05000302/LER-1981-050-03, /03L-0:on 810731,primary Coolant Dose Equivalent I-131 Discovered Exceeding Tech Spec Limit.Caused by Leaking Fuel or Tramp U & Dose Equivalent Iodine Transient Following RCS Transient.Rcs Purification Flow Increased

/03L-0:on 810731,primary Coolant Dose Equivalent I-131 Discovered Exceeding Tech Spec Limit.Caused by Leaking Fuel or Tramp U & Dose Equivalent Iodine Transient Following RCS Transient.Rcs Purification Flow Increased

ML20010E799
Person / Time
Site:	Crystal River
Issue date:	08/27/1981
From:	Hernandez V FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010E796	List: 05000302/LER-1981-050, Forwards LER 81-050/03L-0 05000302/LER-1981-050-03, /03L-0:on 810731,primary Coolant Dose Equivalent I-131 Discovered Exceeding Tech Spec Limit.Caused by Leaking Fuel or Tramp U & Dose Equivalent Iodine Transient Following RCS Transient.Rcs Purification Flow Increased
References
LER-81-050-03L, LER-81-50-3L, NUDOCS 8109080269
Download: ML20010E799 (14)

LER-1981-050, /03L-0:on 810731,primary Coolant Dose Equivalent I-131 Discovered Exceeding Tech Spec Limit.Caused by Leaking Fuel or Tramp U & Dose Equivalent Iodine Transient Following RCS Transient.Rcs Purification Flow Increased

Event date:
Report date:
3021981050R03 - NRC Website

text

(7 171 LICENSEE EVENT REPORT CONTROL BLOCN l )

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e 60 61 DOCir ET NUMBE R 68 69 EVENT DATE 74 75 REPORT DATE B0 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Oto y t 0945 on 7/31/81 during Reactor Coolant sampling, it was discovered that prir'ary I

A coolant Dose Equivalent I-131 exceeded the linit of T.S.

3.4.8.

Redundancy NA.

There l

was no effect upon the health or safety of the general public. This is the twenty-l

g,,,

g fourth event reporte. under this Specification, g

I 10161l l

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l o l8 l l 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SU8 CODE COVPONENT CODE SUBCOOE SUBCODE l0l9l l Z l Z lh lZ lZ lh lZ lZ lZ lZ lZ lZ l l Z lh [Z] @

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9 TO 11 12 13 18 19 20 SEOUE NTI AL OCCtJR RE NCE REPORT REVISION

_ EVENT YE AR REPORT NO.

CCDE TYPE N O.

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33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l 0 l l The cause of the event is attributed to leaking fuel or " tramp uraniun" (i. e., uraniur,l

,,,,; [n the cladding within one recoil radius of the surface) and an anticir>ated Dom ran i m -l fentIodinetransientfollowingaLeactorCoolantSystentransient. RCS purification l

l1 l3i flwwasincreased; Doce Equivalent I-131 was less than 1.0 raicrocuries per gran at l

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y, 80 7

8 9 STA S

% POWE R OTHER STATUS ISCO RY D:SCOVERY DESCRIPTION NA l

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8 9 to 11 PERSONNEL E xFOSLRES NUVBE R TYPE

DESCRIPTION

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8 9 11 12 LOSS OF OR Dr.'/ AGE TO F ACILITY TYPE

DESCRIPTION

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NRC USE ONLY 8109080269 810827

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NA*.tE OF PREPARER OMTMfqHED SUPPLDIENTARY CNFORMATION SHEET)

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REACTOR POWER HISTORY OF PRIOR FORTY-EIGHT HOURS ITIN I LVINT DATE:

July 31, 1981

SUPPIDENTARY INFORMATION Repe-t#50-302/81-050/03I,-0 Facility: Crystal River Unit 3 Report Dat August 27, 1981 Occurrence Date:

July 31,1981 Identification of Occurrence:

Primary Coolant Dose Equivalent I-131 was greater than 1.0 microcuries per gram contrary to Technical Specificatien i

3 4.8.

i Conditions Prior to Occurrence:

Mode 3 - (Hot Shutdown 04)

Description of Occurrence:

At 0945 on July 31, 1981 after a Reactor trip, li; was disyvered that Dose Equivalent I-1 31 exceeded 1.0 mic. euries per gram.

