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| issue date = 04/14/1993
| issue date = 04/14/1993
| title = Rev 7 to EOP FR-S.1, Response to Reactor Restart/Atws.
| title = Rev 7 to EOP FR-S.1, Response to Reactor Restart/Atws.
| author name = MARLOW T A
| author name = Marlow T
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:EOP:          TITLE:
REV: 7 FR-S.1              RESPONSE  TO REACTOR RESTART/ATWS PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
930514005b 930505
'PDR    ADOCK 05000244 F                  PDR
 
  .L 1
 
EOP:
REV! 7 FR-S. 1            RESPONSE  TO REACTOR RESTART/ATWS PAGE 2 of 11 A. PURPOSE  This  procedure provides actions to add negative reactivity to  a  core which is observed to be critical when expected to be shut down.
B. ENTRY CONDITIONS/SYMPTOMS
: 1. ENTRY CONDITIONS  This  procedure  is entered from:
: a. E-O, REACTOR TRIP  OR SAFETY  INJECTION, when  reactor trip is not verified and manual trip is not effective.
: b. F-0.1, SUBCRITICALITY Critical Safety Function Status Tree on either a RED or ORANGE condition.
 
EOP:
REV: 7 FR-S.1                RESPONSE    TO REACTOR RESTART/ATWS PAGE 3  of 11 STEP      ACTION/EXPECTED RESPONSE              RESPONSE    NOT OBTAINED NOTE:  o  Steps  1 through 4 are  IMMEDIATE ACTION  steps.
o  Adverse  CNMT  values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
Manually  trip reactor.
o  At least one train of reactor          IF reactor trip breakers    NOT open, trip breakers - OPEN                    THEN  manually insert control rods.
o  Neutron  flux  - DECREASING o  MRPI indicates  - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM O Verify Turbine Stop Valves 2
CLOSED Manually IF trip turbine.
turbine trip can NOT    be verified,    THEN close both MSIVs.
3    Check  AFW Pumps    Running:
: a. MDAFW pumps - RUNNING                  a. Manually    start MDAFW pumps.
: b. TDAFW pump  - RUNNING  IF              b. Manually open steam supply NECESSARY                                  valves.
                                                      ~ MOV-3505A
                                                      ~ MOV-3504A
 
EOP:              TITLE:
REV: 7 FR-S.1                    RESPONSE    TO REACTOR RESTART/ATWS PAGE  4-of  11 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE  NOT OBTAINED CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING IMMEDIATE ACTIONS OF E-O, REACTOR TRIP OR SAFETY INJECTION.
NOTE:    If offsite    power  is lost coincident with SI, then    MCC C  and  MCC D lockout relays must      be  reset to restore  BA and  RMW  pumps.
O OfInitiate 4
RCS:
Emergency Boration
: a. Check SI status:                            a. Perform the following:
o  All SI    annunciators                    1) Complete the immediate EXTINGUISHED                                  actions of E-O,    REACTOR TRIP OR SAFETY    INJECTION,  while o  All SI    pumps  - OFF IN AUTO                continuing with this procedure
: 2) IF SI flow indicated, THEN go to Step 5. IF NOT, THEN go to Step 4b.
: b. Verify at least one charging                b. Perform the following:
pump - RUNNING
: 1) Reset SI    if necessary.
: 2)  Start  one  charging pump.
c, Align boration path:                        c. Initiate  normal boration at maximum rate using the boric
: 1) Start    two BA  transfer  pumps          acid flow control valve, FCV-110A. IF flow can NOT be
: 2) Open MOV-350                                established, THEN refer to ER-CVCS.1, REACTOR MAKEUP
: 3) Verify BA flow                              CONTROL MALFUNCTION.
: d. Verify charging flow path:                  d. Manually  align valves    and verify flow.
o  Charging valve to loop        B cold leg  (AOV-294) -  OPEN o  Charging flow control valve (HCV-142) -    DEMAND AT 0'5
 
EOP:
REV: 7 FR-ST 1              RESPONSE  TO REACTOR RESTART/ATWS PAGE 5  of 11 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 5  Check  If  The Following Have Occurred:
Trips
: a. Reactor  trip                      a. Dispatch  AO  to locally  trip reactor:
o  Trip  MG  set breakers at bus 13 and bus 15.
o  Open  reactor  trip  breakers locally.
: b. Turbine  trip                      b. Dispatch operator to locally trip turbine using manual trip lever on west end of HP turbine.
6 Check PRZR    PORV  Status:            Verify CNMT ventilation isolation.
IF dampers NOT closed,    THEN o  RCS pressure  - LESS THAN          momentarily deenergize    CNMT 2335 PSIG                          particulate monitor, R-ll, to actuate CVI.
o PORVs  - CLOSED o  Annunciator F-19,  PRZR PORV OUTLET  HI TEMP - EXTINGUISHED
 
