Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999
Proposed Tech Specs,Consisting of 1999 Changes to TS Bases
ML17265A6941999-06-28028 June 1999
Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping
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Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
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ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6521999-04-14014 April 1999
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ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
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Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5911999-03-0101 March 1999
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ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5491999-02-12012 February 1999
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ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5461999-02-12012 February 1999
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ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
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ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML17265A4661998-11-24024 November 1998
Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR
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Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
ML17265A2941998-05-21021 May 1998
Tech Specs Consisting of Submittal Changes for 1998
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A2461998-04-27027 April 1998
Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
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Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17264B0671997-10-0808 October 1997
Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements
ML17264B0441997-09-29029 September 1997
Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept
ML17264B0391997-09-29029 September 1997
Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
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Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264B0031997-08-19019 August 1997
Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3
ML17264A9991997-08-19019 August 1997
Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML20140B8291997-03-24024 March 1997
Rev 3 to EOP ATT-12.0, Attachment N2 Porvs
ML17264A8221997-02-0606 February 1997
Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
ML17264A8201997-02-0606 February 1997
Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction.
ML17264A8081997-01-23023 January 1997
Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1
ML20133N3351997-01-10010 January 1997
Rev 7 to FR-C.3, Response to Saturated Core Cooling
ML17264A8881996-10-10010 October 1996
Rev 9 to ODCM for Ginna Station.
ML20128N0681996-10-0303 October 1996
Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G
ML17264A5311996-05-31031 May 1996
Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2
ML17264A5161996-05-22022 May 1996
Rev 2 to Technical Requirements Manual (TRM)
ML17264A4581996-04-0808 April 1996
Rev 7 to ODCM for Ginna Station.
ML17264A4371996-04-0101 April 1996
Rev 1 to Technical Requirements Manual (TRM)
ML17264A4391996-04-0101 April 1996
Rev 1 to Updated Technical Requirements Manual (TRM)
ML17264A4191996-02-24024 February 1996
Rev 0 to Technical Requirements Manual (Trm).
ML17264A6901996-02-23023 February 1996
Rev 0 to Inservice Testing Program.
1999-05-12
[Table view] |
Text
.
.44 ,
A, Si tops i TLE:- REV: ' 3- '
.AP-RHR.2 ' LOSS OF,RHR WHILE OPERATING'.AT-RCS REDUCED PAGE 1 of 11'
' y]f f INVENTORY CONDITIONS ROCHESTER GAS AND ELECTRIC CORPORATION l GINNA STATION .
CONTROLLED COPY NUMBER D
~
TECHNICAL REVIEW PORC REVIEW DATE N ~ (9- 90 t
[s
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G!NN A STATION
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4 -' QA X NON-QA CATEGORY 1.0 . m.RT:
REVIEWED'BY: D A T E _.. _
l' Ti M E __. . __._ I i
hC.' i["i $ [ED:
u /"Y ,.
c * ;g DATE
, goggg{ {O[$bgjc" TIME:
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- ' EDP: TifLE REV:,3
- AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED t 1 INVENTORY CONDITIONS PAGE 2 of ll ,
A. ' PURPOSE - This procedure provides guidance necessary for maintain-
- ing core cooling and protecting the reactor core in the event that RHR cooling is lost during RCS reduced inventory operation, (i.e.,
at indicated "B" Loop Levels of less than 64 inches).
-B. ENTRY CONDITIONS / SYMPTOMS
- 1. SYMPTOMS - The symptoms of (Loss of RHR At RCS Reduced Inventory Conditions) are-l
- a. Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode) ,
alarm is lit, or
- b. Unexpected increase in RCS temperature while ,
on RHR cooling at low loop'lovels, or
- c. Erratic or no flow on FI-626, or
- d. Annunciator J,-9, Safeguard Breaker _ Trip alarm lit. t i
s_x ,
i L: m l !
