ML19225A118: Difference between revisions
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{{#Wiki_filter:W C1'4 C CC C V Ci '4 i F C.- U n i | {{#Wiki_filter:W C1'4 C CC C V Ci '4 i F C.- U n i | ||
'*CCNTCL ELCCK l | ' | ||
'voE fvat b lC l0 !? lS lV | * | ||
[CJ1]CCN r | . CCNTCL ELCCK l l l l l l l (pLEASE D AINT ALL AE3UIRED 1.*;FC AM AT:CN 1 6 LEENSEE NAME LCENSE EN E N T LCENSE NLveFQ 'voE fvat b lC l0 !? lS lV l114 7 89 0 !0l-l0I0l0l0l0l-l0l0l l 4l 1 1l2l0l [ l 15 25 26 30 31 32 CATELAY Ya[ s$$aN =ccxET NLMCEE EVENT CATE RE8C A T O A ?E | ||
Failure modes and ef fects analyzed. | [CJ1]CCN r 7 8 l l lT l: l 01510 l- l 0 l 2 l 617 016l1l7l7[6l 0l7 12 l 719 57 56 59 50 61 da 69 74 75 6C EVENT CESC9;PY:CN o2 l Wile the reactor was in a cold shutdown conditica, operations personnel observed that 7 89 ec h lone steam water duca valve in each loop was open. Failure modes and ef fects analyzed. l 7 89 ec | ||
[CIdl Steam water dura circuits revised. l 7 39 gg C,l5 l l | |||
7 89 | |||
.2 C 10 16 l A0 76-19A ~g 7 89 sysitu | |||
%g eC CAess cumNea c uacNen COCE 000E COMACNENT :: E SLpay.g uanura,m,, me vet,4res M lIl3l l3 l 7 89 10 11 l 2l ZI Cl ZI ZI 12 l | |||
-.P2 PORT DATE: | 17 lZ l l Z 19 19 l9 lN l | ||
July 12, 1979 A3 NORMAL OCCURRENCE 76-19A Page 1 of 6 OCCURRE' ICE DATE: | ~ | ||
June 17, 1976 FORT ST. VRAIN NUCLEAR GENERATING STATION PU3LIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATIEVILLE, COLORADO 80651 REPORT NO. 50-267/ 76-19A Final IEI.;TIFICATION OF OCCURRENCE: | 2 43 44 47 48 CAUSE DESCFiPT.CN g l The occurrence was due to a design problem. l 7 89 80 l | ||
On June 17, 1976, one steam / water dump valve in each loop was open. | 7 89 l BC | ||
This has been identified as an abnormal occurrence per the Fort St. Vrain Technical Specifications, Section 2.1, paragraph f. | {11C l 7 89 l FactTY MET W O OF 80 STATUS % CWER OThEA STATUS OtSCOVERY Q y l0 l0 l 0 l l N/A l [45 l N/A Ot5COVEAY OESOMTCN l | ||
CONDITIONS PRIOR TO OCCURRENCE: | 7 8 9 10 12 13 44 46 Fcau 0F 80 ACMTTY OONTENT RELEASED AMCUNT CP AN h 2 CF lZlSELEASE N/A l N/A LOCATEN OF EELEASE l | ||
S teady State Power Routine Shutdown Hot Shutdown Routine Load Change X Cold Shutdown Other (specify) | 7 8 9 10 11 44 45 SC PERSCNNEL EXPCSUPES NewetA TYos :EscwicN g l 0l 0l 0 lZl l N/A l 7 89 11 12 13 SQ PERSCNNEL WAAIES NUMBEA OESC M fCN 7 89 l0ln!0l S /A l | ||
11 12 so CFFSITE CCNSECUENCES y N/A l | |||
7 89 _ | |||
50 LCSS CR OAMAGE 70 FACLTf TY99 OESCwrCN k l 2l 7 89 l N/A ~ l 10 80 PtfELLTf | |||
[Iifl l N/A l 7 89 dC ACCIT*CNAL FACTCFS 118 lN/A 3/[$7 fl ~ h 7 89 dC | |||
, ,g l 7 9 07180 W/ c/ ;_ | |||
NAME: l* N* CdhU NCNE: (303) 785-2253 | |||
- | |||
. | |||
P2 PORT DATE: July 12, 1979 A3 NORMAL OCCURRENCE 76-19A Page 1 of 6 OCCURRE' ICE DATE: June 17, 1976 FORT ST. VRAIN NUCLEAR GENERATING STATION PU3LIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATIEVILLE, COLORADO 80651 REPORT NO. 50-267/ 76-19A Final IEI.;TIFICATION OF OCCURRENCE: | |||
On June 17, 1976, one steam / water dump valve in each loop was open. This has been identified as an abnormal occurrence per the Fort St. Vrain Technical Specifications, Section 2.1, paragraph f. | |||
