ML20086S721
| ML20086S721 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/12/1982 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML20086S719 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 74-1125531, 74-1125531-00, NUDOCS 8403050110 | |
| Download: ML20086S721 (86) | |
Text
BWNP-20004 (6-76)
BABCOCK & WILCOX sucteas rowse cewu4rraw oivision TECHNICAL DOCUMENT h h
DAVIS BESSE NUCLEAR POWER STATION UNIT UNIT I ABNORMAL TRANSIENT OPERATING GUIDELINES PART I 74-1125531-00 V Doc.10 - Serial No., Revision No.
for TOLEDO EDISON COMPANY by BABCOCK & WILCOX THIS DOCUMENT WAS PREPARED FOR TOLEDO EDISON COMPANY UNDER MASTER SERVICE CONTRACT NO. 582-7151 (B&W No. 582-7108). ANY USE OF THE INFORMATION CONTAINED llEREIN OTHER TilAN UNDER THE EXPRESS CONDITIONS OF SAID CONTRACT IS EXPRESSLY PROHIBITED WITil00T THE WRITTEN PERMISSION OF Tile BABCOCK &
WILCOX COMPANY.
8403050110 840301 PDR ADOCK 05000346 F ppg PAGE 1
BWNP-20005 (6-76)
BABCOCK & WILCOX NUMSER NUCLEAR POWER GtN?RATON DIV4 BON s RECORO OF REVISION 74-1125531-00 REV. NO. CHANGE SECT / PARA. DESCRIPTION / CHANGE AUTHORIZATION 00 Original Issue - J. J. Kelly System Engineering Prepared by / ! ,- Date /6 7 Reviewed by & , _
,,a Date C'[ 81 Approved by ) A Date d J"L !F Approved by Date /d//2.//L Released by - -
fff/ Date /b[/L//2.
N DATE: 7-6-82 PAGE 2
f BWhP-20007 (6-76)
BABCOCK & WILCOX Numien NUCLEAa POWER GENERATION OlViblON
'~' 74-1i23331-00 TECHNICAL DOCUMENT
\ l V
TABLE OF CONTENTS SECTION TITLE TAB NAME Abbrevation Glossary Section I Immediate Action REACTOR TRIP f,,%_d) Section II Vital System Status 5'erification REACTOR TRIP Section III A Lack of Adequate Subcooling Margin SUB000 LINS Section III B Lack of Heat Transfer LACK OF HEAT TRANSFER Section III C Excessive Heat Transfer EXCESSIVE HEAT TRANSFER Section III D Steam Generator Tube Rupture SGTR
,,., CP-101 A Large LOCA Has Occurred and the C00LDOWN
/ N Core Flood Tanks Are Emptying k
\
CP-102 Normal Coodlown CP-103 Trans ient Termination Following an Occurrence That Leaves the MCS Saturated With OTSGs Removing Heat CP-104 Transient Termination Following an Occurrence That Leaves the RCS Being Cooled by MU/HPI Cooling CP-103 Transient Termination Following an
-x Occurrence That May Require Pres-
[\ surizer Recovery or Solid Plant
)' Cooldown With SGs Removing Heat and RCS Subcooled Specific Rules Specific Rule 1 SPECIFIC RULES Specific Rule 2 Specific Rule 3 Specific Rule 4 SAD SAD
,_s Section ICC Inadequate Core Cooling ICC I )
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DATE: 7-6-82 PAGE 3 1
BWNP-20007 (6-76)
SABCOCK & WILCOX OII wucteAn Powea oewsRAHON DMSON _ _
TECHNICAL DOCUMENT LIST OF FIGURES Figures Title 1 HPI Flow Vs. RC Pressure 2 RC Pressure / Temperature Limits 3 Core Exit Fluid Temperature For Inadequate Core Cooling ,
4 HPI Throttling Limit (for High Flow HPI Line)
LIST OF TABLES Tables Title 1 (Sheet 1 of 2) SFRCS Equipment Actution - Actuation Channel 1 1 (Sheet 2 of 2) SFRCS Equipment Actuation - Actuation Channel 2 DATE: 7-6-82 PAGE 3-1
BWNP-20007 (6-76) l SASCOCK & WILCOX *"""
