05000324/LER-1980-082-03, /03L-0:on 801114,Unit 2 Reactor Scrammed.During Subsequent Startup,Coolant Activity Exceeded Tech Specs. Caused by Leaking Fuel Element.Fuel Bundles Will Be Sipped During Next Refueling & Leaking Bundles Removed

/03L-0:on 801114,Unit 2 Reactor Scrammed.During Subsequent Startup,Coolant Activity Exceeded Tech Specs. Caused by Leaking Fuel Element.Fuel Bundles Will Be Sipped During Next Refueling & Leaking Bundles Removed

ML19345D862
Person / Time
Site:	Brunswick
Issue date:	12/08/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345D856	List: 05000324/LER-1980-082, Forwards LER 80-082/03L-0 05000324/LER-1980-082-03, /03L-0:on 801114,Unit 2 Reactor Scrammed.During Subsequent Startup,Coolant Activity Exceeded Tech Specs. Caused by Leaking Fuel Element.Fuel Bundles Will Be Sipped During Next Refueling & Leaking Bundles Removed
References
LER-80-082-03L, LER-80-82-3L, NUDOCS 8012170625
Download: ML19345D862 (6)

LER-1980-082, /03L-0:on 801114,Unit 2 Reactor Scrammed.During Subsequent Startup,Coolant Activity Exceeded Tech Specs. Caused by Leaking Fuel Element.Fuel Bundles Will Be Sipped During Next Refueling & Leaking Bundles Removed

Event date:
Report date:
3241980082R03 - NRC Website

text

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LICENSEE EVENT REPORT Os CONTROL BLOCK: l l

l l

l l lh (PLEASE PKINT OR TY;E ALL REOut ED~1NFORMATION) lo l i l l N l C l 3 l E l P l 2 l@[ 0 [0 *l - 10 l 0 l 0 l 0 l 0 l-l 0 l 0 l@l 4 l 1 11 11 l 1 l@l l

l@

7 8 9 UCENSEE CZE 14 15 LICENSE NL'/SER 25 26 UCENSE TvPE 40

$7 L A T 56 CON'T lolil 3[,C l L }@l 0! 5 l 0 l - l 0 l 3 l 2 l 4 @l 1 l 11114 l 810 l@l112 l o ! 8 I 810 l@

7 8

60 61 DOCK ET a.uv6ER 68 69 EVENT DATE 78 75 RE*CRT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Iol2l l On November 13, 1980, Unit No. 2 scrammed followine approximately 2 weeks I

10121 i of high power operation.

Following the scram and during the subsequent startup, 1

I o I 4j lthe coolant activity exceeded Che technical specificatu n limit of 0.2uci/gm.

I g,_

j 1oj5l l dose equivalent for 15.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> with the highest recordet tetivity at 0.42tC1/em.

I Io is I l l

Io I7I I I

I o la 11 Technical Specifications 3.4.5, 6.9.1.9b i

80 7

8 9 SYSTEM

CAUSE

CAUSE COUP.

VA LV E COCE CODE SUSCODE CovPONENT CODE SU9 CODE SUSCOOE 1o191 19 18 l@ W@ I z i@ l 21 zl 7.1 zl zi zl@ l zl@ Iz l@

7 8

9 10 11 12 13 18 19

J SEQUENTI AL OCCURRENCE REFORT REvlSION LER RO EVENT VE4R REPORT NO.

CODE TYPE N O.

@ suga' btL2J I-I IOI8i2i 1-1 10 13 I Iti l-l 10 i as

_ 21 22 23 24 26 27 28 29 30 31 22 TA N AC ON ON PL NT ET HOURS SB I POR1 8.

St PPLIE Y N ACTURER LyJ@LrJ@

Ln_l@

I z lO 10101018 I lx l@

IV l@

Iz l@

I z 19 19 19 l@

33 34 35 36 37 40 43 42 43 4.4 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 11 101 l T1,o high ~nin-e nceiv4*v ene n atence vaenir nf *ha rane*ne cern,virh n svikenen one I

1. "o1 I

I1 iiil4,r-one.

<n cnninne c4ce4nn nenance i nvan e n m nvi g4 nn H ng F--

n l a s t-47 l i i 21 l eierent.

Reactor never was held to <25% until the iodine activity return to l

i i 13 I I within soecifications.

The Unit No. 2 fuel bundles will be sipped during the next l

I i I 4 I l refueline outace and the leakine bundles removed frora the core.

I 7

8 9 90 A 5

% POW E R OTHER STATUS 015 O RY DISCOVERY DESCRIPTION

[.,'jf.,j [Jjh l 0 l 2 l 5 lh!

NA l lAlhl Coolant Sampling l

ACTiv t TV CO TENT REtf ASEo 05 RELEASE AMOUNT OF ACTivsTY LOCATION OF RELEASE l8 16 l l' 'I h Whl NA l l

NA l

7 8 9 to I

44 45 80

' PERSONNEL EXPOSLRES NU'.*B E R TvPE

DESCRIPTION

li l 71 I ni nl nl@lz l@l NA l

,iRSONNEL ~m4 S E

ESCRiPTiON@

NuveER l1 lxllOlOlOlhl NA l

7 8 9 18 12 80 LOSS OF OR DAMAGE TO FACILtTV TYPE D ESCRIP TION I i I 9 I (,_d@l NA l

7 9 d to 80 h

( h } fjf G tSdsuE @DESCRIPT!ON l

NA l

lllllll1I!l!l,I 2 o 8 9 10 68 69 80 5 NAME OF PREPARER A. C. TOLLISON, JR.

919-457-9521

{

, PHON E:

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0FF-GAS ANALYSIS Prior to this incident, the following Unit No. 2' Steam Jet Air Ejector (SJAE) off-gas levels were measured:

Date Reactor Power, %

Off-Gas uCi/sec at SJAE 11-3-80 94.6 6.25 E 4 11-5-80 96.2 3.63 E 4 11-7-80 100.0 2.10 E 4 11-14-80*

22.0 11-21-80 82.6 1.31 E h At this ti=e a sample was drawn and counted; however, the flow rate at the SAJE could not be determined because the reactor was at low power.

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