CONDITIONS PRIOR TO OCCURRENCE: S teady State Power Routine Shutdown Hot Shutdown Routine Load Change X Cold Shutdown Other (specify) | |||
Refueling Shutdown Routine Startup The major plant parameters at the time of the event were as follows: | Refueling Shutdown Routine Startup The major plant parameters at the time of the event were as follows: | ||
Power RTR 0 YJth ELECT 0 YJe | Power RTR 0 YJth ELECT 0 YJe Secondarf Coolant Pressure | ||
* Circulators lA 1,500 RPM on Feedwater 13 1,500 RPM on Feedwater 1C 1,500 RPM on Feedwater 1D 1,500 RPM on Feedwater DESCRIPTION OF O CCURRE' ICE : | - | ||
1,000 psig Temperature 174 *F Flow 100,000 #/hr. | |||
Primary Coolant Pressure 340 psig Temperature 194 *F Core Inlet 194 *F Core Outlet Flow * | |||
#/hr. | |||
347 031 - | |||
ABNORMA1. OCCURRENCE 76-19A Page 2 of 6 CONDITIONS PRIOR TO OCCURRENCE (continued) : | |||
* Circulators lA 1,500 RPM on Feedwater 13 1,500 RPM on Feedwater 1C 1,500 RPM on Feedwater 1D 1,500 RPM on Feedwater DESCRIPTION OF O CCURRE' ICE : | |||
The reactor operator was =aking a routine check of the plant control boards and noticed that a s ea=/ water du=p valve in each loop was open and the alarm light was lit. | The reactor operator was =aking a routine check of the plant control boards and noticed that a s ea=/ water du=p valve in each loop was open and the alarm light was lit. | ||
APPARENT CAUSE I 0F OCCURRENCE: | APPARENT CAUSE I 0F OCCURRENCE: X Design Unusual Se rvice Cond. | ||
X Design Unusual Se rvice Cond. | I Including Environ =ent Manufacture Co=penent Failure Ins tallation/Const. Other (specify) | ||
I Including Environ =ent Manufacture Co=penent Failure Ins tallation/Const. | |||
Other (specify) | |||
Op era tor Procedure ANALYSIS OF OCCURRENCE: | Op era tor Procedure ANALYSIS OF OCCURRENCE: | ||
Reference attached Figure 1 which shows two parallel du=p valves in a loop and the trip signals which will open a du=p valve. Loop 1 and Loop 2 du=p valves discharge to a co==en s team / water du=p tank. | Reference attached Figure 1 which shows two parallel du=p valves in a loop and the trip signals which will open a du=p valve. Loop 1 and Loop 2 du=p valves discharge to a co==en s team / water du=p tank. Figure 2 shows the inter-locks which were required to be closed to open a s team / water dump valve. If a loop steam / water du=p valve is open, its relay must be energized. Th e en-ergized relay and position switches on the open valve interlock and should prevent automatic opening of either steam / water du=p valve in tF1 other loop. | ||
Figure 2 shows the inter-locks which were required to be closed to open a s team / water dump valve. | |||
If a loop steam / water du=p valve is open, its relay must be energized. | |||
Th e en-ergized relay and position switches on the open valve interlock and should prevent automatic opening of either steam / water du=p valve in tF1 other loop. | |||
The seal in circuit also insures that operator action is required to close an open valve by utilizing the hand switch. | The seal in circuit also insures that operator action is required to close an open valve by utilizing the hand switch. | ||
The manual bypass can open a valve in each loop but this also requires opera-tor action. | The manual bypass can open a valve in each loop but this also requires opera-tor action. | ||