1 l
r l'
's u
l L
l i
L)
til f,
'! i .
toes unt' REV ,3
'AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED
' INVENTORY CONDITIONS PAGE 3'of 11 g
- STEP -
ACTION /EXPhCTED RESPONSE RESPONSE NOT OBTAINED l Establish CNMT Closure 0-2.3.lA,-CONTAINMENT. CLOSURE CAPABILITY'DURING RCS REDUCED INVENTORY OPERATION, Step 5.8, while continuing with this procedure 2 Check RHR Pumps - AT LEAST Go to Step 7.
ONE RUNNING CAUTION DO NOT START A SECCND RHR PUMP UNTIL THE CAUSE OF THE ERRATIC FLOW OR LOSS OF (LOW 'ON THE FIRST PUMP HAS BEEN DETERMINED AND CORRECTE.
3 Check RHR Flow - GREATER THAN Perform the following:
200 GPM AND STABLE
- a. Stop all runnitig RHR pump (s).
'b. Go to Step 7.
L4- Verify ' CCW Operation: Perform the followings o CCV: pumps - AT.LEAST ONE RUNNING a. Restore CCV to RHRt o' CCV To RHR Hxs,-MOV-738A and o Start the standby CCV pump if
'MOV-738B - OPEN AS NECESSARY it is not running.
- o. CCV temperature and flov alarms o Open MOV-738A and MOV-738B,.
'- - EXTINGUISHED as necessary.
- b. JJP, CCW can NQT be restored,1HEH 7 C refer to AP-CCV.3, LOSS OF.CCV - , i PLANT SHUTDOWN, Step 1. ;
4 i .-
4
' hu i
o 4
1
, a t
" sop: TITLE: REV: ' 3
AP-RHR.2 LOSS OF RHR WHILE OPERATING'AT RCS REDUCED N- INVENTORY CONDITIONS PAGE 4 of 11 r b '
- STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I J: .
- 5 Verify RHR Alignment - NORMAL Align valves as required.
1 (Refer.to Attachment A)-
, 6 . Check RCS ' Temperature: s
- a. RCS temperature'- STABLE OR a. Return to Step 2. l
-DECREASING q-
- b. Go to Step 12 bCheckIfRCS'LoopLevelMust
- Be Raised:
- a. RCS loop level - LESS THAN'30" a. If,RCS loop. level is greater ON B LOOP LEVEL INDICATOR than.30", IEEE start an available RHR pump and go to I
, - Step 9 immediately.
. N).
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b
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E0Pic TITLE: Rm j 3 t
- AP-RHR.2: LOSS'OF RHR'WHILE OPERATING AT RCS REDUCED PAGE 5 ofl1'1 INVENTORY CONDITIONS 1:
j
$ - STEP -
- ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- * * * *.* *J* * * * * * * *-* *.* * * * * * * *~* * * * * * * * * * * * * * *
9 E BEFORE RAISING LOOP LEVEL,- THE S/G OFFICE SHOULD BE NOTIFIED.
l: ******-*********************************'**
l 8 Increase RCS Loop' Level'By The:Following Methods, Listed in. Preferential Order of Use:
a; Gravity feed method
(
- 1) Close RHR pump discharge
- valve to loop B cold Jeg, MOV-720 ,
- q 2) Dispatch A0 to locally open l; -
RHR pump suction from RVST, I'- -
MOV-856 m
- 3) Check RCS loop level - 3) H RCS loop level M' T!
a INCREASING'AS EXPECTED increasing, M perform. the following:-
a) Close MOV-856.
b) Open MOV-720. .!
f c) Go to Step 8b.-
i
- 4) WHEN B loop level indicator
' greater than 30 in., THEN close MOV-856 ^i 5)-Open RHR pump discharge valve 5) H NOV-720 does E open, q '
to B loop cold leg, MOV-720 M open core deluge valves MOV-852A and MOV-852B.
- 6) Start one RHR pump
- 7) Go to Step 9 immediately This Step continued on the next page, a:
t e
- - . -- .~ . - . . . - . - - . . -
.f I n - ,
UN' . top: TITLE: REV:-3' -
- AP-RHR.~ 2 LOSS OF'RHR'WHILE OPERATING AT RCS~ REDUCED I e INVENTORY CONDITIONS PAGE 6 of 11 3Q l
STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
1
]
'(Step 8 continued from previous page)
~
\ .b.~ Charging to intact loop cold leg method:
i.
