ML20092G926
Text
Appf0v3 DIOcedur. N3, Vogtle Electric Generatinc Plant MY NUCLEAR OPERATICNG
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ABNORMAL OPERATING PROCEDURES OPERATION FRON REMOTE SHUTDOWN PANELS
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*~--.-..L PURPOSE This procedure provides operator instructions in evacuating the Main Control Room, maintaining hot standby, and attaining cold shutdown from the remote shutdown panels.
This procedure is applicable with or without the availability of offsite power.
This procedure addresses sotential or actual component failures which may be induced' -
by Control Room fire events.
.T This arocedure also provides instructions in the' folloWing.:
attachments.
ATTACHMENT A - TURBINE DRIVEN APW PUMP OPERATION FROM SHUTDOWN PANEL C A
ATTACHMENT B - STARTING AND PLACING DG A(B) ON DEAD BUS FROM OUTSIDE THE CONTROL ROOM ATTACHMENT C - REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 ATTACHMENT D - REQUIRED SHUTDOWN MARGIN FOR MODE 5 ATTACHMENT E - RCS/PRZR TEMPERATURE AND PRESSURE DATA
' ATTAC1D&WP F - RCS_lRESSURE TERERATURElIMI S ATTACHMENT G - LOCAL OPERAtidh 0F TIIE SGARVs H TTKCHME F R --E5TamLISHING MARU MW W1HUUT INSTRUMENT AIR
[ATTACHMENTI-NON-PERIODICOPERATIONOF ATTACHMENT J - FIRE EMERCENCY OPERATION OF SCARVs FROM SHUTDOWN PANEL PSDB
- i. ' ~ -
l-SYMPTEMS
.The bain Control Room is or is about to become inaccessible due to fire, toxic gas, or any other unforeseen reasons.
i 9202200396 920116 PDR ADOCK 05000424 S
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f-1 PROCEDURE No.
LEV 158oN PAGE NO VEGP 18038-1 10 2 of 56 ACTIbN'/EXPECTEDRESPONSE RESPONSE NOT OBTAINED IMMEDlATE OPERATOR ACTIONS 1.
Manually trip the reactor NOTE e Step 2 or 3 should be done prior to Control Room evacuation IF personnel safety is NOT hindered, F
e 19000-C REACTOR TRIP AND SAFETY INJECTION should NO-' be inglemented IF, the Control Room is evacuated.
SUBSEQUENT OPERATOR ACTIONS
' j.,
2..
IF a Control Room fire, and at discretion of Shift Supervisor THEN:
- 1) OPEN LV-112E and/or LV-112D
- 2) Shut LV1123 and/or LV112C
- b. Shut PRZR PORV block valves z.
-c. Stop RCP's 1 and-4.
d., Isolate Main Feedwater SEQtr' e
MFIVs e
BFIVs
- e. Shut - SG blowdown isolation valves.
[v^)
- f. Shut MSIVs and bypass valves.
g.-Throttle total AFW to minimum - CREATER THAN 570 gpm.
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PROCEDURE NO.
REVISION PAGE No.
VEGP 18038-1 10 3 of 56
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ACTION / EXPECTED PISPONSE RESPONSE NOT OBTAINED 3.
IF NOT a Control Room fire or at discretion of Unit Shift Supervisor, THEN
- a. Verify turbine trip.
- b. Align VCT for AUID makeup:
e HS-40001A in AUTO e
HS-40001B in AUTO-AFTER-START
~
e FIC-110 pot set at 8.6.
9, o
LV-112A in AUTO e
PV-131 in AUTO
-s
- c. Place PRZR pressure control in AUTO.
- d. Place SG precsure control in AUTO.
e Steam Dumps in STEAM PRESSURE mode,
- e. Throttle total AFW flow
~
to minimum - GREATER THAR 570 gpm.
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9
/
X.
/
9 PRoCEDU E No.
isEVISloN PAGE No-VEGP 18038-1 10 4 of 56 7
i ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE If at any time the Control Room becomes habitable, recovery should commence at Step 53 of this procedure.
CAUTION If Control Room is evacuated due to fire, Shutdown Panel A controls and instrumentation may not be reliable.
Train B is preferable for Control Room fire event operation.
Fire Event qualified instrumentation is marked in red.
4.
Send operators to the 4.
If insufficient personnel following locations to are available, use the
)
perform applicable actions following priority:
K>
of Steps 6 through 9:
- a. Shutdown Panel B.
- a. Shutdorn Panel B.
e Shift Superviser e Reactor Operator e Extra Shift Personriel
- b. Shutdown Panel A.
- b. Shutdown Panel A.
e BOP Operator,
~
- c. Shutdown Panel C AFW
- c. Shutdown Pane'l C AFW Punghouse.
Pumphouse.
o Outside Area Operator.
e OSOS e STA 5.
Upon exiting Control Room,
(~'T isolate shutdown sound-povered phone system from the Control Room.
(located outside east entrance to Unit 1 Control Room)
=
P9oCEDURE No.
- ,EYistoN PAGE No.
i VEGP 18038-1 10 5 of 56
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- c.,
I ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If an SI actuation occurs, any components previously transferred to the Shutdown Panels must be manually actuated by the operator.
Diesel Generator sequencing is also disabled for any load previously transferred to the Shutdown Panels.
Components not transferred to the Shutdown Panel should realign to the safety configuration.
6.
Verify reactor is tripped.
6.
Trip the reac; tor:
i e
Reactor Trip and Bypass e
HS-40002A - Panel A Breaker - OPEN.
_)
Neutron flux - LOWERING'.
e HS-40002B - Panel B e
-OR-Locally open Reactor Trip and Bypass Breakers.
(Control Building, Room RB-71)
-OR-Place the Rod Drive MG sets Motor and Generator Circuit Breakers ~ in TRIP position.
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PROCEDURE No.
A EVISloN PAGE No.
VEGP 18038-1 10 6 of 56
-v ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE After transfer of controls is complete, then match applicable switch flags (targets) with component status.
7.
IF a Control Room fire, 7.
_IF NOT a Control Room fire, THEN perform following:
THEN place transfer switches to LOCAL when required by a
At Shutdown Panel As procedural steps.
e ENSURE Aux. Spray Valve HV-8145 is
- shut, THEN slace transfer switc:1 to LOCAL.
4-
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e ENSURE control switches with orange m
does are aligned
)
properly, THEN place all transfer switches to LOCAL.
- b. At Shutdown Panel B:
e ENSURE control switches with orange does are aligned properly, THEN place all transfer switches to LOCAL.
- c. THEN:)ls'ce all transfer switeles on lAA02-00 to LOCAL.
d.rHEY place all transfer swirches on 1BA03-00 to LOCAL.
.es s.._ /
C 4
PRoCEDUAE l.o-CEVIStoN PAGE No.
VEGP 18038-1 to 7 of 56 ACTION'/ EXPECTED RESPONSE
, RESPONSE NOT OBTAINED NOTE 91000-C, EMERGENCY CLASSIFICATION AND IMPLEMENTING PROCEDURE should be implemented at this time.
8.
Establish communications 8.
All stations on same between all stations, channel or lines (Preferably sound powered telephones remote e
Bridge Phone Ext 3055 shutdown channel, red box) e Page e
Radio u,
CAUTION If a loss of offsite powsr occurs, the NSCW pump should
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be started immediately after the diesel generators have
(_/
restored power to the bus.
9.
Locally verify AC 9.
Attempt to energize any Emergency Buses lAA02 unenergized bus irum and 1BA03 - ENERGIZED
? referred sources ueing by observing:
3andswitch on lAA02-00 or 1BA03-00.
4160 volt matar on each bus.
IF any Emergency Buses cannot be energiz'ed from
-OR-preferred normal source, THEN start a diesel NSCW Flow on each bus generator on that bus using Attachment B.
e FI-1640C -(Train A) e FI-1641C (Train B)
J l
PROCEDURE No.
- EVISioN PAGE No.
VEGP 18038-1 10 8 of 56 (Q
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ACTIOM/ EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Shutting SG ARVs by opening 1AY2A or IBYC1 and shutting MSIVs and MSBVs by opening 1AD12 or IBD12 will require secondary pressure control using Main Steam Code safeties unless initiating Attachment G to locally control SG pressure.
10.
IF a Control Room fire, TREN send operator to:
- a. Trip the following breakers in Table:
' W.
Breaker No.
Location Significant Equipment Action,s
()
1BD12-08 Control Bldg., RB-47 e Shuts MSIVs e Shuts MFIVs e Shucs BFIVs 1BD12-03 Control Bldg., RB-47 e Shuts MSBVs e Isolates RMW to VCT blender e Shuts Head Vent to PRT EV-0442B e Shuts Accumulator Vent HV-0943B e Shuts Safety Grade Charging HV-0190B
~~
. Control Bldg., RB-52 e Shuts MSIVs' e Shuts MFIVs e Shuts BFIVs LAD 12-03 Control Bldg., RB-52 e Shuts MSBVs e Icolates RMW to VCT blender e Shuts Head Vent to PRT HV-0442A e Shuts Accumulator Vent HV-0943A e Shuts Safety Grade Charging HV-0190A g-IBYCl-10 Control Bldg., RB-61 e Shuts SG ai.V PV-3010
(_)S 1BYCl-12 Control Bldg., RB-61 e Shuts SG ARV PV-3020 1ADil-08 Control Bldg., RB-52 e Shuts SGBD e Isolates Fire Protection to CNMT
PMoCEDURE NO.
0.EVISION PAGE No.
VEGP 18038,
10 9 of 56 D
n/ -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Transfer switches on following SWGR to LOCAL:
e 1BB06 (Control Bldg, RB-61) e-IBB07 (Control Bldg, RB-61) e 1AB05 (Control Bldg RB-76) e 1AB04
,(Control Bldg, RB-76) e 1BB16-(Aux. Bldg, R207) e 1AB15 (Aux. Bldg RD-105)
- c. Trip the following
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t breakers in Table:
Breaker No.
Location Significant Equipment Actions 1AY2A-17 Aux. Bldg, Ril8 e Shuts SC ARV PV-3000 1AY2A-18 Aux. Bldg Rll8 e Shuts SG ARV PV-3030
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PROCEDURE NO.
AEvlSION LAGE NO.
VEGP 18038-1 10 10 of 56
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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If there is a Control Room fire, Train B is the preferred pressure train.
11.
Control PR2R pressure 11.
IF pressure less than 2220 between 2220 and 2260 piig AND lowering psigi THEN:
- a. Operate backup heaters
- 1) VerifyPRZRPORVs.PV-45hA on Panel A or Panel B.
on Panel-4.and PV-456A;on Panel B
' SHUT
- b. Operate PRZR sprays on Panel A.
IF PRZR PORV can NOT be
- aEut,
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- c. Ensure at least one THEN manually shut its PRZR PORV block valve block valve.
HV-8000A on Panel A or HV-8000A on Panel A or HV-8000B on Panel B -
HV-8000B on Panel B.
OPEN.
-OR-Trip Breaker 4 on 1ADlM for PV-455A or Breaker 4 on IBDlM for PV-456A.
(located in Control Bldg.,
room RB-52,RB,-47)
- 2) Verify PRZR spray vilves on Panel A - SHUT IF NOT, THEN manually shut.
IF PRZR spray valve can RUT be shut, THEN stop RCP supplying Ti1Ted valve.
RCP 1 for PV-455C or RCP 4 for PV-455B on Panel A.
i'
- 3) Energize PRZR henters
PROCEDURE No.
GEVISION FAGE Noi VEGP 18038-1 10 11 of 56
.[
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4) IF PRZR pressure - LESS TRAN 1870 psig or continues-to lower, THEN perform the following to restore PRZR pressure between 2220 and 2260 sig-and PRZR level 50% to 0%:
- a. Start additional ECCS pumps.
o
@en LV-ll2D or LV-ll2E I
-- 42 Shut'LV-112BJor i e
LV-ll20.
- c. OPEN BIT isolation
. []-
valves.
IF pressure greater than 7760 psig, THEN:
- 1) De-energize PRZR heater on-Panel A and Panel B.
- 2) Control pressure using-normal sprays on Panel A.
IF normal [Pl5R spray NOT available, L
AND letdown is in service, u
THEN-use auxiliary spray-L E7:3145 on Panal A.
n L
IF auxiliar available. y spray NOT l
THEN use PV-455A on Panel'A l
or PV-456A on Panel B.
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PROCEDURE No.
REVISION PAGE NO.
VEGP 18038-1 10 12 of 56 l..
I ACTIONhEXPECTEDRESPONSE RESPONSE NOT OBTAINED CAUiION The AW pumps and throttle valves will NOT respond to automatic signals after control has been transferred.
12.
Control SG WR level (s) at 12.
Initiate Attachment A.
651 to 70% on all SGs.
Turbine Driven AFW pump operation from Panel C.
- a. On Shutdown Panel A:
,Gotostep'ly o
Start MD-AFW Pump A e
Throttle FV-5139 and TV-5137
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hg e
Verify miniflow FV-5155 - OPEN.
b.-On Shutdown Panel Bs e
Start MD-AFW Pump B e
Throttle FV-5134 and F7-5132 e-Verify miniflow FV-5154 - OPEN.
13.
JF both MDAPW pumps are available.
THER legall THIFW yump.y*stop the using Attachment A.
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PROCEDU. E No.
- .EV8SloN PAGE NO VEGP 18038-1 10 13 of 56 ACTION / EXPECTED RESPONSE RESPONSE Nt? OBTAINED CAUTION Shutting MSBV's by opening 1AD12-03 and 1BD12-03 will isolate RMW to VCT blender.
14.
Verify RCS temperature.
14.
IF temperature is less than STABLE AT OR TRENDING TO 337'F and lowering 557'F.
THEN:
- 1) Perify SGARVs on Panel'A and Panel B are SHUT.