The steam water du=p valves were tested on June 16, 1976, per approved surveil-lance test S R 5 - 3.1-Q . | The steam water du=p valves were tested on June 16, 1976, per approved surveil-lance test S R 5 - 3.1-Q . | ||
bb b | ~ | ||
.ABNORMAL OCCL"ARENCE 76-19A | bb b | ||
? age 3 of 6 CORRE CTIVE ACTION: f Approved test, T-46, tested the s team water du=p valve circuitry. | |||
The | . | ||
Failure modes and effect analysis was perfor=ed. | ABNORMAL OCCL"ARENCE 76-19A | ||
For the s team water du=p circuit as it existed, the analysis did not identify any other unacceptable system consequences than were known to exist. | ? age 3 of 6 CORRE CTIVE ACTION: | ||
These were (1) the potential | f Approved test, T-46, tested the s team water du=p valve circuitry. The relay l logic system operated as specified and thers was no explanation f or the simul-taneous opening of a s team / water du=p valve in each loop. | ||
Failure modes and effect analysis was perfor=ed. For the s team water du=p circuit as it existed, the analysis did not identify any other unacceptable | |||
'monitors out of service and tripped acco=panied by an instrument bus f ailure, and (2) du=p inhibit of Loops 1 and 2 due to single integrated circuit chip failures.For the proposed modified design, the analysis indicated both the | , system consequences than were known to exist. These were (1) the potential l for a concurrent du= of Loops 1 and 2 with the permissible nu=ber of moisture | ||
;unacceptable system consequences stated above were eliminated and no others | ' | ||
!were introduced. Based on the results of these analyses, it was concluded | monitors out of service and tripped acco=panied by an instrument bus f ailure, and (2) du=p inhibit of Loops 1 and 2 due to single integrated circuit chip failures. For the proposed modified design, the analysis indicated both the | ||
[that the design modifications to the steam / water du=p system satisfy all Plant | ; unacceptable system consequences stated above were eliminated and no others | ||
! were introduced. Based on the results of these analyses, it was concluded | |||
[ that the design modifications to the steam / water du=p system satisfy all Plant Protective System requirements and are consistent with the original design | |||
Vrain steam water dump system circuitry. The modifications are as follows: | {, basis of the plant. | ||
'l.Made the auto =atic trip upon moisture monitor system f ailure a manual action; and revised the logic to per=it individual manual trip of the associated =cisture monitor (as opposed to disabling by pairs) . | t t | ||
The moisture monitor trip outputs (reflected light) were revised to transmission logic. | i The following describes the modifications resulting from various analysis of i the Fort S t. Vrain steam water dump system circuitry. The modifications are as follows: | ||
The alar =.s and indications have been reviewed to assure that the operator is advised of moisture monitor system failure and enable him to readily ascertain manually tripped channels. | ' | ||
2.Revised the relay interlocks to eli=inate an undesirable single f ailure | : l. Made the auto =atic trip upon moisture monitor system f ailure a manual action; and revised the logic to per=it individual manual trip of the associated =cisture monitor (as opposed to disabling by pairs) . | ||
