ML19340C153

From kanterella
Jump to navigation Jump to search
LER 80-045/01T-0:on 801028,purge Isolation Valves AHV-1A & 1B Were Inoperable.Caused by Radiation Monitor RM-A1 Not Representatively Sampling Reactor Bldg Atmosphere Due to Maint Actions Involving Detector Removal/Replacement
ML19340C153
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/07/1980
From: Lamaster K
FLORIDA POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340C148 List:
References
LER-80-045-01T, LER-80-45-1T, NUDOCS 8011140050
Download: ML19340C153 (2)


Text

r ~

Q 171 u. s. Suc,.22a a ccut.aren ::wir.s.cs

' LICENSEE EVENT RE? CAT EXHISIT A contac:. st.:cc l I I I I I l v..rAss amsi ca rvse at:. azcuimsc imaenua- cm i

l3 iil.l .? I Li C R\ ?! 3 l@-l 0101- l 0 ; 0[

meas u :::. .. >

0lOO mcam ,-...

J J gG Ogga a 4j 1,I l ;1;glg

._:, m :... .a ig o a. u

e loeii l5 cfge4l L g! 0 r 5t::c ei o Iar-rw osaai 3 f o w12 gi sa l i o r 21818 t o gl 1; ir01718 ! 0 l@

s s~r :*ri  :. s =4 :=r ms u avsur:sscaiatics 2.so *acsast.4 c:ssacutNess Ot:

,,,,,[ At 2325 on 10/28/80 and again at 2123 on 10/29/80 it was discovered that purge

. 73,3, g isolation' valves AHV-1A and 1B were inoperable, contrary to T.S. 3.6.3.1. Event 9

g( durations were approximately 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> respectively. For each eventj i 3 i s ! t_ the R. B. purge was terminated at the time of discovery. The inoperability was due t o is i I to radiation monitor RM-Al providing a less than conservative value of radiogas t

[: iri l in the exhaust duct. There was no effect upon the health or safety of the general t public. These are the first and second events of this type. This is the twenty-to.sii seventh report under this Specification. t sv1?1st cal.s E sa CALIE . c ve va gy g COct C;;E Sb5C::t  : uscggs* ::( gt.3 : g gggq: g 1 : , aj

[ St Dl@ lD l@ y@ [I i2I N l S i Tl Ri Ul@ IE l@ y @

. ia i. ,2 2. ,, a sacu t w rta t C ggag%:2 as. e; sist as t a a0 (VENT

  • tam 218Caf NC.  :::t vet s;

@ *a(i *"*m r1810ul l-. l [ Oi4 l 5 l l/l 1011 l l Tl l __1 l 0l

_v u x. u :1 a n u t---

u TN "Sc"4 c!#25r 57.WE' cu.. n= 'r?.^5,5 ! ? .c'J 3 ', ' ;"' M > .E,?a'i, .

I,>x !gl. x l@ I z l@ p_J@ I 01010 Nii I vi@ lNig lAl@

causa cascaiarics 280 ::amscnvs ac icss 27

- >, .a .. ., .a l Tl31010l( .,

1i,al[ The cause of t'his event was RM-Al not representative 1v sampling the R. B. atmos-

,,,,,g phere due to maintenance actions involving detector removal / replacement. This wast 7, , . I i augmented in the second event by a valve misalignment. Purge isolation valves isq-

,,,,, g lated at 0018 on 10/30/80. Procedures have been revised to improve control of g maintenance and testing activities. Personnel have been retrained in SIS require-t..;t ments, control of maintenance and the requirement for procedures "in hand" duringi s, g stem manipulation. , , , **

svarus s os= cv.t stares b_  :,,is::v am-

sc:vtav :ssc=

es @

li ! 5 I W@ l0 I 9 I 6 l@l NA l

lBl@l Technician observation  !

' .Enurv CEdtst '* * '*

aassase tecarios c ei 342 h y l Z l @s es astrastil/pl F 5 9 la t av:vwreea:turv NA as h [l.S NA I

ei scssas iveau.t cs go v u. r e,  ::::.. ve, . .

li t ri 10 10;O!@[zj@[ NA l

age:C%stL sN6afigs "

wevgge :ssco'mCs letel[0)0101@l F # 8  :: 1:

NA I

  • 053 Ce C# 3ava:t '3 8 A::ut* 3a r* 1 :ss:sia*'C4 22 D. f 0 -

'b.

i s i a. l,l Z !@l,.

NA [  ;@ q. 80 .L !)U]l l

- wua "b8b'M e erg t e St$:8 mC%

  • NACt.M cN(y

[: 6 c l l N l@l NA I ,IIIIIIlI'I II I

hame of Preparer:

/ ,mg g9Cl4 793-M86 (SEE ATTAE SU??LF.50CAFZ Di?OFXCICS SEZZT) ,

80'11 y a o '

. . ... T;O- - ..

r SUPPLEMENTARY INFORMATION Report No.: 50-302/80-045/01T-0 0

Facility: Crystal River Unit #3 Report Date: 7 November 1980 Occurrence Date: October 28, 1980 Identification of Occurrence:

Failure to have containment isolation valves operable contrary te Technical Specification 3.6.3.1.

Conditions Prior to Occurrence:

Mode 1 power operation (96%).

Description of Occurrence:

At 2325 on October 28, 1980 it was discovered that AHV-1A & IB had been inoperable since approximately 1345 when maintenance actions resulted in failure of radiation monitor RM-Al to provide a conserva-tive value of radiogas in the exhaust duct. The Reactor Building purge was terminated at the time of discovery and restarted at 1040 October 29, 1980. At 2323 on October 29, 1980 it was discovered that RM-Al was failing to sample the Reactor Building exhaust ,act. The Reactor Building purge was terminated and the purge isolation valves were dis-abled at 0018 on October 30, 1980.

Designation of Apparent Cause:

For October 28, 1980: Maintenance actions removed the detector for the gaseous channel from the monitor resulting in a bypass flowpath, which resulted in non-conservative radiation indications.

For October 29, 1980: Maintenance action had replaced the detector im-properly, allowing bypass flow to again affect radiation indications.

Additionally, a valve was misaligned when the monitor was placed in service, which left the monitor isolated from the sample stream.

Analysis of Occurrence: There was no effect upon the health or safety of the general public.

Corrective Action:

4 The detector was properly installed in the monitor at 2345 on October 20, 1980. Procedures have been revised so that monitor flow will be cycled to verify proper monitor operation. Detector maintenance is now procedurally controlled. Personnel have been retrained in Stand-ard Technical Specifications requirements, control of maintenance and the requirement to have procedures in hand during system manipulation.

Failure Data:

These are the first and second events of this type. This is the twenty-seventh report under this Specification. l

/rc