Designation of Apparent Cause:

The cause of this event is attributed to leaking fuel or

" tramp uranium" (i.e., uranium in the cladding within one recoil radius of the surface) and an anticipated Dose Equivalent Iodine transient following a Reactor Coolant System transient.

Analysis of Occurrence:

There was no effect upon the health of safety of the general public.

Corrective Action

The Reactor Coolant System flowrate through the Makeup and Purification System 'tas increased.

Dose Equivalent I-131 i

was determined to be less than 1.0 microcuries per gram a' 0100 on August 1, 1981.

FPC Nuclear Support Servicee is also conducting an evaluation to determine if failed 1% 1 is present.

Failure Ihta:

This is the twenty-fourth event reported under this Specification.

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cm i10l (3

h2 DATE 7r29r81 k. Ll m

M

is!.

( % HOUR GMWE TURB G MWTH NI RATIO RATIO u,. g,J^+,"u f

(E710)

(T856)

(P753)

(P723)

NI/MT ME/MT m'

~,

=/aFP BTU /KWH aJaFP n/aFP

- AFP a/*FP

( %'

1 96.71 105tti 99.51 99.80 1.003

-.972

.r*

3 2'

96.70 10545 99.51 99.90 1.004

.972.

T- ' 'D L2E-3 96,65 10552 99,55 - -99,90 1,004 w971 Mi E ( h22' e

Lt 96.73 10569 99.51 99.90

1. 0 0 tt

.972 a

'i M

5 96.91 10529 99.31 99.70

1. 0 0 Lt

.976

~

4 6

97-. f4 4 10L&88

99. 8tt ---10 0 10 1, S t)3

.976

.h;p;%

l k. f 7

97.33 110391 99.88 100.20 1.003

.975

.. JJ B

97.844 10238 99.92 100,10 1.002

.975 3

I,-

! (

9 97.45 - - 10247 100.04 - 100,10 1,-001

.974

~

,5

.l] E {' d 10 97.32 1026tt 100.0tt 109.10 1.001

.973 4

11 97.11 10271 99.88 100.20 1.003

.972

!34 12 9.7.1.1 10266 99,8tt 1.00.20 1.0 0l+.

.973

(' [

3 13 97.09 10273

. 99.88 100.20 1.003

.972

/'

14 97.09 10255 100.00 100.20 1.002

.971 33

- 15 97,15 10237 - 99.92 100r10 1-i O O 2

.972 T[. s 16 97.10 102f47 99.92 100.10 1.002

.972

,..gI 17 97.11 10239 99.92 100.20 1.003

.972

'4 '

18 96.12 10249 98.98 99.30 1-003

.971 19

- 9 6.169

- 10252 99.39 99.70 1.003-

.971 b,37}

13 8 I 20-96.71

~10277 99.59 100.00 1.004

.971

~

N 21 96,82-10261 99,71 100.00.003 - _.971 d

22 96.94 10368 99.67 99.90 1.002

.973 b

23

96. 9 tt 105tt5 99.67 99.90 1.002

.973 d21 94 9L 87 10536 99 63 99 80 1.009

.979

!n

(,' M -

M

(~ d AVERAGE DAILY GENERATOR GROSS 829.11 MWH(E)

Ld7j AVERAGE DAILY THERMAL POWER 24t+LF. 96 MWH( T)

~44>se

1. VERAGE DAILY _ TURBINE _ GROSS _ HEAT _ RATE 10360_ BTU /KWH

'4? AVERAGE DAILY MWTH POWER 99.713 */aFP C 5 AVERAGE DAILY NUCLEAR INST. POWER 99.983 a/*FP

.sn (b

i RAT IO OF NI TO MWTH = 1. 0 02

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(., f

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n

.n.

.n. b DATE 7,30,81

.4

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+

(

( b 0UR GMWE

'T. URB._G MWilH_

NI RATIO RATIO 4!

(E710)

(T856)

(P753)

(P723)

NI/MT ME/MT 6['

a/aFP BTU /KWH

• /aFP

• /aFP

• /=FP a/*FP M

1 96,_77 10450 9L59 99 a0 1A03

.9.72 W

2 96.84 10053 99.59 99.80 1.002

.972 6 ' 5j 3

.96.90-10050 99.63 99.80 1.002

.973

..a s s

m

't.