The moisture monitor trip outputs (reflected light) were revised to transmission logic. The alar =.s and indications have been reviewed to assure that the operator is advised of moisture monitor system failure and enable him to readily ascertain manually tripped channels. | |||
See Reportable Occurrence Report No. 50-267/77- | + | ||
'7(14)A..3.Removed the temporary time delay relay modification. | : 2. Revised the relay interlocks to eli=inate an undesirable single f ailure | ||
:nhibit problem. See Reportable Occurrence Report No. 50-267/77- | |||
'7(14)A. | |||
. | |||
, 3. Removed the temporary time delay relay modification. | |||
I l The modified circuits have b een functionally tested successfully, i | |||
l The applicable operating procedure has been revised. | |||
l l No further corrective action is anticipated or required. | |||
FAILURE DATA /SIMILAR REPORTED OCCURRENCES: | FAILURE DATA /SIMILAR REPORTED OCCURRENCES: | ||
None PROGRA"MATIC IMP ACT: | None PROGRA"MATIC IMP ACT: | ||
None CODE IMPACT:)k! | None CODE IMPACT: | ||
.'ABNOFXAL OCCUIL" '!CE 7G-19A | None )k! | ||
. | |||
# | . | ||
_ _ _ _ _ _ _ . _ | ' | ||
_ _ , VALVE VALVE I I | " | ||
ABNOFXAL OCCUIL" '!CE 7G-19A | |||
, Page 4 of e T | |||
- | ] | ||
!OUMP PRESSURE---i VALVES | r ^ ''- - - -- -- ' | ||
,,,_,___J'SIGNALS DUMP | '' I | ||
FIGURE 1 347 03f~ | , | ||
. | r- - | ||
f ' | |||
l | |||
__ | |||
-on Loop 2 valves). | .:' \ | ||
r- | l HYDRAULIC Y I LOOP 1 VALVES SET , 1 STEAM GENERATOR | ||
- | # ENE.~GlZE " | ||
# | MODULES l | ||
(1) Relay contacts are open if the Loop 2 dump relay is energized; closed if de-energized. | TO CLOSE l AAAAAA CHECK Y VALVE bl | ||
(2) Valve position switches are on each Loop 2 dump valve. | :: vs N k i FEEDWATER BLOCK REGULATING 6._ __ _ _ _ _ _ _ _ _ . _ _ _ , | ||
Contacts open it valve is not fully closed, closed if valve is closed. | VALVE VALVE I I y . .. _ _ | ||
(3) Contacts open if Loop 1 or Loop 2 feedwater flow is low.(l. ) Open if Loop 2 is shutdown by PPS. | _q , , | ||
(5) Hand switch utilized to terminate a stea=/ water du=p whan required; contact no r= ally closed.(6) Relay controlling or.e Loop 1 du=p valve relay cust energize to open a Loop 1 dump valve. | " | ||
FIGURE 2 3 t(7 036- | l i , | ||
.A3 NORMAL OCCURRENCE 76-19A Page 6 of 6 Prepared by: W A, Micpael J. Ferr1[- j Technical Services Engineer Reviewed by-f W. | I l .:' | ||
6 Frank M. Mathie Operations Manager Approved by: | T HIGH REACTOR I | ||
W4vu'Don Warembourg Manager, Nuclear Productuan bk 0.}} | -' | ||
MOISTURE q/ \/ HYDRAULIC | |||
' | |||
LEVIL SIGNALS | |||
---t VALVES SET I | |||
ENERGlZE | |||
- :# E TO OPEN l From Loo; HV-2215 y 2 Dump HIGH REACTOR l | |||
! | |||
{ h Valves OUMP - | |||
PRESSURE SIGNALS | |||
---i VALVES y | |||
l L.O. L.O. | |||
I ig. | |||
I g OTHER PLANT ,,,_,___J ' | |||
SIGNALS DUMP TANK l V / | |||
\ | |||
. h Steam / water du=p syste= (Loop 1) | |||
FIGURE 1 | |||
~ | |||
347 03f | |||
~ | |||
. | |||
. | |||
A3:!OR".AL OCCURRE!!CE 76-19A Page 5 of 6 | |||
__ | |||
Stea=/ water dump actuating signals (1) Both Loop 2 du=p valve relay CR-2216 and CR- -- | |||