wucteam powea oewenArow ovviscw 74- n 2333i-oO TECHNICAL DOCUMENT ABBREVIATION CLOSSARY AFP Auxiliary Feed Pump AFPT Auxiliary Feed Pump Turbine AFW Auxiliary Feedwater AVV Atmospheric Vent Valve BAMT Boric Acid Mix Tank BWST Borated Water Storage Tank CCW Component Cooling Water CFT Core Flood Tank CP Cooldown Procedure CRT Cathode Ray Tube CS Containment Spray CST Condensate Storage Tank C6HP Chemistry and Health Physics CTMT Containment Vessel DH Decay Heat DHR Decay Heat Removal EP Emergency Procedure FW Feedwater H2 Hydrogen HPI High Pressure Injection ICC Inadequate Core Cooling ICS Integrated Control System IC T/C Incore Thermocouple L/D RC Letdown LOCA Loss of Coolant Accident LOOP Loss of Of fsite Power LPI Low Pressure Injection MFSV Main Feedwater Stop Valve MFW' Main Feedwater MOV Motor Operated Valve MU Makeup MUP Makeup Pump MSIV Main Steam Isolation Valve DATE: 7-6-82 PAGE 4
BWNP-20007 (6-76)
BABCOCK & WILCOX Nuuset NUCLEAR POWER GENERATION DIYlSION _ _
TECHNICAL. DOCUMENT MSSV Main Stean Safety Valve N2 Nitrogen NDT Nil Ductility Temperature NR Narrow Range NNI NonNuclear Instrumentation OTSG Once Through Stean Generator PP Plant Procedure P/T Pressure vs. Temperature Plot for Water PORV Pilot Operated Relief Valve Pzr. Pr es sur ize r RCP Reactor Coolant Pump RC Reactor Coolant RCS Reactor Coolant System RTD Resistance Temperature Detector SAD System Auxiliary Diagram SGTR Stean Generator Tube Rupture SFAS Safety Features Actution System SFRCS Stean Feed Rupture Control System SG Steam Generator SP System Procedure SS Secondary Side SSRH Second Stage Reheaters STA Station Technical Advisor STM LK SG STMLKSG Steau Leak Stean Generator SU Startup SUFP Startup Feedwater Pump TBS Turbine Bypass System TBV Turbine Bypass Valve Tc Tcold, RCS Loop (Cold Leg) Temperature T/C The rmocouple Th Thot, RCS Loop (Hot Leg) Temperature TRSG Tube Ruptured Steam Generator WR Wide Range DATE: 7-6-82 PAGE 5
BWNP-20007 (6-76)
BABCOCK & WILCOX NUuttR NUCLEAR POWit GENERATON Divi $lON TECHNICAL DOCUMENT 74-ti2ssu-On Section I Immediate Actions Determine whether this is a reactor trip or a forced shutdown situation and proceed below, s
Reactor Trip Forced Shutdown
- a. Manually trip the reactor. a. If a tube rupture has occured as indicated by main steam line and/or vacuum system dis-charge monitor alarm, go to SGTR section.
- b. Manually trip the turbine, b. If a forced shutdown is re-O quired by technical specifi-cation or by other operating documents, shut down plant to required conditions per normal procedures, sterting with PP 1102.04 Power Operation.
As soon as the reactor is shutdown, continue with Section II.
- c. Gall STA.
~
- d. Go to Section II.
\
\
Section I DATE: 7-6-82 PAGE 6
O LEFT BLANK e
O O
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BWNP-20007 (6-76)
BABCOCK & WILCOX Numeen NUcttAR POWER OtNERATION DIVI $60N TECHNICAL DOCUMENT 74-1125531-00 Section II Vital System Status Verification Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE hADE, PERFORM THE FOLLOWING:
1.0 REACTOR POWER DECREASING ON Begin emergency boration as neces-INTERMEDIATE RANGE. sary by transferring MUP suction to the BWST (close MU-3971).