!FSGARVYanNOT'be
~
BInually shut, TDEN control RCS cEEperature by initiating
-~
s
)
A4Sachment G, Local i
Operation of the S/G Atmospheric Relief Valves.
-OR-Ensure SGARV shut by opening its breaker:
Aux. Bldg. Room R118 e
17 on LAY 2A for PV-3000 e
18 on LAY 2A for PV-3030 -
Control Bldg. Room RB61:
e 10 on 1BYCl for PV-3010 e
12 on 1BYCl for PV-3020
- 2) IF cooldown continues.
TREN throttle AFW flows to a minimum of 570 gpm 7 y until at least one SG level is above SI NR
~-
N'=
etw+m-*Masam us'du s u"
PROCEDURE No.
s EVCloN L AGE No.
VEGP 18038-1 10 14 of 56
(
)
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ACTIOll/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
Breakers 8 and 3 on LAD 12 (Control Bldg.
Rm RB-52) e Breaker 8 on LAD 11 (Control Bldg. Rm RB-52) e Breakers 8 and 3 on 1BD12 (Control Bldg.
Rm RB-47)
IF temperature greater than 337'F and riaing AND IP a Control Roca.fird, THEN control temperature using 5-20 mA power supply to initiate Attachment J,
)
Fire Emergency Operation of SGARVs From Shutdown Panel PSDB.
-OR-Control RCS temperature by initiating for SGARVs PV-3010 and PV-3020 Attachment G Local Operation of the S/G Atmospheric Relief Valves.
IF temperatureigre.ater than 337'F and rising, AND IF NOT a Control Room
- tire, THEN control temperature
~ ' -
using SGARVs on Panel A or Panel B.
-OR-Control RCS temperature by initiating Attachment G, c3 Local Operation Of The S/G j
Atmospheric Relief Valves, m
PROCEOORE NO.
REVISION PAGE NO
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VEGP 18038-1 10 15 of 56
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ACTION /EXPECTTD RESPONSE RESPONSE NOT OBTAINED NOTE If an SI actuation occurs, TSC consultation may be necessary after it is staffed.
15.
IF an SI actuation occurs.
THEN perform the following
- a. Check if ECCS flow
- a. Do not reduce ECCS flow, should be reduced:
Consult TSC when it is e
RCS subcooling -
staffedi:
GREATER THAN 24*F using Core Exit Go to Step 17.
Temperature and RCS
~
WR pressure 5
i e
RCS pressure - STABLE OR RISING i
)
a PRZR level - GREATER THAN 9%
e Secondary heat sink:
Total feed flow to SGs -
GREATER THAN 570 gpm
-OR-SG WR level - GREATER THAN 65%
e
- h e+
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PRoCEDU, E No.
- .EVISloN Ft.GE No.
VEGP 18038-1 10 16 of 56
)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Train B.is the preferred charging train when operating from remote shutdown panels.
- b. Reduce ECCS flow by stopping the following equipment, e
1 CCP PDP by locally (Aux.
e Bldg. C level Room RC-121) tripping breaker INB21-08.
e' e
SI Pumps e
RHR Pumps L
)
- c. IF preferred notual li'6ver is supplying Emergency 4160V Bus, THEN stop Emergency DTisel Generators using local emergency stop pushbuttons.
- 66 O
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- e-
--iieumm:
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PMoCEDUAE No.
REVi$loN PAGE No.
j VEGP 18038-1 10 17 of 56 0
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
1 1
CAUTION e LV-112B, 112C, ll2D, 112E will NOT reposition on VCT low-low level after they have been transferred to the shutdown panels.
e PRZR heaters will NOT cut off on low PRZR level after their control has been transferred to the shutdown panels.
e When operating from the shutdown panels, Train B is the preferable charging train.
e Shutting MSBVs by opening 1AD12-03 and IBD12-63 will i
isolate RMW to VCT blender.
16.
Control-PRZR level 50% to 70%
- a. Check CCP suction aligned
- a. Align CCP Suction to RWST:
to VCT.
- 1) At Panel B e
LV-112B on Panel A OPEN e
OPEN LV-112E e
LV-ll2C on Panel B e
SHUT LV-112C OPEN e-LV-112D on Panel A
-01.
SRUT *,
e LV-112E.on Panel B-
- 2) At Panel A SEUT
'e Letdown in service e
OPEN LV-112D
~.
(FI-132B on PSDA) e SHUT LV-112B
- b. OPEN charging isolation valves:
e HV-8105 (Panel B) e HV-8106 (Panel A)
-2
PRoCEDU. E No, 4.EVISION PAGE No.
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VEGP 18038-1 10 18 of 56 ACTION / EXPECTED RESPONSE RESPONSE NOT OBfAINED
- c. IF SI actuated.
TREN at discretion of UriE Shif t Supervisor shut BIT isolation valves e
HV-8801A (Panel A) e HV-8801B (Panel B)
- d. Start CCP B on Panel B
- d. Start additional CCP if or CCP A on Panel A desired while waiting for local charging valve 1-FHC-0,121 to be manned,
- e. Stop PDP by locally tripping breaker INB21-08 (Aux. Bldg. C u,
level Room RC-121).
.,./
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PROCEDU..E NO.
REYlSION PAGE NO.
VEGP 18038-1 10 19 of 56 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- f. Maintain PRZR level
- f. IF PRZR level cannot be between 50% and ~3%:
B'"iint aine d,
THEN maintain PRZR level e
Throttle charging between 50% and 70% using using 1-FHC-0121 either of the following:
(located outside PD Pump Room in Aux.
Bldg. RC-113)
- 1) With CCP B running:
Control seal injection a) Verify mini-flow e
flow at 8 to 13 gam by path adjusting 1-1200 'J6-136 and shutting e HV-3110 on Panel A 1-1208-U6-134 (located OPEN in PDP Valve Gallery e HV-8111B on Panel RC-lll).
B 0 PEN
' n..
x
-OR-b) SHUT HV-8438'CCP discharge cross IF instnunent air is NOT connect on Panel.B avai_lable,
-s
)
THEN maintain PR2R level c) OPEN HV-8801B, BIT between 50% and 70% by discharge on Panel B using Attachment H, Establishing Charging d) OPEN HV-8485B, CCP B Without Instrument Air.
discharge on Panel B e) Control PR2R level by:
e Shutting or opening HV-8801B N ~0R-e Stopping and starting CCP B.
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PAcetDU. tidoi 5.EyssioN Pact No.
VEGP 18038-1 10 20 of 56
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ACTION /RXPECTED RESPONSE RESPONSE NOT OBTAINED f) At linit Shift Supervisor's discretion, isolate FV-0121 by shutting 1-l'iC6-U6-153 (in PDP Gallery RC-lll),
and throttle seal injection using 1-1208-U6-151, (located in CCP B Valve Gallery).
Flows can be monitored locally'43B on F1-0144B or FI-01 fn A-level. Trair. E Piping Penetration Roods or on ERF i Computer.
-OR-
)
- 2) With CCP A running a
a) Verify mini-flow path e HV-811d on Panel A OPEN e HV-BillA on Panel B OPEN b) OPEN HV-8485A CCP A discharge on Panel A.
c) OPEN HV-8438 CCP discharge crosaconnect on Panel B.
d) OPEN HV-8801A BIT discharge on Panel A.
e) SHUT HV-8105 CCP discharge on Panel
)
B.
~'--'
a um mu r aa a aa i i
PAoC[ DURE No.
REvi$loN PAGE No.
~
VEGP 18038-1 10 21 of 56
(, m u - J ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED f) Conerol PRZR level by:
e Shutting and opening HV-8801A
-OR-e Stopping and starting CCP A.
g) At Unit Shift Supervisor's discreH on. frolits FV-0121 by shuttin's 1-1208-U6-153 (in PDPhCalleg.RC-111) and throttie seal injection using 1-1208-U6-152
~
(located in CCP A'
'/
Valve Gallery).
Flows can be monitored locally on FI-0144B or FI-0145B t.-level in Train B Piping Penetration Rooms or on ERF Computer.
4 4
4 0
em 4
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PAoCEDU-E No.
A,E vlSloN Pl.G E N o VEGF 18038-1 10 22 of 56
=--
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)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Power cay need to be restored by closing breakers 1AD12-03 and/or 1BD12-03 in Control Building Rooms RB-52 and RB-4 7 to establish safety grade letdown.
- g. IF PRZR level can NOT be iiisintained les:. than 881.
THEN open the followin-until PRZR level lowers less than 701:
e Tre.in B h::d var.t.
e HV-8095B e
HV-8096B e
HV-0442B e
Train A head venti
\\g
'~')
e HV-8095A e
HV-8096A e
HV-0442A 17.
Locally verify at least 17.
Stop all RCPs.
one ACCW pump - RUNNING.
Isolate letdown by closing i
LV-459 and LV-460 (Panel A).
l
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1
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1 (8
C
i
--PROCEDUntNo.
REVISION PAGE No,
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VEGP 18038-1 10 23 of 56 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED t
NOTE 4CP 1 should be run preferentially to provide RCP A - (t norma' F ian sprays.
18.
Verify at least one 18.
IF offsite power is available RCP - RUNNING.
and at least one ACCW pump is in service, THEN:
- a. Start the RCP Oil Lift Pump.
- 6. Verify FRZR spray valver SHUT.
.u,
- c. After about 2 minutes '
start the selected RCP.
g-IF offsite power NOT available 3 ACCQump NOT in service THEN:
Verify that the.RCS is being cooled by natural circulations e
RCS subcooling greater then 50'F.
e SG pressures-stable or lowering.-
e RCS hot leg temperatures stable or lowering.
e RCS cold leg temperatures at saturation for SG pressure.
Refer to Attachment F, RCS Pressure - Temperature Limits.
O smi--miss
PROCLDURE NO.
HEVf 510N PAGEfv0 VEGP 18038-1 10 24 of 56 ACTIO!i/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 19.
IF a Control Room Fire, THEN prevent spurious actions from occurring:
e Secure Containment Sprays by racking outs e
1AA02-14 e
1BA03-14 20.
At the discretion of the Unit Shift Supervisor, locally trip SGFPTs at its front standard.
21.
At the discretion of the Unit Shift Supervisor, T'
i shutdown the following by depressing TRIP on their 7
3 Frankerst
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/
Both Heater Drain Pumps e
(Turb. Bldg. Level 1) e INA04 Brkr 13 e
IRA 01 Brkr 12
.)
All but one Condensate Pump (Turb. Bldg. Level 2) e 1NAA Brkr 6 e
INAN Brkr 5 e
IMAB Brkr 4 All but one Circulating e
, Water Pump (Turb. Bldg.
Level 2),
e INAA Brkr 4 e
INAB Brkr 5 All River Water Makeup e
Pumps not required y
considering requirements
)
of both units.
(River Intake) e ANA01A Brkr 2 e
ANA01A Brkr 3 e
ANA01B Brkr 11 e
ANA01B Brkr 12
PMoCEDURE No.
LEvisioN pAog no VEGP 18038-1 10 25 of 56
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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 22.
IF a Control Room fire.
TREN isolate Excess Letdown and BTRS:
e Open Brkr 14 on IND32.
(Control Bldg. Room RB-53) e Open Brkr 8 on IND31.
(Control Bldg. Room RB-53) 23.
Borate the RCS to a Hot Standby Xenon Free concentration:
- a. Determine required RCS shutdown margin u,
using Attachment C.
8
- b. Determine actual RCS
- b. Go to Step 24.
shutdown margin using (m) 14005-1, S N MARGIN CALCULATION-s LESS THAN REQUIRED.
- c. Start Boric Acid Transfer Pump on Panel A or Panel B.
- d. Open Emergency
- d. If emergency boration Boration Valves path NOT available THEN slilf t CCP suction e
HV-8104 - Panel A to YWST to borate RCS:
'1-0R-Open LV-112D'on' Panel L
A or LV-ll2E on Panel e
RY-8439 - Panel B B.
NOTE With one boric acid transfer pump running and flow through HV-8104, RCS boron concentration will increase about 8 ppm / min. Flow through HV-8439 will increase RCS boron concentration at about 2 ppm / min.
Flow from RWST will increase RCS boron concentration about 1 ppm / min.
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- e. Terminate boration when required shutdown margin is reached or PRZR level reaches 85%.
m
PROCEDUFfE No AEVISION PAGE NO.
VEGP 18038-1 10 26 of 56
')
ACTIOfi/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 24.
IF SI not actuated, THEN 24, Return to Step 23.
Eive Chemistry sample RCS and PR2R for boron -
GREATER THAN REQUIRED.
NOTE If boration was stopped due to high PRZR level THEN continue boration as PR2R level lowers during c33I3own.
25.
Commence a cooldown to 25.
Maintain Hot Standby.
~
cold shutdown if any ONE Return to Step 12.
of the following occur u.
e Both CST levels lower to less than 340,000
'N gal (66%) as read on:
~'
s If NOT Control Room fires e
LI-5101A for CST-1 e
LI-5104A for CST-2 e
If Control Room fires e
LI-5100 for CST-1 e
LI-5115 for CST-2
~
e PRZR lev'el can NOT be controlled less tlian 85%.
Cooldown is achieved by continsfEg following steps, z
x,/
9
FROCLDURE No.
L E vi$10N PAGE No VECP 18038-1 10 27 of 56
(
)
ACTION /KIPECTED RESPONSE RESPONSE NOT OBTAINED 26.
Borate the RCS to Cold Shutdown Xenon-Free concentrations
- a. Determine required RCS shutdown margin using Attachment D.
- b. Determine actual RCS
- b. Go to Step 27.
shutdova wargin using 14005-1, SHUTDOWN MARGIN CALCULATIONS -
LESS TRAN REQUIRED.
- c. Start Boric Acid Transfer Pump on Panel A or Panel B.
9
- d. Open Emergency
- d. IP emergency boration Boration Valvor
. path NOT available
)
M[EN sElft CCP suction J
e HV-8104 - Panel A tbnIWST to borate RCS:
-OR-Open LV-ll2D on Panel A or LV-ll2E on Panel B.
e HV-8439 - Panel B.