! 1) Check B loop cold leg - 1) H A loop cold leg intact, INTACT. M go to' Step 8c.
h.
H A loop cold leg EQI i intact, M go to Step 8d. (
b, .
- 2) Open charging.line valve to loop B cold leg, A0V-294 i
- 3) Verify HCV-142 demand at 0%
4)-. Start-operable charging pump 4) H charging pump vill EQI and increase flow to haximum start, M a) Close A0V-294.- '
.i .
b) Go.to Step 8d.-.
- 5) Check RCS loop level - 5) H RCS loop level EQI INCREASING AS EXPECTED increasing as expected, M : .
a) Stop operating charging:
pump.
b) Close A0V-294.
~
c) H A loop cold leg intact, I go to Step 8c. l L
d) H A loop cold leg (101 l>
intact, go-to Step 8d.. i
- 6) VHEN B loop level indicator greater than 30 in., THEN stop operating charging pump
- 7) Close charging line valve to
-loop B cold leg, A0V-294 0 (~ 8) Start one RHR pump 1-g
.This-Step continued on the next page.
t.
- j. ,
f i: ,x:
a.
< ;; .g . s !>r
. .;g 5 l i-
[ii E0PI' TliLE: m '
3.
- hP-RHR.2' LOSS OF'RHR WHILE' OPERATING AT RCS REDUCED, l = INVENTORY-CONDITIONS PAGE 7 of:11 .
n ,- ,
- n ,
=
S{EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED :
i (Step'8 continued from previous page)
- 9) Go to Step 9 immediately 1
- c. Charging to A loop cold leg- ..
-method:
t h.
L: , 1) Open alternate-charging line
- 2) H charging pump vill F_01 I:
L 2) Start operable charging pump '1 L '
and increase flow to maximum start, M t ,
L .a) Close A0V-392B.
i b) Go to Step 8d. 3
- 3) Check RCS loop level'- 3) H RCS loop level F_QI )
. increasing'as expected, M L;. G '. INCREASING AS EXPECTED ;
D' a) Stop operating charging pump.
-l b).Close A0V-392B.
m 6
c) Go to Step.8d- .
j
?'
'4) VHEN B loop level indicator greater than 30 in., THEN 4
stop operating' charging pump
- i. !
- 5) Close alternate charging line 1 to' loop A cold leg,_A0V-392B p' 6).Siart one'RHR pump-
- 7) Go to Step.9 immediately i o.
4 4
A O : This Step continued on the next page.
fic
- c. ., . ..t
4
, 5
. 11
REV:i 3 -
J.> . APcRHR;2 ; LOSS OF RHR WHILE OPERATING AT RCS~ REDUCED .
~
INVENTORY CONDITIONS' PAGE 8 of 11'
.j
[ Q[ .7; ,
- STEP - ACTION / EXPECTED RES?ONSE RESPONSE NOT OBTAINED l
i
-(Step 8 continued from previous page) ;
-i
'd.~ Safety injection to loop hot r _ legs methods-- ,
1);Open loop
- hot' leg SI inlet, E valves:MOV-878A and/or
- 1. HOV-878C .i l;
p 2)-Open SI pumps suction valves 4 iy , MOV-825A and/or.MOV-825B g 4 3) Start operable safety.
-injection pump.' i
- 4) Check RCS loop level - 4) If,RCS loop level HQI 4 m: INCREASING AS EXPECTED increasing as expected, IEEE --
a) Stop operating SI pump.
b) Close loop hot leg inlet, 4 n 4 valves.
. j]
l
- MOV-878C c) Close SI pump suction-valves.- -]
d) Return to Step 1.
- 5) VHEN B loop level indicator greater than 30 in., THEN ,
stop operating safety injection pump-
- 6) Close SI pumps suction valves ,
T
, i- .* MOV-825B 7)'Close-loop hot leg SI inlet
~
e '
valves-
,k J 8) Start one RER pump
- 9) Co to Step 9 immediately c
<Y.
i_.___..;____._.__l___________________.________ - + - e
,-e ,
th qg , h ' \ "' '
i N %'- t0Ps . TITLE: '
REV:[3'
/" )AP-RHR.2' LOSS OF RHR WHILE OPERATING AT RCS REDUCED .