EOP:              TITLE:
REV' FR-S 1  ~                  RESPONSE    TO REACTOR RESTART/ATWS PAGE 6    of  11 STEP        ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED CAUTION IF  CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
7  Check S/G      Level:
: a. Narrow range    level in at least        a. Perform the following:
one S/G - GREATER THAN    5%  (25%
adverse  CNMT]                              1) Verify total feed flow greater than 400    gpm.
IF NOT, THEN  manually  start pumps and  align valves  as necessary.
: 2) Maintain  total feed flow greater than 400  gpm  until narrow range level greater than 5$ [25% adverse CNMT]    in at least  one S/G.
: b. Control feed flow to maintain narrow range level between 17$
t25%  adverse  CNMT]  and 50%
8  Verify Dilution Paths                        Manually isolate  dilution paths.
ISOLATED o  Place  RMW  mode  switch to  BORATE o  Verify RMW to blender (HCV-ill)
CLOSED o  Verify RMW    pumps  - OFF
 
y't EOP:
REV: 7 FR-ST 1                RESPONSE    TO REACTOR RESTART/ATWS PAGE 7    of ll STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 9  Stabilize    RCS  Temperature:
: a. Control steam dump as necessary
: b. Verify the following:                  b. IF  RCS  cooldown can  NOT be controlled,  THEN close both o  Core  exit  T/Cs - STABLE  OR          MSIVs and go  to Step 10.
INCREASING o  Pressure  in both  S/Gs STABLE OR INCREASING o  Pressure  in both  S/Gs GREATER THAN 100 PSIG
: c. Go to Step  14 10  Verify MFW Isolation:
: a. MFW pumps  - TRIPPED                  a. Manually close    MFW  pump discharge valves and    trip  MFW pumps.
: b. MFW flow control valves    - CLOSED  b. Place A and B S/G MFW regulating valve and bypass valve
          ~ MFW  regulating valves                  controllers to MANUAL at 0%
          ~ MFW bypass valves                        demand.
11  Identify Faulted        S/G:              Go  to Step 14.
o  Any S/G Pressure    - DECREASING  IN AN UNCONTROLLED MANNER
                    -OR-o  Any S/G - COMPLETELY DEPRESSURIZED
 
EOP:              TITLE:
REV: 7 FR-S.1                    RESPONSE  TO REACTOR RESTART/ATWS PAGE 8  of 11 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED CAUTION o  AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
o  IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.
12  Isolate    Feed Flow To Faulted            Manually close valves.
S/G:
IF valves can NOT be closed, THEN o  Close  faulted  S/G MDAFW pump        dispatch AO to locally isolate discharge valve                          flowpaths as necessary.
            ~ S/G A, MOV-4007
            ~ S/G B, MOV-4008 o  Pull stop faulted    S/G MDAFW pump o  Close  faulted  S/G TDAFW flow control valve
            ~ S/G A, AOV-4297
            ~ S/G B, AOV-4298 o  Verify faulted S/G MFW regulating valve and bypass valve -  CLOSED
            ~ S/G A, HCV-466 and HCV-480
            ~ S/G B, HCV-476 and HCV-481 o  Verify MDAFW pump crosstie valves -    BOTH CLOSED
            ~ MOV-4000A
            ~ MOV-4000B o  Close  faulted  S/G SAFW pump discharge valve
            ~ S/G A, MOV-9701A
            ~ S/G B, MOV-9701B
 
EOP:
REV: 7 FR-S.1                RESPONSE  TO REACTOR RESTART/ATWS PAGE 9  of 11 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 13  Isolate    Steam Flow From              Manually close valves.
Faulted S/G:
IF valves can NOT be closed, THEN o Verify faulted  S/G ARV - CLOSED    dispatch AO to locally isolate flowpaths as necessary.
          ~  S/G A, AOV-3411
          ~  S/G B, AOV-3410 o Close  faulted  S/G TDAFW pump steam supply valve and place    in PULL STOP
          ~  S/G A, MOV-3505A
          ~  S/G B, MOV-3504A o  Verify faulted  S/G blowdown and sample valves -  CLOSED
          ~  S/G A, AOV-5738 and AOV-5735
          ~  S/G B, AOV-5737 and AOV-5736 o Dispatch  AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)
 
A EOP:            T1TLE:
REV: 7 FR-S. 1                RESPONSE    TO REACTOR RESTART/ATWS PAGE 10    of 11 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.
NOTE:  Adverse  CNMT  conditions or loss of forced air cooling    may  result in failure of  NIS detectors.
14  Verify Reactor Subcritical:                  Perform the following:
o  Power range channels    - LESS THAN    a. Stabilize  RCS  temperature.
5%
: b. Continue to  inject boric acid.
o  Intermediate range channels STABLE OR DECREASING                    c. Direct  HP to sample  RCS  and PRZR for boron concentration.
o  Intermediate range channels startup rate - NEGATIVE                  d. Verify boron concentration greater than Figure  SDM.
o  Core  exit  T/Cs - STABLE IF adequate shutdown margin verified,  THEN return to procedure and step  in effect.
IF  NOT, THEN  perform the following:
: a. Allow RCS to heat up.
: b. Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.
c  Return to Step 5.
 
