05000000/LER-1977-020-03, /03L:on 770404,RCS Leakage Determined to Be Greater than 10 Gpm.Caused by Packing Leakage Past Stems on RTD Bypass Throttle Valves 13RC20 & 14RC20.Valves Placed on Backseat & Stem Leakage Decreased: Difference between revisions

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=text=
=text=
{{#Wiki_filter:
{{#Wiki_filter:-
o o
+
I 1.lCENSEE EVENT REPORT conTwot stocx l l l ! I l l up,=sa sg,wr uc y o
INIJISIGl Sill 10101-10101010101-f0101 141111111l!
s i4 is a as
.m CArtComy ACE ooCMErMumeEm EVENromrt REpo A' oArt oi com T P O W LL_J 101sl 01 -10I2171 21 1014101417!71 10 4 t 0 is 1717 i e
a si se as 74 73 au EVG47 oEsenertioN Eoa IDuring Mode 1 operation. identified RCS leakane was determined to be areater ni e as o3 lthan 10 GPM. Action Statement (b) for LCO 3.4.6.2 was implemented and th>
W 7
s Eo4 junit taken out of service.
13 & 14RC20 were placed on their backseat andl f-il s se I
E lleakage was reduced to less than 3 GPM. This is the 1st occurrence of I
N 7 es lthis type.
(77-20/3L) 1 "fu n"
uanu"e E"a'an viotation "o'o'l" Tota
* comeomanyeaos 121919191 g
g 12IZl21212121 g
cause ossenterion o s'l Packing leakage past the stems on the RTD Bypass thru the valves (13 I
ie so o. l and 14RC20) caused the excess leakage.
l 7 ae a
3I I
q 7 es se
's'r'2f!E o"EUvInv' oiscoveny oescnierion
*aowsm or=se status IIIII W.
I O! 41 01 1 N/A i Ibl IRCS leak rate surveillance l
Pa 9
to iz is 44 W
as so o o!EI.a"Is amouar on activerv tocarion o,metrass i
N/A I
l N/A l
i2 Il 44 es se 7
pensonnet exposunes aumesa rves casemierion Ti 1010i0i iZi i
w/A i
"Y is se ni s n
i etRooNNEL INAW48ES NumeEn oEsCAiprioM Ti4 10iO10i i w/A i
ni s n
ia ao oppure conssousness
:- M,I N/A I
l Loss on caesaca To eAcluTY ryes osscaserion i
ig pusucirY.
1 hf /1 I"
7 8'
8312O20401 790426 acomoNab PACTons PDR ADOCK 05000263 l
R's J
(D R '.
manas:
T. L. Spencer
%,.(609)365~-7000 Ext. Salem-52:
 
?
o O
Report Number:
77-38/03L Report Date:
5/23/77
[])
Occurrence Date:
5/19/77 Facility Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Reactor Coolant System Leakage Greater Than 10 GPM CONDITIONS PRIOR TO OCCURRENCE:
operational Mode 2 4
DESCRIPTION OF OCCURRENCE:
i At 0526 hours, PRT level increased.
PRT worksheet III-1.3.5 was implemented to determine the leak rate.
The leak rats was 10.4 gpm.
Action Statement (b) for LCO 3.4.6.2 was implemented.
Leakage was determined to be coming from 1PS24 and 1PS28 stem leakoff which is piped to the PRT.
Valves 1PS24 and 1PS28 were placed on their back-seat and leakage was reduced to zero.
Action Statement (b) for LCO 3.4.6.2 was terminated at 0630-hours.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Packing leakage past the stams on 1PS24 and.lPS28 was the cause of the excess leakage.
This leakage is piped thru stem leakoff lines to the pressurizer relief tank.
t ANALYSIS OF OCCURRENCE:
l Action' Statement (b) for LCO 3.4.6.2 states that with any Reactor Coolant System leakage greater than any one of the limits, excluding pressure boundary leakage, reduce the leakage rate to within limits within four hours or be in at least Hot Standby within the next 6 hours.
The leakage was reduced to within the limits, therefore, the LCO was not violated.
At no time was there any danger to the health and safety of the general public or site personnel.
 
==CORRECTIVE ACTION==
Valves 1PS24 and 1PS28 were placed on their backseat theathe stem leak-i age was stopped.
Valves IPS24 and lPS28 will be repacked at the next l
scheduled outage.
'~
I
,~m
,.c.
 