- e. Terminate boration when required shutdown margin is reached or PR2R level reaches 85%.
~
27.
IF RCP 1 or 4 running TREN slightly epen one PRZR spray vdve to epalize boron between RG and PRZR.
CAUTION Train B is the preferable charging train when operating
<y from the shutdown panel, if a Control Room fire.
)
28.
Raise PRZR level to about 70% using control established in Step IG.
PMoCEDU t No.
LEVI 5loN PAQs No.
VEGP 18038-1 10 20 of 56 0'
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Pressurizer heaters may be cycled as necessary to stabilize pressure.
29.
Turn off all PR2R heaters
- a. Locally open e
1NB08 - Brkr 12 (Control Bldg. RB-50) e INB09 - Brkr 12 (Centrol Bldg. R3-50)
- b. Turn off heaters e
HS-10469B Panel A
' M' 1
e HS-104705 Panel B t
30.
Open SGARVa to establish 30.
Locally open SGARVs to a 50'F/hr RCS cooldown establish 50*F/hr RCS 1
rate on the SGs which are cooldown rate using providad with AFW flow.
Attachment G.
-OR-IF a Control Room fire.
TREN locally open SGARVs M 010 and PV-3020 to establish 50*F/hr RCS cooldown rate using:
e Attachment G; Ubcal Operation Of The SG Atmospheric-Relief Valves.
~~
e 5-20 mA power supply to initiate Attachment J.
Fire Emergency Operation of SGARVs-From Shutdown Panel PSDB.
70M45,
2
_.. -.~
. ~. -
a PMOCEDURE NO.
HEVi$loN PAGE No.
VEGP 18038-1 10 29 of 56 O
v ACTION / EXPECTED RESPONSE
_ RESPONSE _ NOT OBTAI!ED 31.
Using PRZR spray 31.
IF letdown is in service, depressurize RCS by Tp~en CVCS Auxiliary Spray using Recosmnend Heat-up/
HV-8145.
Cooldown Path *25'F curve on Attachment F.
IF letdown is out of service, TREN use one PRZR PORV.
IF PRZR PORVs out of service, TREN close 1AD12-03 and TEDT2-03 Control Bldg. Rooms RB-52 and RB-47 (if closed for CR fire)
AND THEN dse Rx Head Ven'es.
32.
Adjust AFW flow as 32.
Locally operate AFW p6mptand required to maintain SG throttle valves to control i
WR level - 65% to 70I SG 1evel using Attachment A.
using:
)
Train A Train B e
HV-5139 e
HV-5134 e
HV-5137 e
HV-5132 33.
Adjust charging flow to maintain PRZR level between 50% and 70%.
34.
Monitor and document cooldown using Attachments E and F at least every 30 minutes.
'(Convert F1ZR pressure to suturation temperature using Attachment F and calculate subcooling using Attachment E.)
L 1
l'
PROCEDURE NO, LEVISION PAGE NO.
VIGP 18038-1 10 30 of 56
,n.,
(d)
ACTIO!(/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 35.
At RCS pressure of 1970 psig
- a. Block PRZR pressure SI:
e HS-40012B - Panel A e
HS-40013B - Panel B
- b. Block Steamline Pressure SI:
e HS-40068B - Panel A e
HS-40069B - Panel B NOTE
.u, RCP 4 or RCP 1 should be run preferably to provide normal PRZR sprays.
()
36.
At RCS temperature of V
450'F, reduce running RCPs to two:
- a. Verify RCPs 1 and 4 -
- a. Go to step 37.
RITNNING
- b. Stop RCP 2 and 3
- 9 8
e 1
("'
N., -l I
~
ROCEDUAE Nd.
REvlSION P AGE, No.
VEGP 18038-1 10 31 of 56 O
ACTIOff/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Power may need to be restored to HV-0943A and B by closing breakers 1AD12-03 and 1BD12-03 (Control Building RB-52 and RB-47) to vent the accumulators.
37.
Stabilize RCS pressure at 950 psign
- a. Vent accurm;'stors by opening the following:
Train A o
HV-8875A e
HV-8875B e
HV-8875C 9-e HV-8875D e
HV-0943A
- OR -
Train B e
HV-8875E e
HV-8875F e
HV-8875G e
HV-8875H e
HV-0943B 38.
Continue cooldown using sprays and,SGARVs:
- a. Stabilize RCS pressure at 165 psig.
b'. Stabilize RCS temperature at less than 350*F.
39.
Rackout the breaker for the non-operating CCP.
O e
Train A, CCP 1AA02 Brkr 13
- OR -
~
e Train B, CCP 1BA03 Brkr 13
l PROCEDURW NO.
R EVISloN PAGE NO
~
VEGP 18038-1 10 32 of 56 3
i,
)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 40.
Rack out the breaker for both SIPS:
e Train A SIP 1AA02 Brkr 16 e
Train B SIP 1BA03 Brkr 17 NOTE RCP 4~ or RCP 1 should be run preferably to provide normal PRZR sprays.
41.. Stop all but one RCP.
O i
42.
Locally ensure HV-8804A 42.
Locall
/
)
and HV-8804B are SHUT bus y open Breaker 5 on
~^
1ABB and 1BBB,
/
(located in RHR Ex Rooms THEN locally shut HV-8804A RC-90 and RC-91).
and HV-8804B.
THEN open Breaker 5 on bus - 1ABB and 1BBB (located in Aux. Bld Rooms Ril8 and Ril6)g.
43.
Ensure RHR vent valves HV-10465 and HV-10466 are SHUT by opening Breaker 8 on IND31.
.(located in Control Bldg. Room RB-53) 44.
Verify two CCW pumas.
44.
Start two CCW pumps.
RUNNING.
(Prefera)1y on Train'B.)
45.
Verify two NSCW pug s 45.
Start two NSCW pumps.
RUNNING.
(Preferably on Train B.)
Verify CBCP XSF Chillers
/
running on operating NSCW i
train.
4 PRoCEDU E No.
t EVISloN PAGE No.
VECP 18038-1 10 33 of 56
' )
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 46.
Start NSCW cooling t.ower fan as needed to support RCS cooldown.
47.
Ensure NSCW tower valves 47.
Manually open valves.
KV-1668A on Panel A and (located in NSCW towers)
HV-1669A on Panel B -
OPEN 6
v
=~e 6
4 O e
. RoCEDU E No.
GEVISION PAGE No.
VEGP 18038-1 10 34 of 56 O
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION The RHR Loop 1 and Loop 4 Inlet Isolations (HV8701 A, 8701B, 8702A, 8702B) will NOT auto close on high RCS pressure af ter control is transferred to the shutdown panels.
NOTE When operating from the shutdown panels. Train B is the preferable RHR train.
t 48.
Establish one train of RHR:
48.
If any preferred RHR train
>)
equipment cannot be placed in service, repeat Step 48 to place alternate train RHR in service.
IF no RHR. train can be placed in service, verify RCP running or maintain natural circulation as in Step 18 RNO.
Continue attempts to establish RHR;and go to Step 49.
- a. Place RHR Loop Inlet Isolation inverters in service by initiating 134051,125V DC 1E ELECTRICAL DISTRIBUTION SYSTEM:
e 1DDlI6 - Train B (Control Bldg. RB-48) e ICD 115 - Train A
()
(Control Bldg. RB-55)
F AOCEDURE No AEVi$loN PAGE No.
VEGP 18038-1 10 35 of 56 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Close inverter AC output breakers e
IDD1I6 - Train B e
ICD 1I5 - Train A
- c. Close RHR isolation starter input breaker.
e HV-8702A - Train B e
HV-8701B - Train A
- d. Unlock and close RHR isolation valve breaker:
(In Control Bldg. Room RA-77):
e 1BBE-13 Train B e
1BBE-13 Train B (In Control Bldg. Room RB-79):
-x
')
e 1ABE-15 Train A e
1ABE-15 Train A
- e. Shut RHR Heat Exchanger Outlet e' HV-0607 - Train B e
HV-0606 - Train A
- f. Shut RER Heat Exchanger Bypass e
FV-0619 - Train B e
FV-0618 - Train A
4 IW-88125 - Train B e
HV-681.2A - Train A
- h. Ensure RHR to Cold Leg
- h. Transfer control and Isolation open open the valves, a
KV-8809B - Train B
/, ~
e HV-8809A - Train A i
- i. Open RHR Hot Leg Suction:
i e
HV-8702A - Train B
~
e HV-8702B - Train B e
HV-8701A - Train A e
HV-8701B - Train A
PRocEDumtNo.
r4Vl54cN PAGE No.
VEGp 18038-1 10 36 of 56 ACTIO!(/ EXPECTED RESPONSE RESPONSE NOT OBTAINED J. Start the RHR pump on the selected train,
- k. Slowly adjust RHR heat
- k. IF RHR pump flow exchanger bypass to Tiidication in NOT establish a flow rate established, of 3000 gpm THEN place THEN stop the applicable in AUTO E pump and place other train in service by e
FV-0619 - Train B returning to Step 48.
e FV-0618 - Train A IF RHR flow rate can NOT lid controlled less than 4500 gpmi THEN stop the app'e.other licable-RHK'~ pump,and plac train in service'by returning 'to Step 48. -
A NOTE It may be necessary to stop RHR pump before throttling RHR discharge valves.
1.
Slowly adjust RHR heat
- 1. IF instrument air is NOT exchanger outlet to livailable establish a 50*F/hr RCS THEN control cooldown rate cooldown rate.
Iif Tocall throttling RHR e
HV-607 - Train B e
HV-606.- Train A e
1-1205-U6-020 - Train B e
1-1205-U6.019 - Train A (located outside RHR Hx rooms in Aux. Bldg.
Rooms RC-92 and RC-39)
-OR-IF Control Room fire, TREN locally isolate and bTeid off air supply to HV-0607 and FV-0619 in RHR B Pump Room, O
AND THEN control cooldown by throttling 1-1205-U6-020 (outside RHR Ex Room in Aux. Bldg. Room-RC-89).
j 1
l
(
PROCEDU.sE No.
GEVISION PAGE No J
VEGP 18038-1 10
'37 of 56 ACTI
/EIPECTED RESPONSE RESPONSE NOT OBTAI ED CAUTION Do NOT attempt to take RCS solid from the shutdown panaTi.
~
49.
IF PR2R level rises to
~~greater than 881 THENS
- a. IF one train of RHR in
- a. IF RHR not in service.;
service, stop the last do not stop RCP.
i RCP.
Continue itith Step 49b.-
- b. Stop the CCP.
- c. Shut letdown isolation valves e
LV-460 - Panel'A e
LV-459 - Panel A
- d. Shut charging isolation valves e
HV-8147 - Panel B e
HV-8146 - Panel A r
e I
i O
l
PAoCEDU E No.
LEVISioN Act f40 VEGP 18038-1 10 38 of 56 i
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 50.
IP a Control Room fire and E the discretion of the Unit Shift Supervisor, THEN prevent spurious actions.
- a. Verify TV-12725 is -
- a. Open TV-12725 by OPEN.
(located in initiating Attachment I, Control Eldg. Room RBe62)
Non-periodic Operation of 1-TV-12725.
- b. IF CBCR ESF Chiller Eom temperature rises to an uncomfortable
~
- level, THEN provide it temporary ventilation.
- c. IF Train B Auxiliary
^'
IGiilay Room (Control Bldg.
Room 223) temperature
~~)
rises to an uncomfortable
- level, THEN provide temporary ventilation to Room 223.
~
n.,
\\___/
PROCEDV,[NO.
L(yl$10N p;Gg Ng VEGP 18038-1 10 39 of 56 7-
)
ACTIOff/ EXPECTED RESPONSE RESPollSE NOT OBTAINED NOTE Power may need to be restored by closing Breakers 1AD12-03 and/or 1BD12-03 in Control Building Rooms RB-52 and RB-47 to establish safety grade letdoun.
51.
IF PRZR level rises to gieater than 88% with charging and letdown out of service.
THEN open the following reactor head vent valves until level lowers to less than 881:
Train A e
HV-8095A e
HV-8096A e
HV-0442A
, )
-OR-Train B e
HV-8095B e
HV-8096B e
HV-0442B 52.
Maintain the following:
e RCS pressure -
approximately 350 psig.
~
RCh tamaerature - less e
,,than 20i)'F.
e Bubble in PR2R.
53.
When access to the Control Room is regained, establish communications between the Shutdown Panels and Main Control m)
Room.
PAoCEDU ENo.
L.EVIStoN PAGE #40 VEGP 18038-1 10 40 of 56 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE If SGFPTs are not reset, an FWI actuation will occur.
54 Reset SGFPT A and D at the Main Control Board.
55.
Check that there aro NO 55.
IP an ESFAS actuation ESFAS actuation signals signal is present, present.
THEN reset condition and actiiation prior to transfer.
NOTE Prior to transferring switches and controls frod'the shutdown panel to the Main Control Room panel, switch positions should be verified and controller errors should be nulled between the control stations, i
\\
J 56.
Transfer controls back to Main Control Room while initiating 11510-1, REMOTE SHUTDOWN PANEL LINEUP.
57.
At the Unit Shift Supervisor's discretion, restore any previously altered equipment back to normal configuration.
58.
Ac.the Unit' Shift Supervisor'c discretion, 16ftiata the appropriate procedure.
END OF PROCEDURE T'tXT l
(-
l w/
PMOGEDURE No.
A E Vi$10N PAGE NO VEGP 18038-1 10 41 of 56
)
Sheet 1 of 2 ATTACHMENT A TURBINE DRIVEN AFW Pt.'MP OPERATION FROM SHUTDOWN PANEL C CAUTION The TDAFW pump steam supply valve. HV-5106, will not automatically open on a pump start signal after control has been transferred to the Shutdown Panel.