2.0 ALL RODS ON BOTTOM. Begin emergency boration as neces-sary by transferring MUP suction to the BWST (close MU-3971) or by Boric Acid addition to make-up tank.
3.0 ALL MAIN TURBINE STOP Manually trip the turbine from the VALVES SHUT. front standard.
4.0 LETDOWN FLOW THROUGH BLOCK Close Block Orifice Bypass Valve ORIFICE ONLY. (MU-6).
5.0 SECOND MUP RUNNING. Start second makeup pump.
6.0 FEEDWATER HAS RUNBACK AND Trip running feedwater pump OTSG LEVELS ARE DECREASING. and start AFW.
\
V Section II DATE: 7-6-82 PAGE 7
r BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR POWER GENERATION DIYl510N 7'- 123531-00 TECHNICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE FOLLOWING:
7.0 NNI POWER CHECK All NNI Power Lost Rafer to EP 1202.63 Loss of NNI Power.
8.0 ICS POWER ON AS INDICATED BY a) Trip SFRCS on W AP.
HAND-AUTO LIGHTS LIT ON ICS STATION. b) Transfer static switch on in-verter YVB to alternate source.
If already positioned to al-ternate source, transfer back to inverter YVB.
c) E ICS power is still not re-stored AND YBR is de-energized ,
THEN place switch on YVB to alternate, close cross tie between YBR and YAR by opening switch YBR-01 and shutting YBR-02 and YAR-02.
d) E ICS power is still not re-stored, THEN use local manual controls.
9.0 STATION AUXILIARIES HAVE a) Start or verify auto start an SHIFTED TO SU TRANSFORMER loading of diesel generators.
WITH VOLTAGE INDICATED ON ALL BUSES. b) Verify auto start of AFW with proper SG level control (see Specific Rule 3 and 4).
O Section II DATE: PAGE 7-6-82 8
BWNP-20007 (6-76)
SABCOCK & WILCOX ,,,,,
MUCLGAR POWEE OGNWATION OfvtS40N 7'-n 23531-00 TECHNICAL DOCUMENT Verification Column Remedial Action Column
. VERIFY THE FOLLOWING:
I l c) IF no SFAS Level 3 actua-tion, THEN ensure a makeup pump is started and RCP seal injection is reestablished.
d) IF no SFAS actuation THEN Esure the station air system starts. Refer to EP 1202.34.
e) Ensure the component cooling water system starts.
f) Ensure the service water pumps start, g) IF power is available in the E SKV switchyard, THEN align one or both of the SU trans-formers to supply power to A and B buses.
Section II DATE:
7-6-82 9
BWNP-20007 (6-76)
BABCOCK & WILCOX s, ,
74-1125531-00 wuct An Powea onwenArioN Dtvl5CN TECHNICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE FOLLOWING:
10,.0 NO SFAS ALARMS, RCS 1650 PSIG Trip a) Verify SFAS levels 1 and 2 have actuated.
b) Close the RC letdown cooler inlet valve (MU-2B).
c) Close the PORV block valve (RC-II).
d) Close PZR Spray Block Valve (RC-10).
e) Verify full makeup system flow:
- Start second MU pump.
- Control valve (MU-32) is open.
- Shift MU pump suction to BWST if required by closing MU-3571.
- Re-establish CCW to MUP if RC pressure > 450 psig, f) IF the HPI system is not op-Eating properly, THEN refer to the SAD section to assist in getting the HPI system operational .
RCS 450 PSIG Trip a) Verify SFAS level 3 has actuated.
O Section II DATE: PAGE 7-6-82 10 j
BWNP-20007 (6-76)
BASCOCK & WILCOX Numeen NUCitAR Powet GENERAfsON OfVi�N 74-li2n3i-00 TECHICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE.FOLLOWING: ,
10.0 (CONT'D) b) IF either the HPI or LPI system is not operating properly, THEN refer to the SAD section to as-sist in getting the HPI or LPI system operational.
CTMT 18.1 PSIA TRIP a) Verify SFAS levels 1, 2, and 3 have actuated, b) Close the RC letdown cooler inlet valve (MU-2B) c) Close the PORV block valve (RC-ll).