96.82,.

10056 ___93.67

_91.90 1.002.

d71 d

5

.96.91 10048 99.67 100.20 1.005

.972 6y 6

96.02 10056 99.63 100,10 1.005'

.972 7

9L 30 10.025 9 1 8.0 100J0 1 003

.915 [13j 8

97.36-10028 99.88 100.20 1.003

.975 63 9

97.44 10027 100.00 100.40 1.004'

.974 i' 5' - 1 0____.S.L J+ 2 10031 100.04 100.8+0 1.0_0 l+

974 v..gw.2 Ufj 11 97.37 10036 100.08 100.60 1.005

.973

'y Y ~,

6 M' 12 97.47 10025 100.00 100.60 1.006

.975 JS 13 9.L.33__10 0 34 99_.S2 100.10 1.S05

.374 E

14 97.29 10033 99. 81+

100.30 1.005

.974.'

r,.

.-. i - ?: J > 6d 15-97.25 10038 99.88 100.30'

1. 0 0 l+

. 9 7 8+ -

• i

?! _16 9.7. 22

__1.0043 99_.S2 10ft. 30

'li.0.0 t+ -

a73 a

ifl?q'.

22j 17 97.27 10042 99.96 100.40 1.004

.973 c

3 18 97.26 10 0 l+ 6 99.96 100.t+0

1. 0 0 L:

.973

. :1 -

U;d

!24 19 9.7.25 10048 100.00

$00.30 1 0.0 3

.913

.!$? j G9' E 20 97.24 10 0l+7 -

99.96 100.40

1. 0 0 t+

.973 f f;Js ? j ' C. M

'2si -

21 97.29 100t14 100.00 100.30 1.003

.973

/7 0.! A b

22___S7.26_ __10043_._ _31.36 1.0 f. 3 0 1_.003 973

.br#:;;l J+9 5 I8I 23 97.27 10037 99.92 100.40 1.005

. 9 78+

' [' i f 24 97.23 10033 99.80 100.30 1.005

.974 L..

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2 23 _ AVE R A GE._II A I LY._ GEN E R A T0 fLG R O S S 83D.98_MWH(E.)

2 tit +8. 62 MWH(T) f Q~". h ~.,

k. &

AVERAGE DAILY THERMAL POWER l35. AVERAGE DAILY TURBINE GROSS HEAT RATE 10041 BTU /KWH

~

hVERAGE_ DAILY _MWTH_E0WER 91B62_.a/ EP 2

'J1) AVERAGE DAILY NUCLEAR INST. POWER

.100.254 a/*FP

_ Q- :~, n.

f.

$ RATIO OF NI TO MWTH = 1.00l+

NNp

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l 6$

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-j'.:.r. sy DATE 7,31,81 g

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V a

'- HOUR GMWE.

TURD.G MWTH-NI - _ RATIO RATIO

.1 (E710)

(T856)

(P753)

(P723)

NI/NT ME/MT l%

• /aFP BTU /KWH

• /aFP

• /=FP

• /=FP a/*FP d!

1 97.23 10018 99.63._._100.10_ _ 1.005

.9.76 I

W

- 2 97.29 10011 99.63 99.90

.1.003-

.976-i UU 3

97.22 10021 99.67 99.80 1.001

.975 e

O' 4

97.27-..-

10020.

9.9..71 _ 99.90 1.002-9.76 5

97.26 10022 99.84 100.10 1.003

.974 l %'E 6

97.26 10021

99. 8tF 100,10 1.003

.974 7

97.24 10027 994.88 100.10 1.002 9.74 4

.M 8

51.36

'O 5LF.16 53.40

.986

. 9L)8 Lh 9

0.00 0

.37 0.00 0.000 0.000 l' F 10 0-.00 0

7.7 -

0 00 D..iOOO.

0.000:

' Y. b'.-

'E 11 0.00 0

.98 0.00 0.000 0.000

% 7!

7 12 0.00 0

1.1 LF 0.00 0.000 0.000 5' ' -;.

13 0.00 0

2:73 04 00 0.000 0.000 d

14 0.00 0

4.73 0.00 0'000 0.000 A

p?2 -

l$

15 0.00 0

7.75.