A.1 STARTING TDAFV PUMP A.1.1 TRANSFER control of the TDAFW pump steam supply isolation valves, HV-3009 and HV-3019 to LOCAL.
A.l.2 ENSURE at least one steam supply isolation valve is open.
A.1.3 TRANSFER control of the TDAFV Pump Room Outside Air Damper,
("')
HV-12010 to LOCAL.
v A.l.4 ENABLE differential pressure controller PDIC-5180B by placing transfer switch HS-5180 in LOCAL.
A.I.5 TRANSFER control of the TDAW Pump AFW Throttle Valves IN-5120 HV-5122, HV-5125 and HV-5127 to LOCAL.
A.1.6 ENSURE TDAW pump Trip / Throttle Valve PV-15129 is reset by verifying the motor operator is OPEN and the valve is latched and OPEN.
A.l.7 ENSURE. differential pressure controller PDIC-5180B is in AUTO.
l A.l.8 START the TDAW pump by placing HS-5106C in LOCAL and
. opening HV-5106.
A.1.9 VERIFT that pump speed and discharge pressure begin rising.
NOTE l
Differential pressure controller PDIC-5180B will attempt to maintain a fixed differential pressure of 500-600 paid
-]
between the TDAW pump turbine steam supply pressure and uj the pump discharge pressure by raising or lowering turbine speed as steam pressure varies with RCS temperature.
A.l.10 MONITOR AW flow to each SG usir.g FI-5150C, FI-5151C, FI-5152C and FI-5153C.
PF40CEDU~.E No HEvitlON WAGE No VEGP 18038-1 10 42 of 56
~
(
')
Sheet 2 of 2 ATTACHMENT A TURBINE DRIVEN AW PUMP OPERATION FROM SHUTDOWN PANEL C A.1.11 MONITOR SG levels and adjust TDAW pump AW Throttle Valves as necessary to maintain SG WR level - 65% to 70%.
A.2 STOPPING TDAW PUMP A.2.1 TRANSFER control of ALL TDAW pump and valve controls to LOCAL.
A.2.2 PLACE the TDAFW Pump Speed Controller PDIC-51808 in MANUAL and REDUCE turbine speed to 1535 rpm.
A.2.3 TRIP the pump by placing HS-15111B in CLOSE. -
A.2.4 CLOSE the Steam Supply Isolation Valve HV-5106.
A.2.5 When TDAW pu=p reaches 500 rpm, fully open all TDAFW pt=p '
AFV Throttle Valves.
h
'x END OF ATTACHMENT A 9
4 9 g S
emp
/**-
U sM
PROCEDURE No.
REVISION PAGE No VEGP 18038-1 10 43 of 56 O
Sheet 1 of 3 ATTACHMENT B STARTING AND PLACING DIESEL GENERATOR A(B)
ON A DEAD BUS FROM OUTSIDE THE CONTROL ROOM B.1.
ESTABLISH communications between the diesel generator and affected IE'4ky bus.
At the Generator Control Panel PDG1 (3).
B.2.
RESET lockout relays A, B, C if required.
B.3.
PIACE Local / Remote Switch in LOCAL:
e HS-4516 (4517) c
~
B.4.
IF tripped, THEN reset control power breakers on front of engine control panel.
B.5, PLACE Unit / Parallel switch HS-4414A (4452A) in UNIT.
B.6.
. ALERT personnel in the vicinity that the diesel generator is O
starting.
B.7.
DEPRESS Manual Start pushbutton HS-4569A (4570A).
B.8.
OBSERVE the followings
- a. Red STARTING lamp energizes.
- b. Red SHUTDOWN SYSTEM ACTIVE lamp energizes,
- c. Starting air is admitted to cylinders and engine begins to i
roll.
- d. Red RUNNING lamp energizes when engine speed'r'eaches 200 rpm.
- e. Blue READY TO LOAD lamp energizes when engine speed reaches 400 rpm.
- f. Generator field flashes and generator voltage raises to 3750-4300 volts.
B.9.-
CONTROL generator voltage at 4kV using HS-4488A (4494A).
B.10.
CONTROL generator frequency at 60 Hz using HS-4518A (4519A).
O
~ - -, -. - -. - ~. -... - -. -..,. -...... -. -,.
l PROCEDURE No.
R EVISioN PAGE No.
VEGP 18038-1 10 44 of 56 f))
f Sheet 2 of 3 ATTACHMENT B B.11.
At the 1E 4kV bus local control panels 1AA02-00 (1BA03-00),
- b. TRANSFER control to LOCAL and CLOSE DIESEL GEN BRYa IAA02-19 (1BA03-19).
B.12.
At the Remote Shutdown Panels:
START at least one Nuclear Service Water pump on the a.
affected bus.
~
- b. START AFW pumps on the affected bus.
B.13.
At the 1E 4kV bus local control panels:
- a. TRANSTER control to LOCAL and CLOSE the fol' lowing Sply IDR Brkrs:
I e
1AA02-10 (1BA03-06) e 1AA02-20 (1BA03-04) e IAAr,2-21 (1BA03-09) e 1AA02-22 (1BA03-18)
B.14.
At 480V AC MCC INBI(INBO), CHECK the following:
- a. The Generator Space Heater red indicating lamp is OFF,
- b. The Jacket Water Circulating Pump green indicating lamp is ON,
- c. The Lube Oil Circulating Pump green indicating ~, lamp is ON.
em g/
PAoCEDU. E No.
GEVISION WAGE No.
VEGP 18038-1 10 45 of 56 c'3 Sheet 3 of 3
_/
ATTACHMEfC B B.15.
CHECK the f'ollowing parameters af ter the engine has been operating for several minutes:
- a. Engine oil pressure stabilizes berween 50 and 55 psig,
- b. Turbocharger oil pressure stabilizes between 20 and 25
- poig,
- c. Jacket water pressure stabilizes between 10 and 30 psig,
- d. Fuel oil pressure stabilizes between 20 and 30 psig,
- f. Generator bearing oil rings are turning freely.
B.16.
Periodically VERIFY operation of the Fuel Oti.?ransfer P' mps'.
u If A train transfer pump (s) is not operating properly and is required, 27579-C, EMERGENCY DIESEL GENERATOR FUEL OIL PUMP CONTROL CIRCUIT EMERGENCY may be used to provide guidance in
()
bypassing Control Room circuitry.
~'
B.17.
VERIFY associated Diesel Generator Room Fan is running or CLOSE Supply Breaker LAB 04-01 in Control Building RB-76 (lBB07-01 in Control Building RB-61).
END OF ATTACIDR'.irr B
~:. ~.
~\\
N._,/
10M41
l PROCEDURE NO.
REVISION PAGE NO VEGP 18038-1 10 46 of 56 0
Sheet 1 of 1 ATTACHMENT C REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (MODE 4 WITH AT LEAST ONE RCP RUlmING) 5.0e AM i
ACCEPTARE OrtRATING REGION
~
O 1-s y
l~
m OrtRATING R.000N 0.04 g, egg age 1200 M
M N
RCS DORON CONCENTRATION isemi O
PROCEDue.E NO.
EsEviSION PAGE NO.
VEGP 18038-1 10 47 of 56 Sheet 1 of 1 ATTACIDfENT D
~
REQUIRED SHUTDOWN MARGIN FOR HODE 5 (HODE 4 LIITH NO RCP's RUNNING) am i
j uses.4m ACCEPTA4LE 4.80 OPERATM80 REGION f
' fi g LN A
j ROGUIR00 9477D0114 IAAAGUI-
/
l 3.89 OPERATICII 1.00 R800010 Weg,1.8W g
+
8 4ES 889 1308 1833 3333 3 egg RCS 30100110000CEftfRATN3II bosni O
l l
PROCEDURE NO, REVISION PAGE NO.
VEGP 18038-1 10 48 of 56 o) -
Sheet 1 of 1 i
s ATTACHMENT E RCS/PRZR TEMPERATURE AND PRESSURE DATA r
PR2R SUBC00 LING =
TIME PRESS SAT TEMP RCS TEMP SAT TEMP RCS TS{P
' t.
Ccapleted Signature Date/ Time Reviewed Signature Date/ Time Comments
./
M m.__
. ~ -.
PROCEOURE NO.
REVISION PAGE NO.
VEGP 18038-1 10 49 of 56 O
Sheet 1 of 1 ATTACHMENT F RCS 3ESSl"EM3EWll_M"S 2400.
l 22 lEGA00ED W / 3 PMH +- 25 T- --- - ----
-tI
- r 200E 2 -
(
5120 PSC
= >[
180E
/
w
/
- 1 n
~~
0 40E Y
)
~~
1
~~
u ja ggggg gggg t
)
e 120E 5
f l
[
1000y 2
~
e r
p o
E y:
- MM
>}
I m ;
w.
9 l-
- INIF k
50fSWC00ED
[
~~
L
/
mamm N
s/
~j
.O 1
11111111111111ll1lllllllll111lll11111111ll11lll11Ill111lll11ll1111111, 1
0-100 200 300 400 500 600-700-ES1DFUWW M m
PAoCEDU.,E No.
r EVISloN PAGE No.
VEGP 18038-1 10 50 of 56
()
Sheet 1 of 3 ATTACHMENT G LOCAL OPERA' ION OF THE STEAM GENERATOR ATMOSPHERIC T
RELIEF VALVES Gl.
OPEN the breaker for the Hydraulic Operator Pump of the Atmospheric Relief Valvo (ARV) intended to be locally operated.
SG1 1PV-3000 1 ABB-25 (Aux. Bldg., Room 118)
SG2 1PV-3010 1BBB-25 (Aux. Bldg., Room 116)
SG3 1PV-3020 1BBB-26 (Aux. Bldg., Boom 116)
SG4 1FV-3030 1ABB-26 (Aux. Bldg., Room 118) 3
'"%BLISH COMMUNICATIONS between the Shutdown panels and the.
Steam Valve Room ARV Local Hand Pump Station.
-;m
'E the Local Hand Pump Station in STANDBY by performing 0
following steps:
9 CHECK level in hydraulic fluid reservoir, 1
~,
b.
POSITION Selector Valve 2 to NEUTRAL (Valve handle will
()
point directly away from the reservoir),
CLOSE the hand pump bleed off valve using the slotted c.
end of the ptmp handle, d.
STROKE hand pump several times to check free movement, e.
CLOSE the Reservoir Inlet Valve llA, f.
OPEN the Accumulator Dump Pilot Supply velve 11B.
g.
"TROKE hand pump until Gauge 8 reada 1000 to' 1500 psig for approximately 1 minute, NOTE Maintaining this pressure may be accomplished by applying continuous force downward on the pump handle while monitoring pressure, h.
OPEN the Reservoir Inlet Valve, llA and allow the pressure on Gauge 8 to drop to O psig,
,e 1.
CLOSE valve llB, j.
CLOSE valve llA.
PAoCEDU.;E No.
7;EVi$loN PAGE No.
VEGP 18038-1 10 51 of 56
)
Sheet 2 of 3 ATTACHMENT G G4.
When directed by the Shutdown panels, LOCALLY POSITION the ARV by performing the following applicable steps:
a.
To jack valve in the OPEN direction:
(1)
Shift the Selector Valve 2 to the OPEN position, (2)
STROKE the hand pump until the desired valve position (as determined by the Shutdown panels) is
- obtained, (3)
SHIFT the Selector Valve 2 back to the NEUTRAL position.
b.
To jack valve in the CLOSE direction:
(1)
SHIFT the Selector Valve 2 to the CLOSE, position',..
(2)
STROKE the hand pucp until the desired valve position (as determined by the Shutdown panels) is r'
obtained,
L J
(3)
SHIFT the Se1.ector Valve 2 back to the NEUTRAL position.
G5.
When it is desired to TRANSFER CONTROL of the ARV back to the Shutdown panels, perform the following steps I
NOTE It may be desirable to control Reactor Coolant System temperature with one of the other ARVs while re-establishing control of the locally operated ARV to the Shutdown Panela.
a.. At.the ARV Local Hand Pump Station:
(1)
POSITION the Selector Valve 2 to the Neutral
- position, (2)
OPEN the Reservoir Inlet Valve llA, (3)
OPEN the hand pump bleed-off valve using the
<~N slotted end of the pump handle.
i a
M 9
===~%mma iii-
PROCEDURE No.
REVISloN PAGE No.
VEGP 18038-1 10 52 of 56
(')M
\\_
Sheet 3 of 3 ATTACHMENT G b.
On the Shutdown panels, ADJUST the ARV controller IPIC-3000B (3010B, 3020B, 3030B) for MINIMUM FLOW, CLOSE the breaker to supply power to the ARV hydraulic c.
pump opened in Step Gl.
d.
ADJUST the ARV controller to maintain Reactor Coolant System temperature as : equired.
G6.
RETURN to Step in effect.
O END OF ATTACHMENT G
.~,
%J e
O v
o PRoCEDU,-;E No.
REVISloN PAGE No.
VEGP 18038-1 10 53 of 56
,O C)
~'
Sheet 1 of 2 ATTACHMENT H 9
ESTABLISHING CHARGING WITHOUT INSTRUMENT AIR H.1. Establish Charging With Train A Emergency Bus Energized:
- 1. Verify Train A normal miniflow isolation valves - OPEN:
e HV-8111A e
HV-8110
- 2. Verify Train A CCP - RUNNING.
- 3. Verify Train A charging isolation valves - OPEN:
e HV-8116 e
HV-190A w.
- 4. Shut the following charging isolation valves: '
l e
HV-84 85A (O
e HV-8106 V
- 5. Dispatch local operators to do the followings
- a. Verify - OPEN 1-HV-8105.
- b. Maintain 8 to 13 gpm seal injection flow by throttling OPEN 1-1208-U6-152.
NOTE If breaker 1AD12-03 was tripped, it must be reset' prior to operating,HV-190A.
~
- 6. Maintain desired charging flow using HV-190A.