2218 de-energized % (1 T -- | |||
~ | |||
(2) Both Loop 2 dump valves Manual Bypass closed (position switches } | |||
- | |||
on Loop 2 valves). r- gg 11- | |||
_4-- | |||
- | |||
In (3) Loop 1 or Loop 2 feedwater flow low. | |||
( | |||
1 Prior to Circuit Revis ion f | |||
- | |||
- | |||
_ | |||
T (4) -Open whee _ Loop 2 T | |||
(S) Hand switch. #l I CR Loop 1 du=p valve (6). | |||
l (1) Relay contacts are open if the Loop 2 dump relay is energized; closed if de-energized. | |||
(2) Valve position switches are on each Loop 2 dump valve. Contacts open it valve is not fully closed, closed if valve is closed. | |||
(3) Contacts open if Loop 1 or Loop 2 feedwater flow is low. | |||
(l. ) Open if Loop 2 is shutdown by PPS. | |||
(5) Hand switch utilized to terminate a stea=/ water du=p whan required; contact no r= ally closed. | |||
(6) Relay controlling or.e Loop 1 du=p valve relay cust energize to open a Loop 1 dump valve. | |||
FIGURE 2 3 t(7 036 - | |||
. | |||
A3 NORMAL OCCURRENCE 76-19A Page 6 of 6 Prepared by: W A, Micpael J. Ferr1[- j Technical Services Engineer Reviewed by-J G4h5 f W. | |||
chnical Services Supervisor Reviewed by: 6 Frank M. Mathie Operations Manager Approved by: W4vu ' | |||
Don Warembourg Manager, Nuclear Productuan bk 0 | |||
.}} |
Revision as of 11:43, 19 October 2019
ML19225A118 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 07/12/1979 |
From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
Shared Package | |
ML19225A117 | List: |
References | |
NUDOCS 7907180444 | |
Download: ML19225A118 (7) | |
Text
W C1'4 C CC C V Ci '4 i F C.- U n i
'
. CCNTCL ELCCK l l l l l l l (pLEASE D AINT ALL AE3UIRED 1.*;FC AM AT:CN 1 6 LEENSEE NAME LCENSE EN E N T LCENSE NLveFQ 'voE fvat b lC l0 !? lS lV l114 7 89 0 !0l-l0I0l0l0l0l-l0l0l l 4l 1 1l2l0l [ l 15 25 26 30 31 32 CATELAY Ya[ s$$aN =ccxET NLMCEE EVENT CATE RE8C A T O A ?E
[CJ1]CCN r 7 8 l l lT l: l 01510 l- l 0 l 2 l 617 016l1l7l7[6l 0l7 12 l 719 57 56 59 50 61 da 69 74 75 6C EVENT CESC9;PY:CN o2 l Wile the reactor was in a cold shutdown conditica, operations personnel observed that 7 89 ec h lone steam water duca valve in each loop was open. Failure modes and ef fects analyzed. l 7 89 ec
[CIdl Steam water dura circuits revised. l 7 39 gg C,l5 l l
7 89
.2 C 10 16 l A0 76-19A ~g 7 89 sysitu
%g eC CAess cumNea c uacNen COCE 000E COMACNENT :: E SLpay.g uanura,m,, me vet,4res M lIl3l l3 l 7 89 10 11 l 2l ZI Cl ZI ZI 12 l
17 lZ l l Z 19 19 l9 lN l
~
2 43 44 47 48 CAUSE DESCFiPT.CN g l The occurrence was due to a design problem. l 7 89 80 l
7 89 l BC
{11C l 7 89 l FactTY MET W O OF 80 STATUS % CWER OThEA STATUS OtSCOVERY Q y l0 l0 l 0 l l N/A l [45 l N/A Ot5COVEAY OESOMTCN l
7 8 9 10 12 13 44 46 Fcau 0F 80 ACMTTY OONTENT RELEASED AMCUNT CP AN h 2 CF lZlSELEASE N/A l N/A LOCATEN OF EELEASE l
7 8 9 10 11 44 45 SC PERSCNNEL EXPCSUPES NewetA TYos :EscwicN g l 0l 0l 0 lZl l N/A l 7 89 11 12 13 SQ PERSCNNEL WAAIES NUMBEA OESC M fCN 7 89 l0ln!0l S /A l
11 12 so CFFSITE CCNSECUENCES y N/A l
7 89 _
50 LCSS CR OAMAGE 70 FACLTf TY99 OESCwrCN k l 2l 7 89 l N/A ~ l 10 80 PtfELLTf
[Iifl l N/A l 7 89 dC ACCIT*CNAL FACTCFS 118 lN/A 3/[$7 fl ~ h 7 89 dC
, ,g l 7 9 07180 W/ c/ ;_
NAME: l* N* CdhU NCNE: (303) 785-2253
-
.
