ML20065E695: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot change) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:w. ,, - | ||
wwm w | |||
sg m , n't | |||
$.[ ie I)h | |||
$': "j..q a , | |||
.( | |||
L < : | |||
m' ., . f ~ | |||
.... 6-C 43* , , , | |||
. . . ,. [ | |||
19 y Jya f , | |||
; PHILADELPHIA ELECTRICi COMPANY , 1, e~ | |||
* '1 NUCLEAR GROUP HEADQUARTERS . , | |||
3% d l'955 65 CHESTERBROOK BLVD. ! | |||
R) ' WAYNE, PA 19087 5691 G m . | |||
-(215) 640-6000; Sept' ember 19,:1990l 9l n | |||
. Docket Nos. 50-352 0 | |||
-{ 50-353 j | |||
.( | |||
License Nos. NPF-39' # | |||
NPF-85 , . | |||
n | |||
(.;c < | |||
1 s! | |||
hk U.S. Nuclear.Regul' atory Commission Attn: Document Control Desk Washington, DC- 20555 " | |||
y ' | |||
J | |||
[ | |||
==SUBJECT:== | |||
Limerick Generating' Station, Units 1 and-2 l NRC Generic. Letter 89-19. " Request for Action Related to . | |||
U | |||
' Resolution of Unresolved Safety Issue A-47.' Safety Implications d of Control Systems in LWR Nuclear Power Plants'," Submittal of.. | |||
* 1 SpecialiReport. | |||
o m Gentlemen: | |||
4 y ,, NRCGenericLetter(GL).89-19,datedSeptember20.1 1989.1 requested ; | |||
p! > licensees to provide a statement as to whether licensees will? implement the. | |||
J, .[ | |||
recommendations providedjin Enclosure 2 of the:GL. :;The.GL also required .< | |||
v flicensees-to provide a: schedule ior.: implementation-of the recommendations and | |||
;f (the basisifor.the! schedule:or to provide' appropriate-justification if-the- 1 | |||
% -recommendations were not going-to be;implementedi~.0ur response to GL 89-19 for | |||
?i. ' Limerick Generating Stationi(LGS), Units'1 and.'2, was provided by our letters i | |||
M' >Ldated. March-20,'1990, and May:4, 1990.-- | |||
a v . | |||
t ' | |||
l [ N k , | |||
. . ;As identified in our MayT4,1990 letter, anL investigation was;perfonned: | |||
;concerning a-Reactor Pressure' Vessel (RPV) rapid'depressurization' transient:-.. | |||
Ni | |||
@a3;c 'which could. result in an s erfill condition. As a result of this investigation.- | |||
i,f', | |||
j procedural: enhancements have been made to ensure that. plant'oprators can more: | |||
: effectively. mitigate!a-RPV overfill event, specifically as a reselt of-a; rapid '9 | |||
-@ .RPVLdepressurization. :Our;May.4, 1990 letter stated that the deta'Is of this d E; , ,4 ; investigation and procedural enhancements would;be' included in a'Special Report: - | |||
Rh ~ submitted to:the NRC. JAccordingly,;the' Attachment-to this letter provides this - | |||
p , g Special.: Report. :} | |||
!r .. .e m :N , , | |||
e . < .. , ~ | |||
I fC 9 M.'! | |||
gpr t[i . , + | |||
y 9010020265 900919 s - | |||
PDR ADOCK 05000352" | |||
) | |||
M[U$ h , l P. PNU J g /j h$$ #MUg .sv .. . 4i | |||
me ::. cs . | |||
, . . . . ~ | |||
1 | |||
,,. 7 : ,' e' ' ~ | |||
up 4 l^;:l l > y'.' ( \l' > ~ -~_ g. | |||
~ | |||
N' ' ~~ . | |||
w w; - | |||
n | |||
=;m | |||
* ;J g /r y' c s i. > | |||
; w :. ,,.w 3 y ' | |||
< : ULS} Nuc1har[ Regulatory Commission Page 2c j c | |||
, go; , - ' | |||
.a | |||
, . . .y- , | |||
; nil. ;]. . ,.]' | |||
4 r. | |||
e, . | |||
- V' j g; .-If you. have any questions, or require additional:information, please; | |||
# contact us. | |||
o. | |||
+:- | |||
R. , | |||
t . | |||
, 1 we > . . | |||
Very truly yours, u | |||
,. ^ | |||
.e | |||
'~, | |||
.--{' i l | |||
. = | |||
q l ,h,l [ 4.$ . | |||
* N G.'A. Hunt , Jr. * | |||
*i Manager . | |||
i | |||
,. Licensing . | |||
"1 ' ' | |||
Nuclear Engineering and Services: | |||
H | |||
==Attachment:== | |||
: stj | |||
