, l 1 l G l d @ W@l 7

8 9 10 11 44 45 80 PERSONNEL E XPOSUR:S NUVBER TYPE

DESCRIPTION

NA l

l0l0l0l@ W @l 1 7 IES PERSONNEL INJU DESCRIPTION @

NUMBER NA l

l0l0l0l@l i a 80 7

9 11 12 LOSS OF OR DAMAGE TO FACILITY h TYPE DE SCRiPTION v

NA l

W lZl@l 80 7

8 9 10 PUUt ICIT Y NRC USE ONLY ISSUE D

DESCRIPTION

NA l

lllll1Illllll*4 M Whl 68

84 i

8108100173 810728 M. J. Pastva, Jr.

919-457-9521 o

PDR ADOCK 05000324 "

p 2L R @ '

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Off-Gas Analysis Prior to this incident, the following Unit No. 2 steam jet air ejector (SJAE) off gas level was measured:

Date Reactor Power %

Off-Gas pCi/sec at SJAF 6/18/81 96%

2.40943 E 4 6/19/81 96%

2.5227 E 4 6/30/81 86.4%

2.0104 E 4 Following this incident, the following Unit No. 2 steam jet air ejector (SJAE) off gas level was measured:

Date Reactor Power %

Off-Gas pCi/sec at SJAE 7/6/81 86.2%

1.874013 E 4 7/8/81 88.2%

2.41197 E 4 7/9/81_

87.8%

2.29793 E'4 l

l 7

i L-

. ~,

-..- ~,.-.

. _ ~ - - _..

i LER INFORMATION SHEET IODINE CONCENTRATIONS pCi/ML e

1 Date Time T Power l-131 1-132 l-133 I-834 l-135 l-13I Dose Eaulvalent 6/28/81-0835' 20%

l.046E-l 9.662E-3

< MDA 7.958E-3 2.374E-3 1.05lE-1

'6/28/81 1250-20%

7.229t'-2 9.33E-3

< MDA 2.505E-2 8.080E-3 7.328E-2 6/28/81' 1750 49%

4.236E-2 1.ll5E-2 7.648E-3 4.617E-2 1.663E-2 4.626E-2 6/30/81 1045 84%

.l.06tE-3 1.142E-2 9.728E-3 4.469E-2 1.978E-2 5.807E-3 7/1/88 1355 91%

8.203E-4 1.348E-2 1.034E-2 4.480E-2 l'.761 E-2 5.637E-3 7/2/81 0153 Unit No. 2 7cator Scram 7/2/81 0639 0%

7/2/81 Unit No. 2 Reactor Startup @ 0639

7/2/88 0724 0%

1.235E-3 1.587E-2 9.816E-3 2.152E-3 7.656E-3 5.149E-3

'7/2/81 1824 Unig ho. 2 Reacter Critical 7/2/81 l145 Cri t ica l 9.669E-4 I.394E-2

_6.262E-3 < MDA 3.080E-3 3.445E-3 7/2/81 1523 Uni t No. 2. Reactor 'Porer Level 9.0% Power Level 7/2/81

.2011 Unit No. 2 Reactor Scram approximately 9.0% Power 7/2/81 2320

_ Unit No. 2 Reactor Sta rtup @ 2320 7/3/81 0115 0%

1.625E-1 2.839E-2 1.589L-1 1.572E-2 2.808E-2 2.100E-l 7/3/81 0326 4%

1.614E-1 2.398E-2 1.403E-l. < MDA 1.861E-2 2.028E-l l

- 7/3/81 0526' 10%

l.87tE-l 2.618E-2 1.460E-4 < MDA l.675E-2

~

2 300E-l 7/3/81 0835 10%

2.142E-l 2.627E-2 1.534E-1 < MDA 1.400E-2 2.589E-1 7/3/81 1810 1.575E-l 2.037E-2 1.170E-l 9.820E-3 1.270E-2' l.918E-1

~7/3/81 1320 45%

't.323E-1 8.906E-2 8.660E-2 1.999E-2 1.137E-2 1.580E-l i-7/3/81 1616 48%

4.627E-2 9.'r55E-3 3.705E-2 1.965E-2 8.149E-3

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