0.00 0.000 0.000

?h 1-6 0.00 0

8.69 0.-00

'0,000 0,.0 0 0

{-M 17 0.00 0

9.54 0.00 0.000 0.000 [N- [kh 18 1.46 30723 11.13 15.70 1.410

.131 l!

19 25.57 1-2836 31.r24 39r00 1r248

.818 i

?

,l$3[;NiN.

M 3

,5~ l h'25i 20 32.11-11tF27-35. 2 LF -

43.20 1.226

.911

Wh 21 LF 6.~ 8 0 10830 50.33 58.40 1,160

.930'

~9

' ' (d. d 5 I (

'22 67.53 10258 70..11 76 90 14097 i963 I

% M; E

=

23 71.01 10557 76.10 81.00 1.064

.933

~

2tt 8tF.07 10113 86.83 89.80

1. 03tt

.968 JL

.rs

., 3g s

l. 2 f._ AVER AGE _ DA ILY.ISENE R ATO R_ G ROSS - 377 86 MWH(E) 9 AVERAGE DAILY THERMAL POWER 117tt.96 MWH(T) b !35l AVERAGE DAILY TURBINE GROSS HEAT RATE 6954 BTU /KWH kAVERAGE_ DAILY-MWTH_ POWER

• diJ d l

4.7.918 a/>EP b7: AVERAGE DAILY NUCLEAR INST. POWER 48.225 a/*FP

( n wm-n.,:

. !+$ RATIO OF NI TO MWTH = 1.006

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2.

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FUEL BURNUP BY CORE REGION ITB4 2 EVHiT DATE:

July 31,1981

ITH4 2 THE BUMP WAS CAICUIATED AT 265 9 EPPD FOR THE TIEEE (3) HEICIMNT REGIONS.

BATCH NUMBER OF FA BURNUP (MWD /MTU)

B 9

25,552 C

60 23,589 D

52 13,745 E

56 6,891 AV.15,514 MWD /MTU

CLEANUP FLOW HISTORY ITH4 3 EVHTT DATE:

July 31, 1981

ITIM 3 CLEANUP FLOW HISTORY FORTY-EIGHT (48) HOUBS PRIOR TO THE FIRST SAMPLE IN WHICH THE LIMIT WAS ET.CEEDED INDICATED A LETDOWN FIOWRATE OF R)R1T-FIVE (45) GPM.

NEITHER MEGJP AND PURIFICATIN DIMINERALIZER WAS IN SIRVICE DUE TO A IOSS'0F ACCURATE PRIMARY SYSTIM ph C0h'IROL.

9L DIMIN FIOWRATE 7/29/81 "A"

47 7/30/81 0

DEAS OPERATION ITH4 4 EVBIT DATE:

July 31,1981

i ITD4 4 DEASSING OPH1ATIONS PRIOR TO EXCEDING LIMIT (7/29/81 at 1115 through 7/31/81 at 1115) 7/30 0255 Started pressurizer spray 0618 Stopped pressurizer spray 7/31 0435 started pressurizer spray 0630 Stopped pressurizer spray

z a

TIME DURATION WHEN DEI-131 EXCEEDED 1.0 u Ci/ gram and I-131 ANALYSIS RIEULTS ITD4 5 EHNT DATE:

July 31, 1981 l

l

a ITm 5 AS PER TECHNICAL SPECIFICATION 3 4.8, the FOUR (4) HOUR SAMPLING FRMUINCY AS DEPICTED m THE TABLE BELCV WAS INITIATED AT 0945 AND THE DOBE MUIVALINT I-131 WAS 138 MICR0CDRIIB PIR GRAM.

THE FOUR HOUR SAMPLING FREUINCY WAS TIEMINATED AT 8 /1 /81 0100 hrs.

WHEN THE DEI-131 WAS DETERMINED TO BE 0.648 MICROCURIIB PIR GRAM.

THE TIME DURATIN WHIN THE SPECIFIC ACTIVITY OF PRIMARY COOLANT EKCEEDED 1.0 MICROCURIIB PIR GRAM DTE MUIVAINT IS:

15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, 15 minutes DATE TIME DEI-131 (uCi GRAM) 7 1

0945 1 38 7

1 1300 1 54 7

1 1700 1 59 7

1 2105 1.19 8

81 0100 6.48E-1 l

l

_ _ ~. _ _ _.., _, _. _.