ML19308D343

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
Issue date:	07/15/1977
From:	Stewart W FLORIDA POWER CORP.
To:
Shared Package
ML19308D340	List: ML19308D339 ML19308D343
References
NUDOCS 8002270799
Download: ML19308D343 (2)

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1 6 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 EVENT CATE REPChT OATE CATECORY T N SC[H$E 00Cxt? NUMBEA -

E CCNT I l l it ! It I lo is lo I-lo I, lo h i Iof6l2l41717I74 lo 17 11 is 17 17 75 7 8 57 58 59 60 61 68 69 i.

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

7 89 o l it was discovered that the time frequency for sampling RCS activity was exceeded bv 7 8G -

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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 7 89 L 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)

L 7 89 pauf M 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 7 89 L o l prescribed by surveillance procedure SP-709. Follow-up report F.U.R.77-174 was E

, [ A]8 9l posted to insure compliance with SP-709 by Chem / Rad personnel.

/ FACUTY METHOO CF STATUS  % POWEA oTHER STATUS CrSCOVERY DISCOVERY CESCAIPTCN 11 lG l l0l0l0l l ' NA l 44 l.Cl 45

~l 46 NA 5

78 9 10 12 13 A E of AMOUNT OF ACTMTV LOCATCN OF RELEASE 12 lZ l lZlELIASE l NA l l NA 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 1 l01010 l l MA i

7 89 11 12 OFFSITE CONSEGUENCES l NA -

3 l ]

7 89 0 LOSS OR DAMAGE TO FACluTY j TYPE CESCRPTON . l 1

7 89 dl 10 NA L l

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PUBUCITY  !

i 1 l See attached Supplementarv Information i-7 89 t ADDITIONAL FACTOAS 8002270 7 77 t-7 89 A

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W. P. Stewart (( ' PHONE: (813) 866-4159

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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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