\\._,)
o PAOCEDU..E NO.
7;EVISION PAGE NO.
VEGP 18038-1 10 54 of 56
)
Sheet 2 of 2
~
ATTACHMENT H (Cont'd.)
H.2. Establish Charging With Train B Emergency Bus Energized:
- 1. Verify Train B alternate miniflow isolation valves - OPEN:
e HV-8111B e
HV-6110
- 2. Verify Train E CCP - RUNNING.
- 3. Verify Train B charging isolation valve HV-190B - OPEN.
- 4. Verify Train B BIT outlet isolation valve HV-8801B - OPEN.
- 5. Shut the following charging isolation valves:
e HV-8438 e
HV-8485B y
- 6. Dispatch local operators to do the following:
,,);
Maintain 8 to 13 gpm seal injection flow by throttling OPEN 1-1208-U6-151.
NOTE If breaker 1BD12-03 was tripped, it must be reset prior to operating HV-190B.
- 7. Maintain desired charging flow using HV-190B.
~.
O END OF ATTACHMENT H
~.
_/*~~*
W
o PAoCEDU..E NO.
LEVISION PAGE NO VEGP 18038-1 10 55 of 56 c
)
Sheet 1 of 1
~
ATTACEMENT I NON-PERIODIC OPERATION OF 1-TV-12725 NOTES
- a. Manual operation of these valves is accomplished by positioning the 4-way Selector Valve and operating the Hand Pump to cycle the valve.
- b. This valve serves the subsystem Control Building Safety Features Electrical Equipment Room Train B.
I.1. OPEN the Power Supply Breaker for the following' valve VALVE BREAKER MCC LOCATION 9
1-TV-12725 IBYAl-22 IBBA CB R-322 I.2. REMOVE the small Cover Plate from the side of the Valve Cover.
NOTE The 4-way Selector Valve is located directly below the Hand Pump.
I.3. POSITION the 4-vay Selector Valve as required to open or close the valve.
I.4. PUMP the Hand Pump until the valve completely strokes.
I.5. POSITION the 4-way Selector Valve to the center position.
I.6. REPLACK the side cover on the Valve Cover.
O END OF ATTACHMENT I
%~_c' e
9 P,.oCEDU.4E No.
REVI5 ion PAGE No.
VEGP 18038-1 10 56 of 56
[)
Sheet 1 of 1
~
ATTACKHENT J FIRE EMERGENCi OPERATION OF SGARVS FROM SHUTDOWN PANEL PSDB J.l. CONTACT the I&C Shop and DIRECT them to send an I&C Technician to Panel PSDB.
The technician should bring a Transmation Digital Calibrator, Model 1040 or equivalent and test leads 3
suitable to plug in banana jack plugs in PSDB and the Transmation.
NOTE l
Steam Generator Atmospheric Relief Valves for Steam Generators 2 and 3 (1-PV-3010, 3020) are operated remotely from Remote Shutdown Panel PSDB.
These ARVs have the capability to be controlled with a portable temporary current source.
J.2. POSITION 1-HS-3010A (3020A) to the FIRE EMERGENCY position at the PSDB.
/~(T J.3. CONNECT a 4-20 mA current signal via banana jack plugs inside y
the PSDB for the ARV to be operated.
(Use Transmation Digit.
Calibrator, Model 1040, or equivalent rupplied by the I&C Department.)
J.4. Manually ADJUST the current signal to the valve to maintain Reactor Coolant System temperature as required.
J.5. Upon completion if the Fire Emergency Operation, PERFORM the followings independent verification required:
- a. Manually ADJUST the current signal to CLOSE the ARV being
- operated,
- b. DISCONNECT the Transmation Calibrator from inside the PSDB for the ARV being operated, c'.. POSITION 1-HS-3010A (3020A) to the NORMAL position at the PSDB.
fm.
END OF ATTAC1 MENT J v
f
(
Wartcar lyss )
RADIATION MONITORS STATUS
(
')
Immediately before the event:
V Channels inoperable from daily report ARE2532A & B Fuel Handling Bldg. Exhaust System Isolation IRE 0017A CCW Train A
- Admin 1RE0020A NSCW Train A
- Admin IRE 1950 ACCW Pump Inlet 1RE48000 CYCS Letdown Monitor 1RE0024 A & B Select Component Cubicle Monitor 1RE12839X SJAE & Stm Packing Exhaust Rad Monitor Immediately after the event during loss of power to the 1-E busses:
Channels operable for monitoring only (powered from DC source through an inverter).
1RE0002 Area Monitors Containment - Operating Level
- [d IRE 0003 Area Monitors Containment - Operating Level 1RE0005 Area Monitors Containment - Operating Level 1RE0006 Area Monitors Containment - Operating Level ARE2533 A & B FHB Exhaust System Isolation 1RE12116 Main Control Room Outside Air Intake 1RE12117 Main Control Room Outside Air Intake IRE 2562 A, B, C Containment Atmosphere IRE 13119, 13120 Main Steam Live Monitors 13121, 13122 Instruments read out in the Control Room on the Safety Related Display Console (SDRC).
,y w/
-)
O.
How do we identify and assess safety issues in the planning phase of outage preparation?
The Outage Planning Group collects the information on the work to be performed and using the Tech Specs, Limiting Conditions of Operation, industry experience, and operability requirements imposed either by procedures or the Operations Department for guidance, lays out a sequence of work activities.
Normally, Engineering, Chemistry, Heal th Physics, and Radwaste will provide input to operability requirements, not necessarily spelled out in procedures, to aid the initial sequencing of work.
The draft schedule is reviewed by all departments and comments provided to the Outage Planning Group.
Significant comments or concerns are discussed at the Outage Planning Meetings where all depa rtmen ts a re represented.
Action Items are generated out of the Outage Planning Meeting to resolve the concerns.
The progress on the significant issues is discussed at the Outage Planning Meetings until resolution is reached.
The resolution of items can take many forms.
Sometimes an Engineering evaluatian is needed; special testing may be prescribed; schedule changes can result with additions, deletions, or chcnging work sequence.
A good example of this process is the scheduling of remaining swi tchgear from service for cleaning and inspection.
First, the loads on the switchgear were determined.
Then a plan was developed whereby we would take out 1/3 of the switchgear each cycle.
Operational concerns were referred to Engineering for review.
The adequacy of these review efforts by all parties in each stage l
of schedule development is heavily dependent on the training, knowledge,
and experience of our plant s ta f f.
In addi tion to our plant s ta f f, Westinghouse reviews our NSSS work for proper sequencing, work durations, crew size, etc. and provides comments through their Site Manager.
l l
U i
f l
How do you factor industry event information into the Vogtle Outage Schedule.
My comments are restricted to how information gets xs into the Chage ScNdule, and does not include the entire process for dissemirRing industm/ event information.
Industry Event Information is received at the site and processed in accordance with Procedure 00414-C, the Operations Assessment Program.
There the information is categorized and any information involving refueling outages or work controls or anything that would offect outage activities, is sent to the Outage and Planning Manager for information and sometimes for action.
The Outage and Planning Manager then will review the information and provide copies of this infort:.ation to the Outage Scheduling Group.
Based on his initial
-essessment of the information, action items may or may not be assigned, depending upon the information at hand or the event that has taken place.
In parallel with the Scheduling Group reviewing the industry event for possible schedule _ action.
These events are also discussed in outage planning meetings where the broader scope of plant population evaluates the impact on activities such as midloop and seismic events during refueling, etc.
During the outage planning meetings actions are then. assigned _ to the -- individual departments such as, Engineering or Operations where either a
Engineering evaluation or procedural requirements from Operations or the Reactor Engineering Group are ask for to address these specific industry events.
D During the First Refueling Outage preparations an evaluation was done to use the Unit 2 Turbine Building Crane on the Unit 1 side of the
Turbino
- Building, b;ccuco of the concern for coicmic events and dropping loads onto the Control Building the electrical alignment to 1
[j')allowtakingonereserveauxiliarytransformeroutofservice, as asked t
for by the Augusta Division to change oil.
At the Outage and Planning Meetings, Resolution Items (Action Items) are assigned to various departments.
Such as, Engineering, Operations, Licenses, etc. to address the specific issue to determine if the FSAR needs to be revised, some analysis performed, whether a Tech Spec change may be appropriate, some operations Procedure changes or other changes may be appropriate.
These resolution items are tracked through to completion.
The issue dealing with the safety significance of the plant are presented to the Plant Review Board for such things as safety tO cvaluations or certain operation procedure changes, as required by Tech spec.
Once a resolution has been reached then the Outage Scheduling Group decides whether a milestone is appropriate for flagging some information in the schedule or whether it should be an activity of l
specified duration to ensure that the activity is constantly being reminded about during the outage.
An example would be safety injection pump available while nozzle dams are installed.
To ensure proper l
train availability during the IR2 Schedule, the appropriate safety injection pump was flagged in the schedule to be l.
l L
l
,. ~,
Y 1
l l
l 6vlR$Adlidid MFvli lilid Id III'lidid IIsdRdR!IdN>NTIiKdh
4 4
operable while nozzle dams were installed.
To accommodate the Gwitchgear Cleaning Program established, the operable SI Train was cpelled out by long durations, in the schedule, to ensure that they were constantly reminded that the train could not be taken out of cervice.
To ensure operstional considerations are addressed, the Operations Department reviews the schedule and verify the appropriate Tech Spec compliance issues are addressed, the appropriate operational considerations are addressed, and where necessary appropriate temporary codification plans are established to do such things as feed the cppropriate interlocks, etc.
p The Outage and Planning Department currently has a licensed SRO as the Department Manager with 9 years of nuclear plant experience.
In cddition the Scheduling Group has a supervisor who is a former NRC Certified Instructor for Plant Vogtle with over 24 years of nuclear plant experience.
In addition the Scheduling Group has a Planning Scheduling coordinator who is also a currently licensed SRO for Plant Vogtle with 10 year of nuclear plant experience.
The Section also has a Planning and Scheduling Coordinator who has extensive experience utilizing the scheduling program, Project 2 and has 9 years of nuclear plant experience, most of which has been in the outage scheduling area.
The bottom line is that the training and experience of the staff in the Outage Scheduling Group coupled with the process of disseminating information throughout the plant staff along with the processing
/i utilized in the outage planning meetings to address these significant g
issues helps to ensure that significant industry events are adequately s
cddressed and reflected in Plant Vogtle Outage Schedules.
Another mechanism that Vogtle uses to feedback pertinent information is a
Lesson Learned Program.
Throughout the outage comments are solicited as to the logic of particular work efforts, the cequence of work efforts.
In essence any particular identified problem that' would inhance the smooth operation of refueling activities captured.
During the first refueling outage several comments were received that were reflected into the scheduled changes, such as the improvement in containment access controls, the improvement in the area for Health Physics dress out trailers and access to conta.nment, the ALARA Briefing activities, and the processing of contractors in to cdequate records are maintained.
In the area of Midloop activities, evaluations were done to allow the utilization of the cross tie valve between RHR -Trains during Midloop activities to allow the Tech Spec required inspection of the cccumulator isolation check valve internals.
Some of the significant issues that have been evaluated-are; 1) the electrical alignment removing one reserve auxiliary transformer l
into service 2)
The cross tie between RHR Systems to allow the l
inspection check valve internals, 3)
Keeping a SI Pump available during the time the nozzle dams are installed, 4)
The modification to containment penetration to allow for sludge
- lancing, and 5)
The process. to using the Kelly System for deconing the reactor cavity l
during the draining down period.
l
Of course, I would like to also add that in the process of schedule development all departments receive industry experience information.
They view from their specific disciplines such as, Engineering, Operations, Maintenance, Health
- Physics, etc.
and provide comments to the schedule development.
'l 1
I I
i l
t 1
{
O YN?1"A/1"$l1."A/1"A/3'n/.1'd1.'U1'n/17x11"A'/1'El1'A N V}1 F N M Ts.r M f m]1 % M a)Tn N N M d V V
a
()[ Q3--fD RELIEF REQUEST
-(
!. )
RR-7 SYSTEM:
Safety Injection-System No. 1204 VALVE (S):
1204-U6 079, 1204-U6 080, 1204-U6 081, 1204-U6 082 CATEGORY:
AC CLASS:
1 FUNCTION:
These valves open when the downstream pressure is less than the upstream pressure which allows cold leg injection from the accumulator tanks.
QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
BASIS FOR RELIEF:
The SIS accumulator tanks are isolated from the RCS by these normally closed check valves.
Each accumulator is charged with a' nitrogen blanket of 650 psig.
This pressure is insufficient during operation to inject
- ( (_s) into the RCS.
If these valve: were to be
\\~'
exercised at cold shutdown, the contents of the tank would be dumped into the RCS at the charge pressure of 650 psig which could result in a low temperature overpressurization of the RCS.
ALTERNATE TESTING:
One of these valves will be disassembled and manually stroked at refueling on a staggered test basis.
If disassembly reveals that the valve is inoperable, the remaining valves will be disassembled.
These valves will not be disassembled and manually stroked to perform preservice testing.
A f
N, __/
5-7 REV. 1 0843n
RELIEF REQUEST
. O)
(
RR-ll SYSTEM:
Safety Injection-System No. 1204 VALVE (S):
1204-U6 083, 1204-U6 084, 1204-U6 085, 1204-U6 086 CATEGORY:
AC CLASS:
1 FUNCTION:
These valves open when the downstream pressure is less than the upstream pressure which allows cold leg injection from the accumulator tanks.
These valves also open for RHR flow.
QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
BASIS FOR RELIEF:
The SIS accumulator tanks are isolated from the RCS by these normally closed check valves.
Each accumulator is charged with a nitrogen blanket of 650 psig.
This pressure
( (f s'j is insufficient during operation to inject into the RCS.
If these valves were to be exercised at cold shutdown, the contents of the tank would be dumped into the RCS at the charge pressure of 650 psig which could result in a low temperature overpressurization of the RCS.