CTMT 38.0 PSIA Trip a) Verify SFAS level 4, has actuated.
CTMT RAD Trip a) Verify SFAS level I has actuated.
BWST Low Level Transfer (8 FT) a) Verify SFAS Level 5 has actuated.
b) Shift LPI pump suction to con-tainment emergency sump if necessary.
Section II DATE: 7-6-82 PAGE
[
EWNP-20007 (6-76)
BABCOCK & WILCOX NUCifAt POWER GENERAtlON DIVISION 74-1125s31-00 TECHNICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE FOLLOWING:
11.0 SFRCS ACTUATION a) Verify proper SFRCS actuation in accordance with Table 1.
I b) Verify proper OTSG level con-trol by AFW (se Specific Rule 3 and 4).
c) Regain OTSG pressure control with AVVS.
12.0 ADEQUATE SUBC00 LING MARGIN Go to Lack of Subcooling EXISTS. Section - III A.
Go to Lack of Heat Transfer O
13.0 ADEQUATE PRIMARY TO SECONDARY HEAT TRANSFER EXISTS. Section - III B.
14.0 PRIMARY TO SECONDARY HEAT Go to Excessive Hee.t Transfer TRANSFER IS NOT EXCESSIVE. Section - III C.
15.0 MAIN STEAM LINE AND/OR Go to SGTR Sect. ion - III D.
CONDENSER VACUUM SYSTEM RADIATION MONITOR ALARMS.
16.0 THE PLANT IS STABLE IN A SAFE, SUBC00 LED CONDITION WITH PROPER PRIMARY TO SECONDARY HEAT TRANSFER AND NO MAJOR PRIMARY TO SECONDARY BOUNDARY FAILURES, FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
O Section II DATE: PAGE l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ )
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BWNP-20007 (6-76)
BABCOCK & WILCOX Numeen NucttAR POWtt GENERATON DIVISCN 74-t i2n31-00 TECNNICAL DOCUMENT III A LACK OF ADEQUATE SUBC00 LING MARGIN FOLLOWUP ACTIONS FOR THE TREATMENT OF LACK OF SUBC00 LING MARGIN 1.0 TRIP ALL RCPs. .
2.0 INITIATE AND CONTROL MU/HPI PER SPECIFIC RULES 1 AND 2.
3.0 MAINTAIN PROPER OTSG LEVELS.
3.1 E primary to secondary heat transfer is not excessive.
THEN increase OTSG 1evels to 93" on startup range. (See
. Specific Rule 4).
4.0 E THERE IS TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER THEN GO TO EXCESSIVE HEAT TRANSFER SECTION III C, OTHERWISE CONINTUE.
5.0 ISOIATE POSSIBLE LEAKS.
5.1 Close the PORV block valve (RC-11) and PORV (RC-2 A) .
5.2 close the letdown isolation valve (MU-2B).
5.3 Close the pressurizer spray block valve (RC-10) and pressurizer spray valve. (RC-2) 5.4 Close pressurizer vent and sample valves (RC-240A and RC-240B).
6.0 E SUBC00 LING MARGIN HAS BEEN ESTABLISHED, THEN GO TO STEP 12.0,
.OTHERWISE CONTINUE.
Section III A DATE: AGE 7-6-82 l3
l BWNP-20007 (6-76)
BABCOCK & WILCOX wumsta NUQtAR POWER GENERATION DIVISION 7'- 2 n31-00 TECHNICAL DOCUMENT 7.0 IF SUPERHEATED, THEN GO TO ICC SECTION.
7.1 E the incore T/C temperatures indicate superheat, THEN go to ICC Section, otherwise continue.
8.0 g THERE IS PRIMARY TO SECONDARY HEAT TRANSFER IN BOTH OTSGs , THEN GO TO CP-103, OTHERWISE CONTINUE.
S The RCS is saturated. A small break is indicated.
T Cooldown with the OTSGs can be performed while HPI A maintains RCS inventory.
T U
S 9.0 g THERE IS A PRIMARY TO SECONDARY HEAT TRANSFER IN ONLY ONE OTSG, THEN GO TO LACK OF HEAT TRANSFER SECTION III B, OTHERWISE CONTINUE.
