ML19308D343
| ML19308D343 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 07/15/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19308D340 | List: |
| References | |
| NUDOCS 8002270799 | |
| Download: ML19308D343 (2) | |
Text
.
'0CERSGE tsE&n4EPiJm
~
I
[
CONTROL BLOCK.l l
l l
l l
l
[PLEASE PRINT ALL REQUtACD INFC".".17.T:C.
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 T N SC[H$E 00Cxt? NUMBEA EVENT CATE REPChT OATE CATECORY E CCNT I l
l it !
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
7 89 o
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
~
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)
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 L
7 89 o
l prescribed by surveillance procedure SP-709.
Follow-up report F.U.R.77-174 was
, [ A]8 9 E
l 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
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
]
3 l
NA 0
7 89 LOSS OR DAMAGE TO FACluTY j
TYPE CESCRPTON dl NA
)
1 L l 7 89 10 PUBUCITY i
1 l
See attached Supplementarv Information i-7 89 8002270 7 77 ADDITIONAL FACTOAS t
t-7 89 A
/
W. P. Stewart ((
(813) 866-4159 PHONE:
gggg; f
cPo m.ce
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.
v 4
y
---ww, v.-