ML19308D343

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RO-77-68:on 770624,reactor Coolant Letdown Not Sampled for Dose Equivalent I-131.Caused by Personnel Error.Time Frequency Info Posted
ML19308D343
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/15/1977
From: Stewart W
FLORIDA POWER CORP.
To:
Shared Package
ML19308D340 List:
References
NUDOCS 8002270799
Download: ML19308D343 (2)


Text

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[PLEASE PRINT ALL REQUtACD INFC".".17.T:C.

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LCEN3EE LCENSE EVENT NAME UCENSE NUMCER TYPE TYPE l FlL' l Cl R l P l 3 l l0 l0 l-l0 l 0 l 0 l 0 l 0 l-l 0 l 0 l l 4 l1 l1 l1 l 1l l 0l 3l 7 89 14 15 25 26 30 31 32 T N SC[H$E 00Cxt? NUMBEA EVENT CATE REPChT OATE CATECORY E CCNT I l

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It I lo is lo I-lo I, lo h i Iof6l2l41717I lo 17 11 is 17 17 7 8 57 58 59 60 61 68 69 74 75 i.

EVENT DESCRIPTION gl Following a Reactor trip and determination that D.E.I-131 was greater than lue/granr E

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l it was discovered that the time frequency for sampling RCS activity was exceeded bv 7 8G 3l l 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, contrary to Tech. Spec. action statement 3.4.8.a.

Redundancy NA.

This event

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L 7 89 hI was non-repetitive.

Immediate sampline was initiated and subsemmnt as-nli,g -ae E

7 u9 o5 l the time requi~rements of Tech. Specs.

(LER 77-68)

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A VOLATCN CE COCE CCMPONENT CODE o

IC ic I IAI lZ l Zi ZI Zi ZI ZI bHj l 7I 41 of of buj 7 89 10 11 12 17 43 44 47 48 CAUSE DESCR:PTION f

U8 l Failure of Chem / Rad technician to comply with Tech. Spec. sampling requirements as L

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l prescribed by surveillance procedure SP-709.

Follow-up report F.U.R.77-174 was

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l posted to insure compliance with SP-709 by Chem / Rad personnel.

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FACUTY METHOO CF STATUS

% POWEA oTHER STATUS CrSCOVERY DISCOVERY CESCAIPTCN 11 lG l l0l0l0l l

' NA l

l.Cl

~l NA 78 9

10 12 13 44 45 46 5

ELIASE l AMOUNT OF ACTMTV LOCATCN OF RELEASE A E of NA l

l NA lZl 12 lZ l 7 8 9

10 11 44 45 E

PERSONNEL EXPCSURES NUM BER TYPE CESCHIPTCN 8 10 I ol el L7J l

na 7 89 11 12 13 6

PERSONNEL INJUAIES NUVSER CESCRIPTON l01010 l l

MA 1

i 7 89 11 12 OFFSITE CONSEGUENCES l

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NA 0

7 89 LOSS OR DAMAGE TO FACluTY j

TYPE CESCRPTON dl NA

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1 L l 7 89 10 PUBUCITY i

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See attached Supplementarv Information i-7 89 8002270 7 77 ADDITIONAL FACTOAS t

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W. P. Stewart ((

(813) 866-4159 PHONE:

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s Supplementary Information b

1.

Report No.

50-302/77-68 2.

Facility:

Crystal River Unit #3 3.

Report Date:

15 July 1977 4.

Occurrence Date:

24 June 1977 5.

Identification of Occurrence:

Failure to sample / analyze Reactor Coolant letdown for dose equivalent I-131 at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> interval as required by Technical Specification Action Statement 3.4.8.a.

6.

Conditions prior to Occurrence:

Mode 3 hot shutdown following a Reactor trip.

7.

Description of Occurrence:

As reported in LER 77-67, following a Reactor trip, the dose equivalent I-131 was d

detemined to be greater than 1 pc/ gram. At 2000 it was discovered that the Tech Spec required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time frequency to sample / analyze the Reactor Coolant for D.E.I-131 had been exceeded by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. A sample / analysis was immediately initiated and subsequent sampling met the time frame require.1,nts of Tech Specs.

8.

Designation of Apparent Cause:

Failure of Chem / Rad technician to follow surveillance procedure SP-709 frequency of sampling requirements.

9.

Analysis of Occurrence:

There was no safety hazard to the plant or general public as samples taken indicated a decreasing I-131 activity.

10.

Corrective Action:

Chem / Rad follow-up report FUR 77-174 has been posted to insure technicians review the time frequency of SP-709.

11.

Failure Data:

This is the first occurrence of this event.

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