P2 PORT DATE: July 12, 1979 A3 NORMAL OCCURRENCE 76-19A Page 1 of 6 OCCURRE' ICE DATE: June 17, 1976 FORT ST. VRAIN NUCLEAR GENERATING STATION PU3LIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATIEVILLE, COLORADO 80651 REPORT NO. 50-267/ 76-19A Final IEI.;TIFICATION OF OCCURRENCE:
On June 17, 1976, one steam / water dump valve in each loop was open. This has been identified as an abnormal occurrence per the Fort St. Vrain Technical Specifications, Section 2.1, paragraph f.
CONDITIONS PRIOR TO OCCURRENCE: S teady State Power Routine Shutdown Hot Shutdown Routine Load Change X Cold Shutdown Other (specify)
Refueling Shutdown Routine Startup The major plant parameters at the time of the event were as follows:
Power RTR 0 YJth ELECT 0 YJe Secondarf Coolant Pressure
-
1,000 psig Temperature 174 *F Flow 100,000 #/hr.
Primary Coolant Pressure 340 psig Temperature 194 *F Core Inlet 194 *F Core Outlet Flow *
- /hr.
347 031 -
ABNORMA1. OCCURRENCE 76-19A Page 2 of 6 CONDITIONS PRIOR TO OCCURRENCE (continued) :
- Circulators lA 1,500 RPM on Feedwater 13 1,500 RPM on Feedwater 1C 1,500 RPM on Feedwater 1D 1,500 RPM on Feedwater DESCRIPTION OF O CCURRE' ICE :
The reactor operator was =aking a routine check of the plant control boards and noticed that a s ea=/ water du=p valve in each loop was open and the alarm light was lit.
APPARENT CAUSE I 0F OCCURRENCE: X Design Unusual Se rvice Cond.
I Including Environ =ent Manufacture Co=penent Failure Ins tallation/Const. Other (specify)
Op era tor Procedure ANALYSIS OF OCCURRENCE:
Reference attached Figure 1 which shows two parallel du=p valves in a loop and the trip signals which will open a du=p valve. Loop 1 and Loop 2 du=p valves discharge to a co==en s team / water du=p tank. Figure 2 shows the inter-locks which were required to be closed to open a s team / water dump valve. If a loop steam / water du=p valve is open, its relay must be energized. Th e en-ergized relay and position switches on the open valve interlock and should prevent automatic opening of either steam / water du=p valve in tF1 other loop.
The seal in circuit also insures that operator action is required to close an open valve by utilizing the hand switch.
The manual bypass can open a valve in each loop but this also requires opera-tor action.
The steam water du=p valves were tested on June 16, 1976, per approved surveil-lance test S R 5 - 3.1-Q .
~
bb b
.
ABNORMAL OCCL"ARENCE 76-19A
? age 3 of 6 CORRE CTIVE ACTION:
f Approved test, T-46, tested the s team water du=p valve circuitry. The relay l logic system operated as specified and thers was no explanation f or the simul-taneous opening of a s team / water du=p valve in each loop.
Failure modes and effect analysis was perfor=ed. For the s team water du=p circuit as it existed, the analysis did not identify any other unacceptable
, system consequences than were known to exist. These were (1) the potential l for a concurrent du= of Loops 1 and 2 with the permissible nu=ber of moisture
'
monitors out of service and tripped acco=panied by an instrument bus f ailure, and (2) du=p inhibit of Loops 1 and 2 due to single integrated circuit chip failures. For the proposed modified design, the analysis indicated both the
- unacceptable system consequences stated above were eliminated and no others
! were introduced. Based on the results of these analyses, it was concluded
[ that the design modifications to the steam / water du=p system satisfy all Plant Protective System requirements and are consistent with the original design
{, basis of the plant.
t t
i The following describes the modifications resulting from various analysis of i the Fort S t. Vrain steam water dump system circuitry. The modifications are as follows:
'
- l. Made the auto =atic trip upon moisture monitor system f ailure a manual action; and revised the logic to per=it individual manual trip of the associated =cisture monitor (as opposed to disabling by pairs) .