EOP:
REV: 7 FR-S.1              RESPONSE  TO REACTOR RESTART/ATWS PAGE 11 of 11 STEP    ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 15  Return to Procedure And Step In Effect
                                          -END-
 
EOP:
REV: 7 FR-S. 1          RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FR-S. 1 APPENDIX LIST TITLE                              PAGES
: 1) FIGURE SDM
: 2) ATTACHMENT FAULTED S/G
 
EOP:          TITLE:
REV: 7 FR-ST 1              RESPONSE  TO REACTOR RESTART/ATWS PAGE 1  of  1 FIGURE SDM 1
NOTE:    o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod.
o To obtain core burnup, use PPCS turn on code BURNUP.
BORON CONCENTRATION  (PPH) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDM 1200                                                  100 PPH CONS ERVATISH INCLUDED 1000 800 600 400 BORA 200                                                                  BURNUP INCREMENTS 100 HWD/MTU 0    1000  2000    3000  4000  5000  6000  7000    8000 9000  10000  11000 CYCLE 23 BURNUP (HWD/HTU)}}

Latest revision as of 10:36, 4 February 2020

Rev 7 to EOP FR-S.1, Response to Reactor Restart/Atws.
ML17263A275
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/14/1993
From: Marlow T
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A269 List:
References
FR-S.1, NUDOCS 9305140056
Download: ML17263A275 (26)


Text

EOP: TITLE:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

930514005b 930505

'PDR ADOCK 05000244 F PDR

.L 1

EOP:

REV! 7 FR-S. 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 2 of 11 A. PURPOSE This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:
a. E-O, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.
b. F-0.1, SUBCRITICALITY Critical Safety Function Status Tree on either a RED or ORANGE condition.

EOP:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Steps 1 through 4 are IMMEDIATE ACTION steps.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

Manually trip reactor.

o At least one train of reactor IF reactor trip breakers NOT open, trip breakers - OPEN THEN manually insert control rods.

o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM O Verify Turbine Stop Valves 2

CLOSED Manually IF trip turbine.

turbine trip can NOT be verified, THEN close both MSIVs.

3 Check AFW Pumps Running:

a. MDAFW pumps - RUNNING a. Manually start MDAFW pumps.
b. TDAFW pump - RUNNING IF b. Manually open steam supply NECESSARY valves.

~ MOV-3505A

~ MOV-3504A

EOP: TITLE:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 4-of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING IMMEDIATE ACTIONS OF E-O, REACTOR TRIP OR SAFETY INJECTION.

NOTE: If offsite power is lost coincident with SI, then MCC C and MCC D lockout relays must be reset to restore BA and RMW pumps.

O OfInitiate 4

RCS:

Emergency Boration

a. Check SI status: a. Perform the following:

o All SI annunciators 1) Complete the immediate EXTINGUISHED actions of E-O, REACTOR TRIP OR SAFETY INJECTION, while o All SI pumps - OFF IN AUTO continuing with this procedure

2) IF SI flow indicated, THEN go to Step 5. IF NOT, THEN go to Step 4b.
b. Verify at least one charging b. Perform the following:

pump - RUNNING

1) Reset SI if necessary.
2) Start one charging pump.

c, Align boration path: c. Initiate normal boration at maximum rate using the boric

1) Start two BA transfer pumps acid flow control valve, FCV-110A. IF flow can NOT be
2) Open MOV-350 established, THEN refer to ER-CVCS.1, REACTOR MAKEUP
3) Verify BA flow CONTROL MALFUNCTION.
d. Verify charging flow path: d. Manually align valves and verify flow.

o Charging valve to loop B cold leg (AOV-294) - OPEN o Charging flow control valve (HCV-142) - DEMAND AT 0'5

EOP:

REV: 7 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If The Following Have Occurred:

Trips

a. Reactor trip a. Dispatch AO to locally trip reactor:

o Trip MG set breakers at bus 13 and bus 15.

o Open reactor trip breakers locally.

b. Turbine trip b. Dispatch operator to locally trip turbine using manual trip lever on west end of HP turbine.