(
o o
Report No. 77-38/03L 2-5/23/77
)
FAILURE DATA:
Not Applicable
/
/
i 7 ''/ e-n /
' '/-
e, Prepared by T.
L.
Spencer M
er - Salem Generating Station I
SORC Meeting No.
57-77 i
4 1
J
\\
l l
}}
}}


{{LER-Nav}}
{{LER-Nav}}

Latest revision as of 02:22, 26 May 2025

/03L:on 770404,RCS Leakage Determined to Be Greater than 10 Gpm.Caused by Packing Leakage Past Stems on RTD Bypass Throttle Valves 13RC20 & 14RC20.Valves Placed on Backseat & Stem Leakage Decreased
ML20086D575
Person / Time
Site: Monticello, Salem, 05000000
Issue date: 04/05/1977
From: Spencer T
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19289B550 List:
References
LER-77-020-03L, LER-77-20-3L, NUDOCS 8312020401
Download: ML20086D575 (3)
v • d • e


LER-1977-020, /03L:on 770404,RCS Leakage Determined to Be Greater than 10 Gpm.Caused by Packing Leakage Past Stems on RTD Bypass Throttle Valves 13RC20 & 14RC20.Valves Placed on Backseat & Stem Leakage Decreased
Event date:
Report date:
0001977020R03 - NRC Website
v • d • e

text

-

o o

+

I 1.lCENSEE EVENT REPORT conTwot stocx l l l ! I l l up,=sa sg,wr uc y o

INIJISIGl Sill 10101-10101010101-f0101 141111111l!

s i4 is a as

.m CArtComy ACE ooCMErMumeEm EVENromrt REpo A' oArt oi com T P O W LL_J 101sl 01 -10I2171 21 1014101417!71 10 4 t 0 is 1717 i e

a si se as 74 73 au EVG47 oEsenertioN Eoa IDuring Mode 1 operation. identified RCS leakane was determined to be areater ni e as o3 lthan 10 GPM. Action Statement (b) for LCO 3.4.6.2 was implemented and th>

W 7

s Eo4 junit taken out of service.

13 & 14RC20 were placed on their backseat andl f-il s se I

E lleakage was reduced to less than 3 GPM. This is the 1st occurrence of I

N 7 es lthis type.

(77-20/3L) 1 "fu n"

uanu"e E"a'an viotation "o'o'l" Tota

  • comeomanyeaos 121919191 g

g 12IZl21212121 g

cause ossenterion o s'l Packing leakage past the stems on the RTD Bypass thru the valves (13 I

ie so o. l and 14RC20) caused the excess leakage.

l 7 ae a

3I I

q 7 es se

's'r'2f!E o"EUvInv' oiscoveny oescnierion

  • aowsm or=se status IIIII W.

I O! 41 01 1 N/A i Ibl IRCS leak rate surveillance l

Pa 9

to iz is 44 W

as so o o!EI.a"Is amouar on activerv tocarion o,metrass i

N/A I

l N/A l

i2 Il 44 es se 7

pensonnet exposunes aumesa rves casemierion Ti 1010i0i iZi i

w/A i

"Y is se ni s n

i etRooNNEL INAW48ES NumeEn oEsCAiprioM Ti4 10iO10i i w/A i

ni s n

ia ao oppure conssousness

- M,I N/A I

l Loss on caesaca To eAcluTY ryes osscaserion i

ig pusucirY.

1 hf /1 I"

7 8'

8312O20401 790426 acomoNab PACTons PDR ADOCK 05000263 l

R's J

(D R '.

manas:

T. L. Spencer

%,.(609)365~-7000 Ext. Salem-52:

?

o O

Report Number:

77-38/03L Report Date:

5/23/77

[])

Occurrence Date:

5/19/77 Facility Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Reactor Coolant System Leakage Greater Than 10 GPM CONDITIONS PRIOR TO OCCURRENCE:

operational Mode 2 4

DESCRIPTION OF OCCURRENCE:

i At 0526 hours0.00609 days <br />0.146 hours <br />8.69709e-4 weeks <br />2.00143e-4 months <br />, PRT level increased.

PRT worksheet III-1.3.5 was implemented to determine the leak rate.

The leak rats was 10.4 gpm.

Action Statement (b) for LCO 3.4.6.2 was implemented.

Leakage was determined to be coming from 1PS24 and 1PS28 stem leakoff which is piped to the PRT.

Valves 1PS24 and 1PS28 were placed on their back-seat and leakage was reduced to zero.

Action Statement (b) for LCO 3.4.6.2 was terminated at 0630-hours.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Packing leakage past the stams on 1PS24 and.lPS28 was the cause of the excess leakage.

This leakage is piped thru stem leakoff lines to the pressurizer relief tank.

t ANALYSIS OF OCCURRENCE:

l Action' Statement (b) for LCO 3.4.6.2 states that with any Reactor Coolant System leakage greater than any one of the limits, excluding pressure boundary leakage, reduce the leakage rate to within limits within four hours or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The leakage was reduced to within the limits, therefore, the LCO was not violated.

At no time was there any danger to the health and safety of the general public or site personnel.

CORRECTIVE ACTION

Valves 1PS24 and 1PS28 were placed on their backseat theathe stem leak-i age was stopped.

Valves IPS24 and lPS28 will be repacked at the next l

scheduled outage.

'~

I

,~m

,.c.

(

o o

Report No. 77-38/03L 2-5/23/77

)

FAILURE DATA:

Not Applicable

/

/

i 7 / e-n /

' '/-

e, Prepared by T.

L.

Spencer M

er - Salem Generating Station I

SORC Meeting No.

57-77 i

4 1

J

\\

l l

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