. : cc: T. T.' Martin, Administrator, Region I, USNRC 9.. . | |||
.u DT.-.J. Kenny tUSNRC. Senior Resident' Inspector, LGS- % , | |||
, H | |||
- . ;11 | |||
. .t. p t | |||
. vl k | |||
l' i | |||
. .i | |||
.'. l | |||
-3 rc , | |||
) | |||
*+ g;, j )'' | |||
: 1. .y | |||
.1 p- 7, : - | |||
'1 I | |||
' "' " I | |||
,. .,I,,' | |||
,-.f. , | |||
s , '*: ( 3. , . | |||
n.. , .1 dlb | |||
,Js | |||
'hk I 3j ,f, [, e, I,.A.,, { , | |||
r | |||
.l . | |||
.I. 4,, | |||
1 | |||
~ ' | |||
H | |||
,y 0 | |||
ry a' .# | |||
4 ,p. , e I | |||
.' ,f '. | |||
.: 1 | |||
} g:( | |||
a , , . | |||
.W: , | |||
J ,b i | |||
: v. ; , | |||
(..t e.;is y!) | |||
, 'r' | |||
( ' /.'-i'3,' ' ,' :) | |||
;4 y . | |||
" 'l M e.0 . . < | |||
a t @0 - * | |||
, , i. | |||
j r?; i | |||
' 5 , j, U U, ~- | |||
rs. | |||
col | |||
's sqc. ma t,. , : | |||
t e , < ? | |||
'; Q:?_,*< | |||
. T.!E p e j f!. | |||
ll U q ' .,. w, _ay f. . .. ;< n.'. .: ,. , i .- | |||
'4 - r , | |||
' '; L. | |||
st5 l | |||
.=, _ , | |||
. , , 3 .iU. , | |||
, .. - -~ . .- - .. -- - - _ . - . . - . ~ . | |||
w w | |||
-Attachment' y | |||
. : .. e , | |||
Page l'of IL j it | |||
.g3 g Docket Nos. 50-352 | |||
'-E H 353 5 4 | |||
. t; | |||
^ | |||
-Limerick Generating Station ; Units l'and 2-Generic Letter 89-19 | |||
' ' l H | |||
" Request for Action Related to Resolution of l 1 . | |||
Unresolved Safety-Issue A-47 fSafety Implication of. Contml Systems in LWR Nuclear Power Plants'" i Special Report ' | |||
~ | |||
c Ai referenced to in our response to Generic Letter 89-19, dated May 4.1990,- u a separate investigatioa was performed concerning a Reactor Pressure Vessel : | |||
, ;(RPV), rapid:depresTurizat'on transient which could result in D an overfill! ' | |||
l | |||
, condition. 'Asta re m it'of.?.his investigation, procedural enhancements have been | |||
.made,to ensure that opc*ators can more effectively mitigate an RPV' overfill . H | |||
,;1 event, specifically.as a result'of a rapid RPV depressurization. | |||
Operational Transient-(OT). procedure OT-110, " Reactor Hioh Level," has been l revised and implemented to address the subject issue. Procedure OT-110 is 1 L,4 ' | |||
entered whenever there is.an untxpected or unexplained rise in RPV water. level - | |||
~ l H | |||
which could be due to Sondensate. injection.: This procedure is applicable 1 1 | |||
.whenever RPV overfill. transient would be a concernO during normal operation ' , | |||
g plant: transients, startups and shutdowns. The Main Control Room (MCR) operators; are alerted to this condition by 4*munciation of the. " Reactor HI-LO Level" alarm | |||
: s. , | |||
:or-by visual Observation of an increase in RFV level indicated by the RPVl level 4 : instrumentation.7 The.inusediate' operator action is to reduce feedwater flow " j until normal level is restored. Follow-up actions : include closing:of the Main : 1 Steam.. Isolation Valves (MSIVs) and the primary containment isolation valves for y e | |||
.the High. Pressure Coolant' Injection (HPCI) and Reactor Core Isolation Cooling j g (RCIC); systems'beforetheRPVwaterlevelreaches'thelevelofthe=steamlines. " | |||
u Procedure OT-110 follow-up actions were revised to provide' additional guidance in the following areas. > | |||
h o 1 Terminating l condensate. injection.- ~ | |||
u o' : Terminating Control Rod Drive (CRD) injection. ,A o . Reducing RPV water inventory with Main Turbine Bypass Valve or Safety; C | |||
u . Relief' Valves (SRVs) operation to avoid flooding the Main Steas; Lines.. O M - | |||
u | |||
:q o- Draining Main Steam lines via steam line: drains to the condenser. u o SRV operation:with Main Steam lines flooded.. | |||