6 Check PRZR PORV Status: Verify CNMT ventilation isolation.

IF dampers NOT closed, THEN o RCS pressure - LESS THAN momentarily deenergize CNMT 2335 PSIG particulate monitor, R-ll, to actuate CVI.

o PORVs - CLOSED o Annunciator F-19, PRZR PORV OUTLET HI TEMP - EXTINGUISHED

EOP: TITLE:

REV' FR-S 1 ~ RESPONSE TO REACTOR RESTART/ATWS PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

7 Check S/G Level:

a. Narrow range level in at least a. Perform the following:

one S/G - GREATER THAN 5% (25%

adverse CNMT] 1) Verify total feed flow greater than 400 gpm.

IF NOT, THEN manually start pumps and align valves as necessary.

2) Maintain total feed flow greater than 400 gpm until narrow range level greater than 5$ [25% adverse CNMT] in at least one S/G.
b. Control feed flow to maintain narrow range level between 17$

t25% adverse CNMT] and 50%

8 Verify Dilution Paths Manually isolate dilution paths.

ISOLATED o Place RMW mode switch to BORATE o Verify RMW to blender (HCV-ill)

CLOSED o Verify RMW pumps - OFF

y't EOP:

REV: 7 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 7 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Stabilize RCS Temperature:

a. Control steam dump as necessary
b. Verify the following: b. IF RCS cooldown can NOT be controlled, THEN close both o Core exit T/Cs - STABLE OR MSIVs and go to Step 10.

INCREASING o Pressure in both S/Gs STABLE OR INCREASING o Pressure in both S/Gs GREATER THAN 100 PSIG

c. Go to Step 14 10 Verify MFW Isolation:
a. MFW pumps - TRIPPED a. Manually close MFW pump discharge valves and trip MFW pumps.
b. MFW flow control valves - CLOSED b. Place A and B S/G MFW regulating valve and bypass valve

~ MFW regulating valves controllers to MANUAL at 0%

~ MFW bypass valves demand.

11 Identify Faulted S/G: Go to Step 14.

o Any S/G Pressure - DECREASING IN AN UNCONTROLLED MANNER

-OR-o Any S/G - COMPLETELY DEPRESSURIZED

EOP: TITLE:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

o IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.

12 Isolate Feed Flow To Faulted Manually close valves.

S/G:

IF valves can NOT be closed, THEN o Close faulted S/G MDAFW pump dispatch AO to locally isolate discharge valve flowpaths as necessary.

~ S/G A, MOV-4007

~ S/G B, MOV-4008 o Pull stop faulted S/G MDAFW pump o Close faulted S/G TDAFW flow control valve

~ S/G A, AOV-4297

~ S/G B, AOV-4298 o Verify faulted S/G MFW regulating valve and bypass valve - CLOSED

~ S/G A, HCV-466 and HCV-480

~ S/G B, HCV-476 and HCV-481 o Verify MDAFW pump crosstie valves - BOTH CLOSED

~ MOV-4000A

~ MOV-4000B o Close faulted S/G SAFW pump discharge valve

~ S/G A, MOV-9701A

~ S/G B, MOV-9701B

EOP:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Isolate Steam Flow From Manually close valves.

Faulted S/G:

IF valves can NOT be closed, THEN o Verify faulted S/G ARV - CLOSED dispatch AO to locally isolate flowpaths as necessary.

~ S/G A, AOV-3411

~ S/G B, AOV-3410 o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP

~ S/G A, MOV-3505A

~ S/G B, MOV-3504A o Verify faulted S/G blowdown and sample valves - CLOSED

~ S/G A, AOV-5738 and AOV-5735

~ S/G B, AOV-5737 and AOV-5736 o Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)

A EOP: T1TLE:

REV: 7 FR-S. 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.

NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

14 Verify Reactor Subcritical: Perform the following:

o Power range channels - LESS THAN a. Stabilize RCS temperature.

5%

b. Continue to inject boric acid.

o Intermediate range channels STABLE OR DECREASING c. Direct HP to sample RCS and PRZR for boron concentration.

o Intermediate range channels startup rate - NEGATIVE d. Verify boron concentration greater than Figure SDM.

o Core exit T/Cs - STABLE IF adequate shutdown margin verified, THEN return to procedure and step in effect.

IF NOT, THEN perform the following:

a. Allow RCS to heat up.
b. Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.

c Return to Step 5.

EOP:

REV: 7 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 11 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Return to Procedure And Step In Effect

-END-

EOP:

REV: 7 FR-S. 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FR-S. 1 APPENDIX LIST TITLE PAGES

1) FIGURE SDM
2) ATTACHMENT FAULTED S/G

EOP: TITLE:

REV: 7 FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FIGURE SDM 1

NOTE: o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod.

o To obtain core burnup, use PPCS turn on code BURNUP.

BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDM 1200 100 PPH CONS ERVATISH INCLUDED 1000 800 600 400 BORA 200 BURNUP INCREMENTS 100 HWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 23 BURNUP (HWD/HTU)