05000302/LER-1979-020-03, /03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins

/03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins

ML19263D356
Person / Time
Site:	Crystal River
Issue date:	03/16/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19263D351	List: 05000302/LER-1979-020, Forwards LER 79-020/03L-0 05000302/LER-1979-020-03, /03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins
References
LER-79-020-03L, LER-79-20-3L, NUDOCS 7903270490
Download: ML19263D356 (14)

LER-1979-020, /03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins

Event date:
Report date:
3021979020R03 - NRC Website

text

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I U. S. NUCLEAR RECULATORY COM9 TIS $10N NRC PORM 364 EXHIBIT A (7 77)

LICENSEE EVENT REPORT

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI

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EVENT DESCm*nON ANO *RCS A8LE CONSEQUENCES h it 2020, following a reactor trip, Chem / Rad sampling revealed that the 1

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contrarv to Technical Specification 3.4.8.

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l Coolant System Purification reduced DEI-131 to acceptable levels.

o g i edundancy N/A.

The DEI-131 was.8771 microcuries per cram at 0205 on I

R 2 March 1979. This is the eleventh occurrence reported under thfs I

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SUPPLEMENTARY INFORMATION Report No.:

50-302/79-020/03L-0 Facility:

Crystal River Unit #3 Report Date:

16 March 1979 Occurrence Date:

28 Febru 1979 Identification of Occurrence:

The Dose Equivalent I-131 was greater than 1.0 microcuries per gram of primary coolant contrary to Technical Specifi-cation 3.4.8.

Conditions Prior to Occurrence:

Mode 3 Operation (Hot Standby)

Description of Occurrence:

At 2020, following a reactor trip, Chem / Rad sampling revealed that the Dose Equivalent I-131 exceeded 1.0 microcuries per gram of primary coolant. Dose Equivalent I-131 was 1.915 microcuries per gram. Action statement of 3.4.8 was entered and the four hour sampling frequency was initiated.

The Dose Equivalent I-131 returned to within acceptable limits at 0205 on 2 March 1979.

Designation of Apparent Cause:

This event was due to an expect,ed transient spike following a reactor trip and known leaking fuel pins.

Analysis of Occurrence:

There was no safety hazard to the plant or general public as sampling demonstrated reducing levels of DEI-131.

The transient was within the capabilities of the plant purification system.

Corrective Action

No corrective action deemed necessary as reactor coolant purification returned the DEI-131 to within acceptable limits.

Failure Data:

This is the eleventh occurrence reported under this Technical Specification.

Reactor Power History of Prior Forty-eight Hours

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Ites 1 Event Date: 28 February 1979 i

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2-18779,.Y L'

HOUR GMWE TURB G MUTH M

Rr)TIO PAT)D

[

g 1

(E710)

(T856)

(P753)

(P723)

NI/MT ME/MT W

f. en 2nup

, /,s e r-

/,en

, /,, r n

,. e, r -

m 1

97.04 9906 98.41 99.40 1.010

.956 g

1 2

97.02 9908 98.41 99.30 1.009

.986 cf nnin

~, i ; 1 on 7n i nno eng 6;

7 o-1 4

97.01 9908 98.41 99.20 1.008

.986 1

5 96.97 9915 98.45 99.20 1.008

.985 ci A

c4 o-cosu og u7 oo 7o

nao e g r-3 7

97.02 9912 98.45 99.50 1.011

.985

.li 8

97.10 9907 98.49 99.50 1.010

.986 1:

o 9_?_,02 on!2 o? ' r oo 7n

! 000 o g '-

(P 10 97.02 9942 98.78 99.40 1.006

.982 C'l 11 96.98 9964 98.94 99.60 1.007

.980 h s' a

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13 96.49 10045 99.27 100.2t' 1.009

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14 96.37 10_057 99.27 100.10 1.008

.971 ha.

o.,77 199 7 00,74 3 ggg ego

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(" 'E 16 96.35 10060 99.27 100.30 1.008

.971 3

17 96.32 10060 99.23 100.00 1.008

.971 20 so er ne 4nnmo no ce i. n 4 nno e,r E

19 96.28 10024 o8.82 99.90 1.011

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13 20 96.30 10019 98.02 100.20

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24 e.

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E 22 96.32 10019 98.82 100.30 3.015

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'3 96.27 10027 98.86 100.00 1.012 974 C W 6-1""'"

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29 ae ar p4 i!.0 AVERAGE DAILY GENERATOR GROS 5 826.26 MUH'E'

1 AVERAGE DAILY THERMAL POWER 2423.92 MUH(T)

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.i AVERAGE DAILY MWTH POWER 9E 773 e / c P' l'

AVERAGE DAILY NUCLEAR INST. FOWER o9 725 =/aFF RATIO OF NI TO MUTH = 1.010 it.

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• DATE 2,27 79.

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HOUR GMWE TURB G MWTH NI RATIO RATID

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NI/MT ME/MT

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96.29 10021 98.82 99.90 1.011 974 5'

96.34 10016 98.82 99.90 1.011

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5 96.30 10018 98.78 99.90 1.011

.975 4nn4o og g

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7 96.37 10014 98.82 99.70 1.009

.975

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96.23 10027 98.82 99.70 1.009

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S 10 96.70 10017 99.18 100.30 1.011

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13 96.67 10021 99.18 100.20 1.010

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AVERAGE DAILY GENERATOR GROSS 798.75 MWH(E) i 2.E AVERAGE DAILY THERMAL POWER 2423.58 MWH(T)

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AVERAGE DAILY MWTH POWER 92.84:

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AVERAGE DAILY NUCLEAR INST. POWER 100.054 e/ FP E..

RATIO OF NI TO MWTH = 1.012 n

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19 0.00 0

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22 0.00 0

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AVERAGE DAILY MWTH POWEP 69.852 e/aCo 21 AVERAGE DAILY UUCLEAR INST. POUER 60. 'l % e/aCo n

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RATIO OF MI TO MUTH = 1.009 y

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Fuel Burnup by Core Region Item 2 Event Dace:

28 February 1979

Item 2 The burnup was calculated at 406.6 EFPD for the four (4) enrichment regions.

REGION NUMBER of FA BURNUP A

52 13,302 MWD /MTU B

60 14,136 MWD /MTU C

61 9,303 MWD /MTP Oconee 4

14,000 MWD /MTU Ave.

12,222 MWD /MTU

8 Clean-up Flow History Item 3 Event Date:

28 February 1979 e

=w

Item 3 Clean-up flow history starting forty-eight (48) hours prior to the first sample in which the limit was exceeded is as follows:

DATE TIME LET DOWN FLOW 2/26/79 0030 47 GPM 2/27/79 0105 47 GPM 2/28/79 0120 47 GPM

History of Degassing Operations For This Report Item 4 Event Date: 28 February 1979 I

se > w e

DEGAS OPERATIONS DATE TABLE TIME 2/27/79 Degassed MUT to WGDT 1345 2/28/79 Degassed Pressurizer 1516 2/28/79 Reactor Trip 1639

Time Duration When DEI-131 Exceeded 1.0 p C1/ gram and I-131 Analysis Results Item 5 Event Date:

28 February 1979 e

,s Item 5 As per Technical Specification 3.4.8 The four (4) hour sampling frequency was initiated at 1820 on 28 February 1979 and the Dose Equivalent I-131 was 1.915 microcuries per gram. The four (4) hour sampling frequency was terminated at 0600, 2 March 1979 when the DEI-131 was determined to be.6732 microcuries per gram. DEI-131 was < 1 u Ci/ gram at 0205, 2 March 1979 when the sample results were.8771 u Ci/ gram.