.] | |||
o 'c t 0: Incorporation of a reactor pressure and temperature-diagram for p y Permissible SRV Discharge of: Water (Procedure OT-110 BASES only).- | |||
y q A | |||
Licensed operatoritraining on the revisions to Procedure 01-110 are'being ! | |||
'4 ' | |||
conducted via on-shift notifications and will be incorporated:into the Licensed' Operator:Requalification (LOR) Program. | |||
' w" | |||
+ -Based lon.these actions, existing operating. procedures aM operator training' j 2 | |||
are sufficient;to ensureithat the' operators can mitigate RPV averfill events.' | |||
~ | |||
,t L j | |||
y oi h( I n 4 | |||
/w r}} | |||
Revision as of 08:30, 6 January 2021
| ML20065E695 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/19/1990 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, NUDOCS 9010020265 | |
| Download: ML20065E695 (3) | |
Text
{{#Wiki_filter:w. ,, - wwm w sg m , n't
$.[ ie I)h
$': "j..q a ,
.(
L < : m' ., . f ~
.... 6-C 43* , , ,
. . . ,. [
19 y Jya f ,
; PHILADELPHIA ELECTRICi COMPANY , 1, e~
* '1 NUCLEAR GROUP HEADQUARTERS . ,
3% d l'955 65 CHESTERBROOK BLVD. ! R) ' WAYNE, PA 19087 5691 G m .
-(215) 640-6000; Sept' ember 19,:1990l 9l n
. Docket Nos. 50-352 0
-{ 50-353 j
.(
License Nos. NPF-39' # NPF-85 , . n (.;c < 1 s! hk U.S. Nuclear.Regul' atory Commission Attn: Document Control Desk Washington, DC- 20555 " y ' J [
SUBJECT:
Limerick Generating' Station, Units 1 and-2 l NRC Generic. Letter 89-19. " Request for Action Related to . U
' Resolution of Unresolved Safety Issue A-47.' Safety Implications d of Control Systems in LWR Nuclear Power Plants'," Submittal of..
- 1 SpecialiReport.
o m Gentlemen: 4 y ,, NRCGenericLetter(GL).89-19,datedSeptember20.1 1989.1 requested ; p! > licensees to provide a statement as to whether licensees will? implement the. J, .[ recommendations providedjin Enclosure 2 of the:GL. :;The.GL also required .< v flicensees-to provide a: schedule ior.: implementation-of the recommendations and
- f (the basisifor.the! schedule
- or to provide' appropriate-justification if-the- 1
% -recommendations were not going-to be;implementedi~.0ur response to GL 89-19 for ?i. ' Limerick Generating Stationi(LGS), Units'1 and.'2, was provided by our letters i M' >Ldated. March-20,'1990, and May:4, 1990.-- a v . t ' l [ N k ,
. . ;As identified in our MayT4,1990 letter, anL investigation was;perfonned:
;concerning a-Reactor Pressure' Vessel (RPV) rapid'depressurization' transient:-..
Ni
@a3;c 'which could. result in an s erfill condition. As a result of this investigation.-
i,f', j procedural: enhancements have been made to ensure that. plant'oprators can more:
- effectively. mitigate!a-RPV overfill event, specifically as a reselt of-a; rapid '9
-@ .RPVLdepressurization. :Our;May.4, 1990 letter stated that the deta'Is of this d E; , ,4 ; investigation and procedural enhancements would;be' included in a'Special Report: -
Rh ~ submitted to:the NRC. JAccordingly,;the' Attachment-to this letter provides this - p , g Special.: Report. :} !r .. .e m :N , , e . < .. , ~ I fC 9 M.'! gpr t[i . , + y 9010020265 900919 s - PDR ADOCK 05000352"
)
M[U$ h , l P. PNU J g /j h$$ #MUg .sv .. . 4i
me ::. cs .
, . . . . ~
1
,,. 7 : ,' e' ' ~
up 4 l^;:l l > y'.' ( \l' > ~ -~_ g.
~
N' ' ~~ . w w; - n
=;m
* ;J g /r y' c s i. >
; w :. ,,.w 3 y '
< : ULS} Nuc1har[ Regulatory Commission Page 2c j c
, go; , - '
.a
, . . .y- ,
; nil. ;]. . ,.]'
4 r. e, .
- V' j g; .-If you. have any questions, or require additional:information, please;
# contact us.
o.
+:-
R. , t .
, 1 we > . .
Very truly yours, u
,. ^
.e
'~,
.--{' i l
. =
q l ,h,l [ 4.$ .