ALTERNATE TESTING:
One of these valves will be disassembled and manually stroked at refueling on a staggered test basis.
If disassembly reveals that the i
valve is inoperable, the remaining valves l
will be disassembled.
These valve.s will not i
be disassembled and manually stroked to perform preservice testing.
In addition, these valves will be partially stroke exercised during cold shutdown by normal flow' from the RHR pumps.
~
1v 5-11 REV. 1
- r3 1 og 3
-U IESIm StRVEY GECKLIST KR INPO SCER 86-03 IDENTIFICATICN valvt FJL l-/J M - M -e 3 3 Systemi
/.208 PbID:
1 M9811.2 c5 LSOs
/ W*/ i?u-o 29 in Manuf:
haa Vend Dqi i s/pu-o/ f y q g, ? !
Servicea AaSn (b
I)h*
V U
rm SurrABH.ITY
,;2 u'O's~ LJJJ)v,tr &
I vaiv. Type Fasc Closure Speed A
Requirements:
Variable Flow yg2 tow Press Drop Seal Tishtness
/v, Ccupare to Table 2-1 of EPRI.(K) SAT (
) UN5AT CD H NIS:
A4 cardrfATIN
,m V
' Valve Orientation:
c ri 2 Vendor Dwg/ Manual Rega'ts:
- f>,w L/.) SAT
(
) WSAT CO M NIS: eb SYS*11M 00FIGRATIN Distance to first upstrean fittirig:
2Y fo Ed
~..
, Pipe Dimmeter:
2"
- Pipe Diams:
= /2.
' Distance to first dounstrean fitt
/2 " #3 g/
Pipe Diamecurs
)"
(
4 g t.
om1 u a. 2.3. o--,
(M se
(
) msrT amiers: J O
FOR lNFORMf7l0N oy[,
T
4 2 of 3
'O DISC S'tSILITt.
Approximate Dise Full ing le Capare to EPRI F1 e
.A laaxwy" check (opens 90 with no stop) 4
(/) SAT
(
) LNSAT 02+ENTS:
4 1
m PCR VALVE Is this valve needed for system operation?
( @ YES
(
) NO If NO, inieiste Design mange to renove internals of check valve. DCP f a h (Rafer to EPRI A.G. 2.6.3).
(XHENfS:
- o INIERNAL PARIS IDCKING DEVICES t
\\'Ocupare retaining /1 of int parts to EPRI A.G.
O
.u
/7 A,M:s h
4, t
m 1
MA21RIAIS
'1he materials in the ch kec. valve are adarr=ra to prevent excessive arosian/ccerosion.
Caspare to EPRI A.G. 2.4.1.
4
'l SIZINGNeiglatflouratest.
O d
'7f 68A1 Vhoum (enlanlarad nonnal flow ve ties): /N 2 M APT Vendor apa-iFied Weins.
67 or Calculated Nieta:(fram up.I AG 2.1.1 - attadt asanpetans, references, etc.): w r Visin Vhorn
(
) SAT CGtfNTS:
( p GISAT
.O u
4
3 of 3 frx-MAINITNAM(2 HISHRY REVIDi
. Review and sumarize significant maintenance history: MN PREVENTIVE MAINITNANCE Is a change to the Preventive Mantenance Progre necessary?
(
) YES
( Y) NO See EPRI A.G. 2.5.6.
If 11709 6et'8 yes, specify IM and frequency.
CONENTS:
0 3 (44 GENERAL Oct+ENIS:
3/ Ad
[M45)oh r'ha/,d ms vec,w o+w
/
/
\\
\\
(INCWSIG4S
(
) SAT (g)UNSAT,RecommandfurtherA/EReview.
/3df7 wu.cor
= t.
(Systen Engineer) d1
- / k36$
Revisuer l Ddte (Engineerizu Supervisor)
O
1 of 3 CESIW SURVEY CHECKLIST FOR INPO SOER 86-03
_IDENTIFICATIN Valve MPL: I -/Tf- #/-M/
Systam: / 34 f, PEID:
/yyngnr g5 ISO:
/ n't -/,vi; u e -o.y Manuf:
rg7 e.co Vand Dwgi _iy/uf./ _v/7 Serytce: "AIMI. A M /A, h Rff A-a # >
v v
Tm surrAstttu valve Typ.:
g % u 38 L (k Requiremancs:
Fast closure Speed _ /l4 Variable Flow Ym low Press Drop 4/,
Seal eness W
Ccapare to Table 231 of
(
} SAT ( 9 UNSAT l ma b
}
CO H NIS:
ur yWn %. (k s.
o CRIdnwrrat
. (!
V ve Or4=ar=M = :
erea Vendor Dug /Hanual Rega'es A4 rfa
( g 5AT
(
) IM5AT ixmms -L SYS'11H 03FIGURATIGI 11 Distance to first tes fitting:
ff Pipe Dimeters
- Pipe Diams:
/7,73
- Distance to first dounstraagt fitt 7Y*
Pipe Diannese 3"
iPipe 2 %t/
CD===a application Guidelines 2.3.1 includirig (ySAT-(
) IMSAT
- annans,
+4 P
4 O
9
~
-m w
x
2 of 3 DISC STABILITY roximaca Disc Ibil les N
Campare to EMtI Figure A
learway)' check (oparm 90 vit.1 no scop) is LNSAT.
)(V ) SAT
(
LNSAT CCHMSs
& Lt-NEED FOR VALVE Is this valw needed for system operation? (
) YES
(
) NO If NO, initiate Design Gange to renova internals of check valw. DCP f M
(Rafer to EPRI A.G. 2.6.3).
y COMNIS:
mg INTDtNAL PARTS IDQtING IEVIGS
'f r'-a retainims /
of' internal parts to ERLI A.G.
- 2. 5'. 7.
( F) SAT afD y(
J.s M, l)L L.A Q. -~~ -
caeentS v
r u
MA21! RIALS
-The materials in'ths check w lve are adequate to g M excessive arosion/ corrosion.
Compare to EPRI A.G. 2.4.1.
. ( /) SAT.
(-
IEWAT
.; 02 M NIS:
m
*" ja riosenese 0 - 55 4 /#l ma Wisult (enla*1=*=d nounst flow velocities):
A-
.24/8 Vendor PtiTed % sin:
f,3 /F5 or Cale*1*tM %dn (from z.rKI 2.1.1, attach==Y=,
references, etc.):
hin Vhorst
(
) SAT (i)IAEAT amxrs 4
T')N -
L 3 og 3 MADGUWG HISTORY REVHM Review and stamariza significant maintenance history: /la PREVENTIVE MADGDWC Is a change to the Preventive Mantenance Program necessary?
( ) YES (p) NO See EPRI A.G. 2.5.6.
If yes, specify PM and frequency.
CD M NIS:
/ /209/6 6 - M1941 CE2DAL G)H!NTSs l$ Ald b h)$ <
bl.
xAY rhrk w 2s L hr, Jh a
<o hor.
U
\\h Q
~
CalQ11SICNS
< > se (yo tuse, w turth.e us s.vt 05 i 34rbr
==
mt.
(Systein Engineer) p
, N l l d C +. 3 ls<l g r
~ = vie r men (Engine.rity Supervisor)
O a
D]
l of 3 L
IESIQi SURVEY CHECKLIST KR D@O SOER 86-03 IDDRIFICATION Valve MPL
/- /2/5'- 8/ - A37 System:
/ 246 P&ID:
/ Yv/>M///
M er ~
ISO:
/ tr F -/, W g e g -/) 4 Manuf:
(as E4//7 Vand Dws:
/ WN/-3/7 Service:
'Ah (L h MS /no f W
U TYPE SUITABILITt Valve Type 3
Mb
[IT Requiremante:
Fast closure Speed A/n Variable Flow h
low Press Drop A/o Seal eness Yo em to Table 2 of
(
) SAT yX) UN5AI C3 H NIS:
I}u T >
svf.J n
% c'As v
CR1hn>TLCN
<(]~
Aalveorientation:
Nr/e Vendor Dug /Marmal Rega'ts:
//n,,,3
( W SAT
(
) UN5AT COMNIS:
a/-
A SYS11M CCNFIGRATIGE 49 Distance to first traen fitting:
3 b'd
- Pipe Dianter:
- Pipe Diams:
//. 3 <
' Distance to first doumstrean fitt One Pipe Diameter 34./6 g es t
unes 2.3.1 wwn
- 7) '"
( )""
j 9
4 9
2 of 3 DISC FZ2SILITY roximace Disc Pbli les O
pare to EPRI Figure A
leazusy" check (opena 90 vita no stop) is UNSAT.
(g) SAT
( ) INSAT COtENTS:
N h-NEED FOR VALVE Is this valve needed for system operatixxt?
W)YES
(
) NO If NO. initiate Des,ign Change to renove internals of check valve. DCP i yF (Rafer to EPRI A.G. 2.6.3).
CDefNIS: 39 INTERNAL PARIS IDQuNG DEVICES f
2 i.ipoupare retaining /1 of internal parts to EPIC. A.G.
2.5.7.- ( 4 SAT 4)
/ l)
CDHDfrS:
r1 W.4,
& b>
M_
/Ac 1)
(Od
.t e
o MAIERIALS The materials in the check valve tre adequate to prevent exqessive arosion/ corrosion. Compare to EMI A.G. 2.4.1.
( Y) SAT
( ) 445AT
) CONDirs:
SIZDIG,
(enlailmead nouns 1 flow velocitias): M-J-5/45 V= wine WN %da 5',3 F /5 or rela *1sted %dn (from AG 2.1.1, attach *e? Y =a.
references, etc.):
"f
,g_'
Mata harm
( 7)' SAT
) (IE5AT 03tefIS:
O 4
4 f) v 3 of 3 MADEENAMCE MIS'IORY REVUM Review and sunnarize significant mintenance history: //w PREVENTIVE MADHDMNCE Is a change the Pre m tive Mantenance Progr a necessary?
(
) YES
(
NO See EPRI A.G.
.5.6.
If yes, specify IH and frequency.
OttHENES:
I l'2 /A /49 -C l? M
/4 u,e./I [M T m[
QNERAL 0@H!NTS:
a x x., - p i
nana -
ver p.
o
!_ (.)
(
) SAT (K INSAT, Re,-...-d further A/E Review.
WA i J,ek
..t.
(Sy3CM W )
mm (Engi % W )
l t
P
'U l
l l
m
]
l of 3 DESIm SUP.VEY OFHLIFF FUt INPO STJt 8503 IDENrlFICATIN valve MPt.:
/ -/2tf /// 03T systani - /dd^f5 P&ID:
/ WOR ///
Bf ISO:
r/ xv-oN-Wr-Os/
Hanutt
'G>
Gstn Vand s
iMut/~ 36 y Service:
' 4// / G A.
///5
/~
v i
TYPE SUITABILI1Y Valve Type:
3
/ n d8 Requiranents:
Fast Closure Speed
/he Variable Flow ya low Press Drop 4/o Seal eness ya2 Caspare to Table 2-hpf
(
) SAT yh L.zcrAT CO H MIS:
Il~:2%
mF A n %. C/cc -
~
)
i GtIbgATIGs
((]
alve Or4=e= rim:
Wp venaar a /x.nu.1 Rege est u,,,,,
s
(/1) SAT
) UN5AT D24ENIS:
M SYSITM CENFIGELATIGl Distece to first getream fittirg:
f2 ff /o //
,,, ': Pipe Dianneter:
~7"
- Pipe Dimes:
i r. a 5 Distance to first doomstrean fitt 7f%5/
Pipe Diammster:
3
- 2M #'7 g o. _ m. m.t - m 1 - 2.3. u - e m j
(
) Gl5AT l
nmikern
+h I
2 of 3 DISC SIABII. TTY Approximate Disc F\\s11 Opsning Angles b
Cmeare to EPRI Fi e 3-8.
A "cinatusy" check (opens 90 viti no stop) is
( f) SAT
(
) LNSAT CQtENTS:
.o t-
-l
.o:
!EED ftR VALVE Is this valve needed for system operation?
(X)YES (
) 10 If NO, initiate Daqign Change to remove internals of check valve.
DCP f Ah (Rafer to EPRI A.G. 2.6.3).
COM2 TS:,_ v7 IN1WNAL PARTS IDCKDC DEVIG_S retaining /1 of' internal parts to EPRI A.G.
O cin $rts ? 'c$$ b 'e.i -
b vcLe L)
W O
MATEk*tALS The mats 11als in the check valve are adeqwita to prevent excessive erosion / corrosion. Ccepare to EMI A.G. 2.4.1.
()() SAT
(
)
Ml A
.s
- i$mt e m,
0- 55ffa m
Winum (emim1m**d norinal flow velocities): M - 1. 5M/3' Vandw P tfied Weins
- f. 3,e/ 6 or 2
Calculated % sin (from r.aw AG Z.1.1, attach assumptit.ne.
a ferences, etc.):
4h Wein Vhots
(
) SAT
( V) lkBAT CHLW:
AV Y
h t
e e
(')
V 3 of 3 tyTDWE2 HTSKRY RE/nN Review and sumarize significant maintanarw:e histuya Mn/
PREVENnVE 1%DUT24ANCE Is a change the Preventive Mantenance Progre necessary?
i
(
) US
(
HO See EPRI A.Q
.5.6.
If yes, specify PM and frequency.
Oct M NTS: _ / /pe9 /4 T - or7+f 32DAL 03HNTSs _/4 ma k lAl nf $ Ab.hb taWa r. c san (Ls;G LJ 1%~
0//
(O QNIllSIOtS
(
) SAT
([) EtSAT, Barmmand further A/E Review.
ff/L i wWs (System Engineer) 13hif29 m
(Engineerirg SWoor) t
-r---
w
4 4
f
~%
t i
\\._/
1 of 3 DESIGI SURVEY QECE.IST FDR DUO SOER B6-03 IDENTITICATIQ1 Valve MPL: d-/.303-LN - o $3 System:
/208 P&ID:
e2xwct3irl ISO: - JK4 - / Aol-oF/ -6 4 Manuf DR Essd R Vend % :
h vARob-c1W Service:
Ady sPRA4
(_<.
