ML19263D356

LER 79-020/03L-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

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: ML19263D350 ML19263D356
References
LER-79-020-03L, LER-79-20-3L, NUDOCS 7903270490
Download: ML19263D356 (14)

Text

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EVENT DESCm*nON ANO *RCS A8LE CONSEQUENCES h 1 o 2 itA2020, following a reactor trip, Chem / Rad sampling revealed that the

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

The DEI-131 was .8771 microcuries per cram at 0205 on I g i edundancy N/A. R g 2 March 1979. This is the eleventh occurrence reported under thfs I f

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CAuSE DESCRIPTION ANO CCARECnVE ACDONS h I g IThis event was caused by an expected stiike f o1 10w4 ~- , vn,cene e v 4 .s

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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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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 '- _ __

10 97.02 9942 98.78 99.40 1.006 .982 (PC'l 11 96.98 9964 98.94 99.60 1.007 .980 ao on n n e. e,,

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( l', 13 96.49 10045 99.27 100.2t' 1.009 .972

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'3 96.27 10027 98.86 100.00 1.012 974 7 e.a 1""'" "o " o " * " 'h' y C W 6-O!

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

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. AVERAGE DAILY THERMAL POWER 2423.92 MUH(T) n Aurn.ang ria T t y Tttpr>To- nonce p r > n a--e

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,, .i AVERAGE DAILY MWTH POWER 9E 773 e / c P' l' AVERAGE DAILY NUCLEAR INST. FOWER o9 725 =/aFF it. RATIO OF NI TO MUTH = 1.010

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

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.I._ AVERAGE DAILY MWTH POWER 92.84: >/*FP II. AVERAGE DAILY NUCLEAR INST. POWER 100.054 e/ FP E.. RATIO OF NI TO MWTH = 1.012 n

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~, 2 AVERAGE DAILY GENERATOR GROSS 572.81 MUH(E) d AVERAGE DAILY THERMAL POWEP 1698.25 MUH(T) o- - -- -,-n n->in,i.

3 irg g - p -- n y -.i - e.r o - ren-e l- 1. AVERAGE DAILY MWTH POWEP 69.852 e/aCo 21 AVERAGE DAILY UUCLEAR INST. POUER 60 . 'l % e/aCo n -

.U Ey RATIO OF MI TO MUTH = 1.009 .

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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

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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

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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.

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