- N G.'A. Hunt , Jr. *
*i Manager .
i
,. Licensing .
"1 ' ' Nuclear Engineering and Services: H
Attachment:
- stj
. : cc: T. T.' Martin, Administrator, Region I, USNRC 9.. .
.u DT.-.J. Kenny tUSNRC. Senior Resident' Inspector, LGS- % ,
, H
- . ;11
. .t. p t
. vl k
l' i
. .i
.'. l
-3 rc ,
)
- + g;, j )
- 1. .y
.1 p- 7, : -
'1 I
' "' " I
,. .,I,,'
,-.f. ,
s , '*: ( 3. , . n.. , .1 dlb
,Js
'hk I 3j ,f, [, e, I,.A.,, { ,
r
.l .
.I. 4,,
1
~ '
H ,y 0 ry a' .# 4 ,p. , e I
.' ,f '.
.: 1
} g:(
a , , .
.W: ,
J ,b i
- v. ; ,
(..t e.;is y!)
, 'r'
( ' /.'-i'3,' ' ,' :)
;4 y .
" 'l M e.0 . . <
a t @0 - *
, , i.
j r?; i
' 5 , j, U U, ~-
rs. col
's sqc. ma t,. , :
t e , < ? '; Q:?_,*<
. T.!E p e j f!.
ll U q ' .,. w, _ay f. . .. ;< n.'. .: ,. , i .-
'4 - r ,
' '; L.
st5 l
.=, _ ,
. , , 3 .iU. ,
, .. - -~ . .- - .. -- - - _ . - . . - . ~ .
w w
-Attachment' y
. : .. e ,
Page l'of IL j it
.g3 g Docket Nos. 50-352
'-E H 353 5 4
. t;
^
-Limerick Generating Station ; Units l'and 2-Generic Letter 89-19
' ' l H
" Request for Action Related to Resolution of l 1 .
Unresolved Safety-Issue A-47 fSafety Implication of. Contml Systems in LWR Nuclear Power Plants'" i Special Report '
~
c Ai referenced to in our response to Generic Letter 89-19, dated May 4.1990,- u a separate investigatioa was performed concerning a Reactor Pressure Vessel :
, ;(RPV), rapid:depresTurizat'on transient which could result in D an overfill! '
l
, condition. 'Asta re m it'of.?.his investigation, procedural enhancements have been
.made,to ensure that opc*ators can more effectively mitigate an RPV' overfill . H
,;1 event, specifically.as a result'of a rapid RPV depressurization.
Operational Transient-(OT). procedure OT-110, " Reactor Hioh Level," has been l revised and implemented to address the subject issue. Procedure OT-110 is 1 L,4 ' entered whenever there is.an untxpected or unexplained rise in RPV water. level -
~ l H
which could be due to Sondensate. injection.: This procedure is applicable 1 1
.whenever RPV overfill. transient would be a concernO during normal operation ' ,
g plant: transients, startups and shutdowns. The Main Control Room (MCR) operators; are alerted to this condition by 4*munciation of the. " Reactor HI-LO Level" alarm
- s. ,
- or-by visual Observation of an increase in RFV level indicated by the RPVl level 4 : instrumentation.7 The.inusediate' operator action is to reduce feedwater flow " j until normal level is restored. Follow-up actions : include closing:of the Main : 1 Steam.. Isolation Valves (MSIVs) and the primary containment isolation valves for y e
.the High. Pressure Coolant' Injection (HPCI) and Reactor Core Isolation Cooling j g (RCIC); systems'beforetheRPVwaterlevelreaches'thelevelofthe=steamlines. "
u Procedure OT-110 follow-up actions were revised to provide' additional guidance in the following areas. > h o 1 Terminating l condensate. injection.- ~ u o' : Terminating Control Rod Drive (CRD) injection. ,A o . Reducing RPV water inventory with Main Turbine Bypass Valve or Safety; C u . Relief' Valves (SRVs) operation to avoid flooding the Main Steas; Lines.. O M - u
- q o- Draining Main Steam lines via steam line: drains to the condenser. u o SRV operation:with Main Steam lines flooded..
.]
o 'c t 0: Incorporation of a reactor pressure and temperature-diagram for p y Permissible SRV Discharge of: Water (Procedure OT-110 BASES only).- y q A Licensed operatoritraining on the revisions to Procedure 01-110 are'being ! '4 ' conducted via on-shift notifications and will be incorporated:into the Licensed' Operator:Requalification (LOR) Program. ' w"
+ -Based lon.these actions, existing operating. procedures aM operator training' j 2
are sufficient;to ensureithat the' operators can mitigate RPV averfill events.'
~
,t L j y oi h( I n 4
/w r}}