\\/LV.
TYPE SUITABILT1Y 5m 4 Lt3ADEb CRaK Valve Type 3 Requirenints:
Fast Closure Speed Nb Variable Flow No few Press Drop No Su1 Tidmess NO Ccupare to Table 2-1 of EPRI ( A SAT (
) UlsAT 00 TENTS:
NONE TATIm Valve Orientation:
ORIMTAL
'~
Vendor Dwg/ Manual Regn'est ay(f z
( vi SAT
(
) UNSAT CCMf2ES:
NOM 6 SYSUM CWFIGURATION Distance to first upstrean fitting:
24 Pipe Diamatar:
J'
/ Pipe Dim s:
/a Distance to first downstrean fitting:
/A a Pipe DiamatA.
A" iPipe Diams: _
G geo mz wuc.uon cu unes 2.3.1 inciudin.
( / SAT
(
) LNSAT a n. ES:
l m
F0.1 IVO, live 0;\\' 0 \\ _Y
l
)
rO 2 of 3 DISC STABILIn Approxiste Disc Full Openin les N/41 Cmoare to EMI Figure 3-8. g lear my" check (opens 90 wit 1 no stop) is LNSAT.
(
(
) LNSAT CatfNTS:
voA NEED MR VAINE Is this valve needed for syst e operation? (DYES (
) NO If NO, initiate Design Qwige to recove internals of check valve. DCP f tVM (Rafer to EPRI A.G. 2.6.3).
CONNTS:
W A1FJ INIERNAL PAIUS IDCKING DEVIG.S e re
/1 f internal parts to EPRI A.G.
CG NENIS:
No coufbrJcNn ihl Q u GSTio s MAIERIALS J
The u terials in the check valve are adequate to prwvent exc sive erosion / corrosion.
Ccapare to EPRI A.G. 2.4.1.
(
(
) (ESAT
' CHDrIS:
A0tJE SIZING Naumal flovrate :
D - 76 GFM Vhorn (calculated normal now velocities):
O-7o63 Vendor Specified Vimin:
6 or Calculated Wiin (from t.rKI AG 2.1.1, attach aastaptions, references, etc.):. 566 6FAl thhtENf3 Wiin Vnoria
( # SAT
(
) LNSAT CO NENIS:
.]
~
_ _ -. - ~ -
i 3 of 3 l
MADm2 WEE Histt*Y REVEW Review and stannarize significant maintenance history:
triwe.
PREWNTIVE MAUm2WG Is afchange t Preventive Mantenance Progran necessary?
( VI YES
(
to See EPRI A.G. 2 6.
If yes, specify PM and frequency.
O)t G TS:
No MCATM l'M RUCt1Lb BE INITif4Tm 5fM f t AR To 11 AJ t T' es. t
/ 1 Ao n O9 4 - n % AA ).
amenAL areers:
ASSUM6 h h:
. Ol6 f 30 F4lLLl(Js DOLL LD isEit!t T bbltE. TO ROLO CSC.(Li>LTf0A3 t:
'l
~
QNLUSICNS
(
) SAT
(
(NSAT, Reconnend frJwr A/E Review, lNkk3 L [l[/
/
3 d'f
~~
o.c.
(System Engineer) 3;Yd!87
/
" Reviewer
' Date (Engineering Supervisor) t e
my v.
.y
--4.mw-
-.s 9
- c. g@m g.
--y
-e 3,g9,9.cy, gp e,my,-,r.-e--.
y-.
-. err-y--
_ _ _ = _ - - _ - -
t 4
(7 1 of 3
'w)
CESIm SURVEY CHECi3,IST IVR IhTO SOER 86-03
_itetrIFICNIRN Valve MPL: 2-1.20A - t/(3 - CM Systan:
/408 P&ID:
Moaeit ISO:
AKH- /Ab8 - <xA -o3 Manuf:
~W E ST' Vend % :
A c_,A Ans - 11.jy3 63 Service:
NMM4o C H6r.
C 9e~f < At t.co P
- f.
TYFt SUITABILITI Valve Type:
jtOIN6 CMCK \\lALil/6 Requirements:
Fast Closure Speed No Variable Flow r4o low Press Drop No Seal Ti@tness NO Ccapare to Table 2-1 of EPRL. (4 SAT (
) UNSAT COMNTS:
NNJ6 ORINFTATIM Valve Orientation:
HORl2&JTAL Vendor Dwg/Hanual Regn'es:
Hog /Z.
( 4 SAT
(
) UNSAT 00NENIS:
A)OAJS SYSITH CCIFICERATIN Distance to first tgatrean fitting:
40' Pipe Diameter:
3 (Pipe Diams:
/3, 3 d
Distance to first downstream fitt 6"
Pipe Diamatar J"
(Pipe cR gotoEPRIApplicationGui lines 2.3.1 including
(
) SAT
( vfWSAT oweurs:
N.
l
~
l
('T 2 of 3 O
DISC S* ABILITY Approximate Dise Eb11-Opening Angle N
Camare to EPRI Figure 3-8.
A "clearway", check (opens 90 vit1 no atop) is UNSAT.
(
l SAT
( vf LNSAT CafGHTS:
<e E iSt2dl(s)
NEED FOR_ VALVE Is this valve needed for systs: operation? (/YES (
) to If 10, initiate Desip Quinge to rmove internals of check valve.
DCP i N/A (Refer to EPR1 A.G. 2.6.3).
CattNES:
Hn N2. ~
DnTRRL PARTS IOCKDC LEV. ICES e re
/1 f internal parts to EPRI A.G.
' 'u 02teNis:
ALL ('ARus CAP 71V6 6V d4LVE PhDV McERIALS
'Ihe materials in the check valve are adequate to prevent excepaive erosion / corrosion. Compare to EPRI A.G. 2.4.1.
( vf SAT
(
) LNSAT CQtENTS:
NON6 SIZDU Nonnel flowrates:
C-55 6PM Vnorm (calculated nottal flow velocities):
D - R. $ FPJ,
Vendor Specified W ins 6.3 or Calculated Wda (frun EPRI AG 2.1.1, attach assuoptions,
/
references, etc.):
NA Win Vnom
(
) SAT
( W lNSAT OltfNTS:
1 (3 1 L) e
l 6
3 of 3 MAnm2WCE HISTRY REVID_'
Reviw and sminarize significant mainteunce history!
~~
Nc'sb
_l PREVD1TIVE HAWIT2 WEE Is a,4hange to the Preventive Mantenance Progr e necessary?
( tf YES
(
) 10 See EPRI A.G. 2.5.6.
If yes, specify PM and frequency.
01ters:
4 E-f - IN'504 f t/ALVG 6VERV C E f-t(FL t /6 c RTAAE GENERAL CDt G TS:
N/ALVE CA(LS
$YS ONJ r-t G, AND Flou)
R Gout 4MaJr5 1
(INCLUSICNS
/
(
) SAT
( J lESAT, Racw.wd further A/E Revis.
WM W
l ~3 A8 b'9 tvu o tor o.t.
(Syntam Enginestr)
)
va 4 Yt Nrviewer Cate (Engineering Supervisor)
.O
3, 4
4 1 of 3 CCSIm SURVEY QECKLIST IVR D'PO SCER 86-03 IDDITIFICATICN Valve MPL 2-1208-d(o- 03(o System:
/Ro8 P4tD:
h 4 D P, i i t ISO:
M+ - QCA - ooA - 63 Manuf:_,
a asT Vand Dwgi AeAAob D&1363 Service:
NoKMA L C%. Tb Its imp== r.
WPE SUITABILIW Valw Type SCOIAMr CNC-f( \\/ALVQ Requirements: Tast closure Speed No Variable Tiow eNo tow Press Drop NO Seal Tightne Ccuipare to Table 2-1 of EPRI ( v'p) SAT (__
tJo
) UrcsAT 0@ M Nrs:
NotJ6 8,0, ORIM TATIW
~
Valw Oriantation:
HORl20MTRL Vendor Dwg/ Manual Rega'ts:
4di? / 2..
( # 5AT
(
) WSAT CDMNIS:
AD/E SYSIDI ONFIGEATim u
Distance.to first tpatream fittigt lo Pipe Dianster
- Pipe Diams:
et Distance to first downstrean fitt u"
Pipe Dimastar:
J" (Pipe
- 20. to geo rm wuc.ca u ums 2.3.1 =1%
(
> sit
( <=T 03MNrs:
msu a,,
n -
e
..w w
e, e
9-
(U) 2 of 3 DISC STABII.I'Q Approximate Dise Pull-Opening Angles
-. 39 Camare to EPRI Figure 3-8.
A "cleaxwy" check (opens 90 with no stop) is thSAT.
(
) SAT
( M LKcAT CatMS:
Snf c:t t'NG)
TEED 10R VALV_E Is this valve needed for system operation? (DYES
(
) to If to, initiate Desigp Change to recove internals of check valve.
DCP i N/A (Refer to EPRI A.G. 2.6.3).
Cat m Si tdctJP.
INIUHAL PARIS LOCKDO DEVICES a re
/1 f internal parts to EPRI A.G.
CONENIS:
UAld6 BObL/
MAR RIALS The materials in the check valve are adequate to prevent excepaive erosion / corrosion. Ca pare to EPRI A.G. 2.4.1.
( vf SAT
(
) LNSAT
' QMtENIS:
/\\lON8 SIZING somal nowrates:
O - 3 5 (3 F M Vnom (calculated nomal ncu velocities):
o - a.6 F#J Vendor Specified Wrini
&3 or Calculated Wrin (from EPRI AG 2.1.1, attach asstaptions, references, etc.):
d/A
/
Vmin Vnom
(
) SAT (v1 LNSAT r
CONENIS:
!u
_ _, _ _ _ _. _ _ _ ~ _ _ _ _ - _ _
_ - -. - -. -. - - - - - - - - ' " - - - - - - - - - - - - - - - ~ - ' ' - - " - - - ' - ' - - - - - - ~
~ ~ ^ ' " ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ^ ~ ~ ~ ~
~~~~
[
3 of 3 PADIr2 NANCE HIFIORY REVIEW Review and sunnarize significant maintenance history:
~~
M9A/P-PREVD(TIVE HAU(nNANCE Is aJchange to the Preventive Mantenance Program necessary?
( W YES_
(
) NO See EPRI A.G. 2.5.6.
If yes, syecify PM and frequency.
00t efts:
i A/SPFr7' VALUE 6th=Cv' R6f:u t:LJ 44 nu TMC-r=.
GNERAL CDH2frS:
\\/ALVE iMILS 5 8. C()kiFIdir.
A ed D WLMO K de o f) M E N Cy W,r A) S.
b CXNIljSI(NS
(
) SAT
(
LNSAT, hm--id further A/E Review.
)
G Y
Nl b
i E
.e -
(System Engineer) t f
,k MU
- 4o Reviewer Ddte (Engineering Supervisor) lC l
. ~...
p 1 of 3 DESIGi SURVEY QuZXLIST FOR INPO SCER 86 03 IDDriIFICATIO4 Valve tfL: A-lM8-U b-0Y/
Systan
/408 P&ID:
byc3Tii ISO: axy - t Ao8 - 4tg - og Manuf:
wgr Vend Dqi artAAm - m A 3 Services g LT'.
C%. TD RfS trop
+
'IYPE SUITABILI_TY Valve Type SujldG OJ6CK \\/AU/s, Esquirements:
Fasc closure Speed NO Variable Flow nc tow Press Drop A o Seal Tightneps Capare to Table 2-1 of EPRI ( W SAT (_
) UN5AT CDHNTS NONE
,()
- TI" Valve Orientations
//0R/24A/TAL Vendor Dwg/Hanual Regn'es:
404/2-( vT SAT
(
) UN5AT C@H3tS:
bbN6 smm cuelamTim Distance to first tpstrem fitting:
lo#
Pipe Dimetart-f
/ Pipe Diams:
A Distance to first downstrea "itting:
- /. 0626 "
Pipe Diameter:
J" iPipe Diams:
//.35 g to EPRI Application Gui lines 2.3.1 including
(
) SAT
( glNSAT CO M NTS:
l-l V
i
1 l
2 of 3 DISC STABILITY Approximate Disc Full-Opening Angle SYe Capare to EPRI Figure 3-8.
A "clearway/tNSAT
" checlt (opens 90 viti no stop) is WSAT. / (
) SAT (t
00t4GTS:
<31M
/SiL W,T NEED FOR VALVE Is this valve needed for system opera. tion?
(
YES
(
) 10 If to, initiate Desigp Change to recove intemals of check valve. CCP i N/A (Refer to EPRI A.G. 2.6.3).
CQt errs Now INTERNAL PARTS IDCKING EEVICFJ
\\
(n.
Coupare recapting / locking of internal parts to EPRI A.G.
\\
2.5.7.
( W SAT
(
) LNSAT OCMars:
AIL P M rS (APTd B 64 \\/ALs)6 BODV MATERIALS The materials in the check valve are adequate to prevent excessive erosion / corrosion.
Coupare to EPRI A.G. 2.4.1.
( vf SAT
(
) UNSAT 00ttENTS:
NCAM SIZING Nossmi flowrates:
O-66 GFibi Vnom (calculated normal flow velocities):
O - a M FPJ Vendor Specified Wdnt
- 5. 3 or Calculated W:in (frun EPRI M 2.1.1, attach asstarq.nions, references, etc.):
M/4 Win Vnom
(
) SAT
( ((NSAT Q
CQHENTS V
_ _ _ _ _ _ _ _. _ _ _ _ _ _ - - _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - ' - - - - - ~ ~ - - - - ^ - ^ - - - ' - - - ^ - - - - - - - ' - - ^ - ^ - - - - - - - - '
. ~.. _ _ _.