PAGE 9 of 11 l
. INVENTORY CONDITIONS
, . O, t > . x
- STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
i c
~ 9' Verify RHR Flow:
- a. RHR flov - GREATER THAN 200 GPM a. H an RHR pump is running with AND STABLE less than 200 gpm flow or erratic flov is indicated, IEEE O perform the following: ;
1)-Stop running RHR pump.
- 2) Direct auxiliary operator to vent RHR suction line in CNMT by "A" loop, valve 2764.
- 3) Start one RHR pump. ;
- 4) Go to Step 10 immediately. ~ .
- b. Go to-Step 12 l
l }
.10 - Verify - RHR Flow:
- a. RHR flov - GREATER THAN 200 GPM a. H adequate RHR flow can HQT,be.
AND STABLE established, IggE perform the following:' ;
L . i L
- 1) Stop running PRR pump (s).
l
- 2) Evacuate CNMT. !
- 3) Check to assure that CNMT
( closure _is completed or.
nearing completion. ;
- 4) Place RCDT pumps in service "
(Refer to ER-RHR.1, RCDT .
' OPERATION FOR CORE COOLING).
- 5) Go to Step 11.
- b. Go to Step 12 i
i 1
LU -
t f q
-l y
.. u s
n(i' t.-
i
,p top: Tint . REV:;3
- AP-RHR.2- LOSS OF:RHR:WHILE OPERATING AT RCS REDUCED.
INVENTORY CONDITIONS PAGE 10 of:11
}]2 ll W
- STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
'L t
.11 Verify.' Maintenance Notified' And Continue.Attempta'To-Restore Inoperable RHR. Pumps p Or RHR' Flow: ,
o , Maintenance - NOTIFIED N o Attempts continued to restore
- inoperable RHR pumps OR flow o Go to Step 12 ,
i 12 Establish Monitoring of RCS Temperature:
o .RCS temperature - MONITORING ESTABLISHED 13; : Check' With fligher Supervision:' .4 o.' Higher supervision - NOTIFIED 14 Check-Alternatives For Long
\ Term Cooling: r oi.Long term cooling alternatives -
' EVALUATED 15 - Check For. Site Contingency Classification:
o Site contingency ' classification
-= REFER TO SC-100,'GUINA g STATION EVENT EVALUATION'AND i CLASSIFICATION o
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f ,-)q n INVENTORY.' CONDITIONS -PAGE 11 of 11 i
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- STEP - ACTION /EXPECTEbRESPONSE RESPONSE NOT OBTAINED y ;
'16 Check ForlNRC Reporting-Requirements:
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- REFER TO 0-9.3,;NRC IMMEDIATE
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o ,17 Verify RHR' Cooling: .,
- La. RHR cooling normal- a. Return to Step 1. i l
- o. RHR cooling -' RESTORED o RCS temperature - STABLE OR
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- b. Return - REQUIRED PLANT
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1 ATTACHMENI_A NORMAL RHR COOLING VALVE ALIGNMENT i
.IUUR from. Loop.A Hot Leg .................. MOV-700 Open l MOV-701 Open l RHR to Loop B' Cold Leg ................... MOV-720 Open MOV-721 Open p RHR Letdown to CVCS ..-.................... HCV-133 Open RHR Pump Discharge Cross-Connect ......... V-709C Open V-709D Open .i 7 RHR HX Bypass ............................ V-712A Open h ,
FCV-626 as desired [
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HR From-1AERHR Hx ....................... HCV-625 as desired RHR,From 1B RHR Hx ....................... HCV-624- as desired -
I000 Supply Valve From RWST ............... MOV-856 Closed i
L RHR Pump Suction. Valves l A RHR Pump .................. MOV-704A Open B RHR Pump .................. MOV-704B Open m
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