05000366/LER-1981-061-03, /03L-0:on 810624,hi-lo Flow Alarm Received for Reactor Bldg Vent Radiation Monitor Sys.Caused by Tripping of Sample Pumps a & B Due to Overload Protection Tripping. Vanes in Pump a Replaced.Pump B Overload Reset

From kanterella
(Redirected from ML20009F703)
Jump to navigation Jump to search
/03L-0:on 810624,hi-lo Flow Alarm Received for Reactor Bldg Vent Radiation Monitor Sys.Caused by Tripping of Sample Pumps a & B Due to Overload Protection Tripping. Vanes in Pump a Replaced.Pump B Overload Reset
ML20009F703
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/21/1981
From: Rogers W
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009F685 List:
References
LER-81-061-03L-01, LER-81-61-3L-1, NUDOCS 8107310424
Download: ML20009F703 (2)


LER-1981-061, /03L-0:on 810624,hi-lo Flow Alarm Received for Reactor Bldg Vent Radiation Monitor Sys.Caused by Tripping of Sample Pumps a & B Due to Overload Protection Tripping. Vanes in Pump a Replaced.Pump B Overload Reset
Event date:
Report date:
3661981061R03 - NRC Website

text

NRC FOI M YS (7 77) e LICENSEE EVENT REPORT CO*JTROL BLOCK: l l

l l

l l \\h (PLEASE P%3NT OR TYPE ALL REQUIRED INFORMATION) i 6

jo l1l l G lA l E j IlH i 2l@l O l 0 l -10 l 0 l 0 l 0 { 0 l -l0 l 0 ]@l 4 l 1l l li l 1l@l l

l@

7 8 9 LICE c EE CODE 14 15 LICENSE NUMSEH 26 26 LICENSE TYPE JO

$1 CAT 58 CON'T loIiI

"' ORC [lL f@lOl5lOl0l0l3I6I6l@l0l6I2l4IA I 1 l@l 0 l 7 l 2 l 1 I 8 l 1 l@

7 8

60 61 DOCKET NUV8ER 68 69 EVENT DATE 74 75 REPORT DATE 60 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo12IlDuring norm?1 operations at 2239 MWT, a Hi-Lo Flow Alarm for the Unit I

l o t a l ! 2 Reactor Buildinc Vent Radiation Monitor System occurred.

An investi-l 10141 l aation revealed that both " A" and "B"

samole cumos had tripoed.

1 IoIslIcausing a loss of flow to the monitoring systems.

This loss of mon-I l o Is l l itors violates 8nvironmental Tech Specs ~ oarc.

2.1.4.b.

There were no I

LoE l ef fects uoon oublic health and safety due_to this event.

This is a l

10181Irepetitive event and was reported last on LER 50-321/1980-097.

l 80 SYSTE M

CAUSE

CAUSE COYP.

VALVE CODE CODE SUSCODE COMPONENT CODE SU8 CODE SUBCODE lO191 IM ICl @ l El@ lB l@ IP IUl MlPlX l X lh l H l@ l Zl @

7 8

9 10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION

,_ EVENT YE AR REPORT NO.

COGE.

TYPE NO.

@ yu'E R ROl 811 l l-l 10 16 lj l/l 10 l 3 l lLl

[--j l0l L

aNEM

,,,,, 21 22 23 24 26 27 28 29 30 31 32 TAKEN AC ON ON PL NT MET HOURS SB IT FO b 8.

SU PLIE MAN FACTURER l A l@lZ l@

l Z l@

lZ l@

l 010 l 0 l 0l l Yl@

lY l@

l Al@

IVll-l1l5!@

33 34 35 36 37 40 41 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h l i l o l IThe overload protection for the sample pumps were found to be tripped.

I li li l I Unon resettino of the overload. oump "B" was returned to service within i li171130 minutes of the trio to comolv with Tech Soecs.

The vanes in cumo l

l1 13Il"A" were found to be broken, were reolaced, and the cumo returned to l

I I i l 41 I service.

80 7

8 3

$A S

% POWER OTHER STATUS dis O RY DISCOVERY DESCRIPTION li l 5 l l E l@ l 0 l 9l 2 l@l N/A l

l A l@l Operator Observation l

ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT CF ACTIVITY LOCATION OF RELEASE li l61 W @ W@l N/A l

l N/A l

7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

l ii171lol0!Ol@lZl@l N/A 2

PERSONNe't iN;u' RIES DESCRIPTION @ /A NUveE R N

l it l x l l O l 0l 0 l@l 80 7

8 9 11 12 LOSS OF OR D AYAGE TO FACILITY TYPE

DESCRIPTION

l I i I 91 [2]@l N/A 80 7

d 9 to NRC USE ONLY 8107310424 810721 [T[Tl ISSUE @l DESCRIPTION N/A PDR ADOCK 050003gR j

ll llllllll lllj 6

S P

38 6,

so. ;;;

i a 9 iO W.

H.

Rocers.

H.

p.

A n p +-

NONE. 912 / M 7-7 9 91 E

NAME OF PREPARER

LER No:

50-366/1981-061 License:

Georgia Power Company Facility Name:

Edwin I.

Hatch Decket No:

50-366

Narrative

Report for LER 50-365/1981-061 During normal operations at 2239 MWT, a Hi-Lo Flow Alarm cor the Unit 2

Reactor Building Vent Radiation Monitor System occurred.

An investigation revealed that both "A"

and "B"

sample pumps had tripped, causing a loss of flow to the monitoring systems.

This loss of monitors violates Environmental Tech Specs para.

2.1.4 b.

There were no effects upon public health and safety due to this event.

This is a

repetitive event and was reported last on LER 50-321/1980-097.

The overload protection for the sample pumps were found to be tripped.

Upon resetting of the overload, pump "B"

was returned to service within 30 minutes of the trip tc comply with Tech Specs.

The vanes in pump "A"

were found to be broken, were replaced, and the pump returned to service.

e d

4