-- n..
t l
3 of 3 MADm24ANCE HISTRY REVIW Review and staarize significant maintenance history:
tK&s
(
PREVENTIVE MADmNANCE Is a change to the Preventive Mantenance Progra necessary?
( v) YES
(
)
NO See EPRI A.G. 2.5.6.
If es, specify IN and frMcy.
iN5fTc7 g yAtM8 02 M NTS:
FVpN gq y gj(.,
now,e GNERAL 0GHNTS:
V4LNE CAILJ 9 15 CCIVFIG.
ANO s=wu )
Gcr kwe rJom10AL5 f
- \\
((
034CUJSICNS
(
) SAT
( vr
. kW further A/E Review.
3f28!
/l@P44
/
Evaluator
'Date (Systaan Engineer) db 4 g
((
t Reviewer
'Dkte (Engineering Supervisor)
O
)
,v-e c.,,
v.-
-.-r--.
4
.--,,-~w
,-y
,-w-..,,,,,e v
e
(
1 of 3 DESICN SURVEY CHEQ115T FDR INPO SOER 86-03 IDDITIFICATIm Valve MPL: J-l'2 43 - ()6 - ()38 system:
IA08 P&ID:
A4b8 ii I.
ISO:
JK4 - IA08 - Hb'-O Y Manuf:
W e$r Vend Dwg:
An,AAOL,- DW3fo )
2 Service:
Atr cgA.
To FACS ume 4.
TYPE SUITABILITY Valve Type SD/MS OJtVK \\/4LM6 Requirements:
Fast Closure Speed Alo Variable Flow no Ist Press Drop do Seal Ti #tnepa NO 1
Ompare to Table 2-1 of EPRJ. (A SAT (
) UN5AT 00H2f!S:
NC%
CRIdfrATIW Valve Orientation:
MORl2WTAL.
Vendor Dwg/ Manual Regn'ts:
/CR/2
( 4 SAI
(
) UNSAT 00 M NIS:
kNtb SYSUN ONMCIEATIW Distance to first upstre m fitt (o A "
Pipe Dimeter:
3" (Pi Dimns:
40 %
Distance to first downstream fit ing:
6" Pipe Dimatar:
3" (Pipe Dias:
a to EPRI Applicatiori"Ouidelines 2.3.1 including
(
) SAT
( dlNSAT aweers.
I O
-__,.,y
2 of 3 DISC STABILITY Approximate Disc Full-Opening Angle
_$W Cmpare to EIVI Figure 3-8.
A "clearvay"f WSAT, check (opens 90 wit:1 no stop) is WSAT.
(
) SAT (u
CatENTS:
6E6 5t 2ING )
NEED FOR VALVE Is this valve needed for systect operation?
( uf YES
(
) NO If NO, initiate Design mange to recove internals of check valve. DCP /
A)/4 (Refer to EPRI A.G. 2.6.3).
03MENTSt McMb DEUNAL, PAIUS ILCKING DEVICES
\\
/ locg f internal parts to EPRI A.G.
e re OWMENIS:
ALL FA W S CAPTN6 84
\\lALVE BODY.
MATERIALS
'Ihe traterials in the check valve are adequate to prevent excepsive erosion / corrosion.
Cogare to EPRI A.G. 2.4.1.
( vr SAT
(
),1NSAI CONENIS:
NON6 SIZING Nattaal flowrates:
O-J55 6PM Vnorta (calculated nornal flow velocities):
O-A. 6 FR.S,
Vendor Specified Wdn:
5,3 or Calculated Wdn (frcan EPRI, AG 2.1.1, attach assmptions, references, etc.):
rV/A
%dn Vnorm
(
) SAT
( 44NSAT
(^\\
Mt V
_ _ _ _. _ _ _ ~. _ _ _ _. _ _ _ _ _ _ _ - - - - - - - - - - _ - - - - - - - - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - - ~ - - - - - - - - - - ~ - ^ - - - ~ ~ - ~ ~
i '.
l 3 of 3 MAU @ W E RI!NDRY REVIEW Review ar.d stmmaride significant caintenance history:
NGN&
PREVENTIVE MAD E W G Is & change to the Preventive Mantenance Progran necessary?
( v1 YES
(
) to See EPRI A.G. 2.5.6.
If yes, sp)ecify PM and frequency.
CatfNIS:
itd5PEC.T VfALA d sUeN cet:th:uAl(.y Ou G%E -
conAt. ca+nxIsi il4Lve wall.(
svr CoAh:n IAAIO
- tiv d RPrn vMGM hM19hs s
O 00NCUJSIONS
(
) sa
( v(tusa, Recmmend furthe.r A/E Review.
MMM G/ dh, / 3bF P/
x~
Evaluator (Date (Systen Engineer) lk(
Mewer Date (Engineering Supervisor)
O
____.m____---_.m.---
- - - - -- --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - - - ^ ' - - - - - - " - ^ ^ ^ ^ - - - ~ - -
I 18015-C,Rev. 5 SECONDARY PLA!1T CHEMISTRY NOT INCLUDED:
Is divided into various modes including MODES 4,5, A!1D 6 But does
()
not involve Mid-loop issues.
18028-C,Rev. 7 LOSS OF INSTRUMENT AIR SECTION B APPIES TO MODE 3 B6 NOTE statec that if there is a loss of instrument air pres-
- sure, then MANUAL control of the SG Atmospheric Relief Valves will be required SECTION C APPLIES TO MODES 4,5, AND 6 C5 CAUTION and step rec;uires tripping one RHR Pump if tow are running due to Ri!R llX outlet valves failing full open.
C9 Requires tripping ol' running RHR Pump due to continued cooldown C10 If RHR Temperature rises, actions are throttle RHR Flow 18032-1,Rev. 4 LOSS OF 120 V AC INSTRUMENT POWER NOT INCLUDED:
Written independent of modo to address concerns resulting from loss of 120 V AC iE instrument power.
Primarily addresses at power insure; but may address some losses that affect a shutdown condition.
Examplest (a) loss of INY1N addresses losses of AFW instrumentation which is a Shutdown concern, (b) loss of
()
18Y1B addresses a loss of SR SR countrate indication which would be a shutdown concern.
18034-1,Rev. 1 LOSS OF CLASS 1E 125V DC POWER Written independent of mode to address concerns resulting from loss of 125 VDC IE.
18038-C,Rev. 10 OPERATION FROM REMOTE SHUTDOWN PANELS Not a midloop procedure, but does include ATTACHMENT G for local operation of SG Atmospheric Relief Valves.
19$00-C,Rev. 4 ECA-0.0 LOSS OF ALL AC POWER Does not apply to the midloop situation.
O 1
MIDI 40P PROCEDURES 12000-C,Rev. 16 REFUELING RECOVERY (MODE 6 TO MODE 5)
O 2.1.4 WORK ACTIVITIES 2.2.2 TECH SPECS 2.2.13 RWST INVENTORY 4.1.5 CONTROLS WHEN BEI4W 17 % PRZR LEVEL 4.1.10 MAINTAIN 1 FOOT ABOVE MID-NOZZLE,2 FEET IF SG llOZZLE DAMS INSTALLED 12006-C,Rev. 15 UNIT COOLDOWN TO COLD SHUTDOWN 2.1.4 WORK ACTIVITIES 2.2.6 TECH SPECS SG AVAILABLE 2.2.7 RHR AVAILABILITY IF NOT FILLED 2.2.17 RWST INVENTORY D4.2.15 CONTROLS WHEN BEI4W 17 % PRZR LEVEL 12007-C,Rev. 14 REFUELING ENTRY (MODE 5 TO MODE 6) 2.1.17 WORK ACTIVITIES 2.2.6 TECH SPECS 2.2.15 RWST INVENTORY CONTROLS WHEN BELOW 17 % PRZR LEVEL O
4.1.1 4.1.3 MAINTAIN 1 FOOT ABOVE MID-NOZZLE O
2
I e
13005-1, rov. 10
- ~
REACTOR COOLANT SYSTEM DRAINING 2.1.2 MAlllTAIN 1 FOOT ABOVE HID-NOZZLE AND 6 INCllES IF BURP-O ING SG TUBES WITilOUT USE OF NITROGEN PURGE 2.1.2 TR"ND RUR PUHP PARAHETERS WnEN AT 1 FOOT ABOVE HID-NOZZLE 2.1.8 CONTROLS IF DRAINING DOWN TO PERFORM MAINTENANCE ON REACTOR llEAD, SGs, OR RCP SEALS 2.1.9 ACTIONS IF LEVEL INDICATIO!( LOST 2.1.10 0NLY ONE DRAIN PATl! AT A TIME 2.1.11 NOT DRAIN FROM SAME LOOP AS BEING MONITORED FOR LEVEL 3 2.1 TECil SPECS Oli SG LEVELS 4.1.2 HAS MAINTENANCE IllSTALL TYGON TUBING AllD DEFEAT RilR SUCTION VALVES AUTO CLOSURE INTERLOCK WilEN DRAINING VIA RCDT 4.1.8 CAUTION NOT DRAIN FROM SAME LOOP BEING MONITORED FOR RCS LEVEL 4.1.12 PLACES TYGON llOSE LEVEL INDICATIONS IN SERVICE 4.1.13 MAINTEllANCE TO INSTALL REMOTE RCS TEMPORARY LEVEL INDICATIOli IF DRAINING BELOW 25 % PRZR LEVEL 4.1.15 CAUTION FOR DRAINAGE RATE AFFECT ON TYGON TUBING 4.1.18 USE NITROGEN TO ASSISTING DRAlllING SG TUBES 4.1.19 CAUTIONS AND NOTES ABOUT DRAINING TO 1 FOOT ABOVE MID-NOZZLE 4.1.20 NOTE ABOUT DRAINING TO 1 FOOT ABOVE HID-NOZZLE 4.2.2 MAINTENANCE TO INSTALL REMOTE RCS TEMPORARY LEVEL INSTRUMENTATION IF DRAINING RCS BELOW 25%
'4.2.11 PLACEMENT TO TYGON HOSE LEVEL IllDICATIOli Ill SERVICE O.
4.2.12 MAINTENCE TO INSTALL REMOTE RCS TEMPORARY LEVEL IllSTRU-MENTATION-4.2.14 CAUTION FOR DRAINAGE RATE AFFECT ON TYGON TUBING 4.2.18 USE NITROGEN TO ASSISTING DRAINING SG TUBES 4.2.19 CAUTIONS AND NOTES ABOUT DRAINING TO 1 FOOT ABOVE MID-NOZZLE 4.2.21 NOTE ABOUT DRAINING TO 1 FOOT ABOVE MID-NOZZLE CHECKLIST 1 SG TUBE BUNDLE DRAINING 13011-1,Rev. 18 RESIDUAL HEAT REMOVAL SYSTEM 2.1.6 WHENEVER 1 FOOT ABOVE MID-NOZZLE THE RHR FLOW SHOULD BE LIMITED IN RANGE FROM 3000 TO 3500 GPM.
4.8.1 CAUTION THAT EXCESSIVE FLOWRATE DURING PUMPDOWN WITH UPPER INTERNALS ASSEMBLY INSTALLED COULD LEAD TO.VO1D FORMATION IN RHR PUMP SUCTION, 17006-1,Rev. 11
-ANNUNCIATOR RESPONSE PROCEDURES FOR ALP 06 ON PANEL 1A2 ON MCB PAGE 7 RCS LEVEL LOW PER ANNUNCIATOR WINDOW A03-PAGE 21 RHR PUMP OVERLOAD TRIP INITIATES 18019-C, LOSS OF RHR PAGE 36 RWST EMPTY LEVEL ALARM INITIATES REFILLING 3
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18004-C,Rev. 6 REACTOR COOLANT SYSTEM LEAKAGE i
SECTION B ADDRESSES HODES 4 OR 5:
NOTE IF RCS LEAKAGE IS DETECTED WilILE OPERATING WITil RCS O
B1 LEVEL DELOW PR2R INDICATION Pfl4GE OR WITil AG NOZZLE DAMS INSTALLED TilEN GO TO 18019-C, LOSS OF RiiR SYSTEM.
B5 RiiR PUMP OPERATION INDICATIONS 18006-C,Rev. 2 FUEL HANDLING EVENT 12 SENDS OPERATOR TO 18004-C,RCS LEAKAGE IF SPENT FUEL POOL OR REACTOR CAVITY LOWERS UNEXPLAINABLY 18019-C,Rev. 7 LOSS OF RESIDUAL !! EAT REMOVAL SECTION A APPLIES TO MODES 4 OR 5 ENTIRE SECTION ADDRESSES MIDLOOP CONCERNS SECTION D APPLIES TO MODE 6 W2Tli HEAD REMOVED ENTIRE SECTION ADDRESSES HIDLOOP CONCERNS TO SOME EXTENT SYMPTOMS ADDRESS MIDLOOP CONCERNS Al CAUTION, NOTE AND STEP ADDRESSES WCAP ISSUES 18020-C,Rev. 3 LOSS OF COMPONENT COOLING WATER O
2RNO IF ONE TRAIN OF CCW CAN NOT BE PLACED IN SERVICE,THEN INITIATE 18019-C, LOSS OF RHR 4
IF NON-AFFECTED-TRAIN RHR CAN NOT BE PLACED IN SERVICE, TilEN INITIATE 18019-C, LOSS OF RHR 18021-C,Rev. 4 LOSS OF NUCLEAR SERVICE COOLING WATER SYSTEM SRNO IF RHR CAN NOT BE ESTABLISHED TO AN OPERATING NSCW TRAIN, TiiEN INITIATE 18019-C, LOSS OF RIIR PTDB-1 TAB 8.0,Rev. 2 PICTORIAL AIDS 8.2 SHOWS LAYOUT OF REMOTE AND LOCAL TEMPORARY MID-LOOP INSTRUMENTATION O
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