10.0 g THE CFTs HAVE EMPTIED, THEN C0 TO CP-101, OTHERWISE CONTINUE.
S The core flood tanks emptying is an indication of a major T LOCA. CP-101 provides instructions for long-term core A cooling following a major LOCA. Do not g to Lack of Heat T Trans fer Section. Primary to Secondary heat transfer will be U lost and cannot be regained.
S 11,0 GO TO LACK OF HEAT TRANSFER SECTION III B.
O O
Section III A DATE: 7-6-82 PAGE 14
BWNP-20007 (6-76)
SABCOCK & WILCOX Numeen NUCLEAR POwes OSNNATON OtVISCN 74- 12n31-00 TECHNICAL DOCUMENT ADEQUATE SUBC00 LING MARGIN HAS BEEN ESTABLISHED 12.0 RESTART RCPs IF POSSIBLE 12.1 Start RCPS per SP 1103.06.
12.2 Reopen presurizer spray block valve (RC-11) and monitor RCS pressure for 5 to 30 minutes to ensure that reopening spray block valve does not cause RC depressurization.
12.3 E open pressurizer spray block valve causes significant RC depressurization, THEN close the pressurizer spray block valve.
13.0 E THERE IS LACK OF PRIMARY TO SECONDARY HEAT TRANSFER, THEN GO 10 LACK OF HEAT TRANSFER SECTION III B, OTHERWISE CONTINUE.
14.0 g THERE IS TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER, THEN GO TO EXCESSIVE HEAT TRANSFER SECTION, OTHERWISE CONTINUE.
15.0 g THERE IS INDICATION OF A SGTR, THEN GO TD SGTR SECTION III D, STEP 5.0, OTHERWISE CONTINUE, 16.0 GO TO CP-105 (Cooldown Section).
S The RCS is subcooled. There may or may not be a bubble in T the pressurizer, SG heat transfer is controlled. CP-105 A provides instructions either to draw a bubble if necessary T and then cooldown normally or to cooldown solid if a bubble U cannot be drawn.
S Section III A DATE: 7-6-82 15
Figurs III A LACK OF ADEQUATE SUBC00 LING MARGIN j fit 8
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BWNP-20007 (6-76)
.SABCOCK & WILCOX , , , , ,
NUCLEAR POWER OtNERATION OfV15CN 74- t i2n3 t-00 TECHNICAL DOCUMENT III B LACK OF HEAT TRANSFER SECTION FOLLOWUP ACTIONS FOR TREATMENT OF LACK OF PRIMARY
$ TO SECONDARY HEAT TRANSFER IN EITHER OTSG _
DETERMINE FEEDWATER AVAILABILITY i.0 IF FEEDWATER IS AVAILABLE, THEN GO TO STEP 6.0, OTHERWISE CONTINUE WITH STEP 2.0.
Section III B DATE: PAGE 16 7-6-82
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR POWit GENERATON DIYl510N TECHNICAL DOCUMENT LACK OF FEEDWATER EITHER SUBCOOLED OR SATURATED f
2.0 ESTABLISH MU/HPI COOLING.
2.1 Initiate MU/HPI (See Specific Rule 1 and 2).
2.2 Open PORV block valve (RC-11).
2.3 Open PORV (RC-2 A) .
2.4 Run one RCP as per SP 1103.06 as long as adequate subcooling margin is maintained.
3.0 INITIATE FW.
3.1 Feed both OTSGs with AFW properly controlled to thc appropriate SG level (See Specific Rule 3 and 4).
3.2 E AFW is NOT available, THEN use MAIN FW.
3.3 IF, neither AFW nor MFW is available, THEN attempt to feed both OTSGs using the start up FW pump.
3.4 E the AFW system is not operating properly, THEN refe r to the SAD section.
4.0 E FEEDWATER HAS BEEN RE-ESTABLISHED TO AT LEAST ONE OTSG, THEN GO TO STEP 6.0, OTHERWISE CONTINUE.
5.0 E NEITHER OTSG CAN BE FED, THEN GO TO CP-104.
S There is no heat transfer to either OTSG. Natural circulation T does not exist and cannot be induced due to a total loss of A fe edwa t er . The SGs are dry and the core must be cooled by T MU/HPI cooling.