The moisture monitor trip outputs (reflected light) were revised to transmission logic. The alar =.s and indications have been reviewed to assure that the operator is advised of moisture monitor system failure and enable him to readily ascertain manually tripped channels.
+
- 2. Revised the relay interlocks to eli=inate an undesirable single f ailure
- nhibit problem. See Reportable Occurrence Report No. 50-267/77-
'7(14)A.
.
, 3. Removed the temporary time delay relay modification.
I l The modified circuits have b een functionally tested successfully, i
l The applicable operating procedure has been revised.
l l No further corrective action is anticipated or required.
FAILURE DATA /SIMILAR REPORTED OCCURRENCES:
None PROGRA"MATIC IMP ACT:
None CODE IMPACT:
None )k!
.
.
'
"
, Page 4 of e T
]
r ^ - - - -- -- '
I
,
r- -
f '
l
__
.:' \
l HYDRAULIC Y I LOOP 1 VALVES SET , 1 STEAM GENERATOR
- ENE.~GlZE "
MODULES l
TO CLOSE l AAAAAA CHECK Y VALVE bl
- vs N k i FEEDWATER BLOCK REGULATING 6._ __ _ _ _ _ _ _ _ _ . _ _ _ ,
VALVE VALVE I I y . .. _ _
_q , ,
"
l i ,
I l .:'
T HIGH REACTOR I
-'
MOISTURE q/ \/ HYDRAULIC
'
LEVIL SIGNALS
---t VALVES SET I
ENERGlZE
- :# E TO OPEN l From Loo; HV-2215 y 2 Dump HIGH REACTOR l
!
{ h Valves OUMP -
PRESSURE SIGNALS
---i VALVES y
l L.O. L.O.
I ig.
I g OTHER PLANT ,,,_,___J '
SIGNALS DUMP TANK l V /
\
. h Steam / water du=p syste= (Loop 1)
FIGURE 1
~
347 03f
~
.
.
A3:!OR".AL OCCURRE!!CE 76-19A Page 5 of 6
__
Stea=/ water dump actuating signals (1) Both Loop 2 du=p valve relay CR-2216 and CR- --
2218 de-energized % (1 T --
~
(2) Both Loop 2 dump valves Manual Bypass closed (position switches }
-
on Loop 2 valves). r- gg 11-
_4--
-
In (3) Loop 1 or Loop 2 feedwater flow low.
(
1 Prior to Circuit Revis ion f
-
-
_
T (4) -Open whee _ Loop 2 T
(S) Hand switch. #l I CR Loop 1 du=p valve (6).
l (1) Relay contacts are open if the Loop 2 dump relay is energized; closed if de-energized.
(2) Valve position switches are on each Loop 2 dump valve. Contacts open it valve is not fully closed, closed if valve is closed.
(3) Contacts open if Loop 1 or Loop 2 feedwater flow is low.
(l. ) Open if Loop 2 is shutdown by PPS.
(5) Hand switch utilized to terminate a stea=/ water du=p whan required; contact no r= ally closed.
(6) Relay controlling or.e Loop 1 du=p valve relay cust energize to open a Loop 1 dump valve.
FIGURE 2 3 t(7 036 -
.
A3 NORMAL OCCURRENCE 76-19A Page 6 of 6 Prepared by: W A, Micpael J. Ferr1[- j Technical Services Engineer Reviewed by-J G4h5 f W.
chnical Services Supervisor Reviewed by: 6 Frank M. Mathie Operations Manager Approved by: W4vu '
Don Warembourg Manager, Nuclear Productuan bk 0
.