U S
O'Section III B DATE: 7-6-82 PAGE 17
BWNP-20007 (6-76)
BABCOCK & WILOOX NUCitAt POWEa GENERATION DIVISION 7'- n 25s31-00
(~') TECHNICAL DOCUMENT V
FEEDWATER HAS BEEN RE-ESTABLISHED BUT THERE IS NO HEAT TRANSFER 6.0 MAINTAIN APPROPRIATE OTSG LEVEL.
6.1 See Specific Rule 3 and 4.
,- 7.0 E THE CFTs HAVE E'{PTIED, THEN_ GO TO CP-101, OTHERWISE CONTINUE.
/ 'T
\ i S The Core Flood Tanks emptying is an indication of a major T LOCA. CP-101 (Cooldown section) gives instructions for long-A term cooling following a major LOCA. Primary to secondary T heat transfer is lost and cannot be regained .
U S
8.0 IF AT ANY TIME WilILE ATTEMPTING TO REGAIN HEAT TRANSFER TO THE OTSG, THE RC PRESSURE INCREASES TO THE PORV SETPOINT, THEN OPEN THE PORV, IF NOT ALREADY OPEN, REDUCE RC PRt.SSU RE TO < 100 PSI ABOVE J'7_ \
! ) THE OTSG PRESSURE AND THEN RESHUT THE PORV.
'm j 9.0 LOWER OTSG PRESSURE TO INDUCE HEAT TRANSFER.
9.1 Lowe r OTSG pressure by adjusting TBVs or AVVs while maintaining OTSG 1evel, until secondary Tsat is 40 to 60F lower than core exit thermocouple temperature.
Maintain this OTSG pressure.
1.0.0 g AT ANY TIME WHILE PERFORMING SECTION III B, OTSG HEAT TRANSFER
[ j IS RE-ESTABLISHED, THEN CO TO STEP 16.0 UNTIL THEN, CONTINUE.
\d 10.1 E heat trans fe r is re-established after either Steps 9.0, 12.0 or 13.0, THEN go to Step 16.0.
I1.0 IF RCPs CANNOT BE BUMPED, THEN INITIATE MU/HPI COOLING AND GO TO CP-104, OTHERWISE CONTINUE.
11.1 Determine RCP operability per SP 1103.06.
[m}
\ /
S T
There is no heat transfer to either OTSG. Natural circulation does not exist and cannot be induced by bumping RCPS. The A the core must be cooled by HPI.
U S
Section III B DATE: 7-6-82 PAGE 18
l BWNP-20007 (6-76)
BABCOCK & WILCOX Numset NUCLEAR POWit GENERAflON DIYl540N 74- t i2 n 31-00 TECHNICAL DOCUMENT l
12.0 USE PUMP BUMPS TO INDUCE OTSG HEAT TRANSFER.
12.1 Bump a RCP, which is capable of being started, in the loop with the highest level in the SG.
12.2 Allow RCS pressure to stabilize (within i 20 psig) at new pressure be fore determining if heat t rans fer is established.
12.3 When heat transfer is established, THEN go to Step 16.0, until then, continue.
12.4 Repeat Steps 12.1 through 12.3 for operable RCPs that have not been bumped. Allow 15 minutes between pump bumps. E all operable RCPs have been bumped and heat trans fer has NOT been re-established, THEN continue with Step 13.0.
13.0 FURTHER LOWER OTSG PRESSURE TO INDUCE OTSG HEAT TRANSFER 13.1 Lower OTSG pressure by adjusting TBVs or AVVs main-taining the appropriate OTSG level, until secondary Tsat is 90 to 110F lower than core exit thermocouple t empe ra ture . Maintain this pressure.
14.0 START ONE RCP TO INDUCE OTSG HEAT TRANSFER.
14.1 g at least one hour has passed since reactor trip AND any RCPs are capable of being aiarted, THEN start and run one RCP pre ferably in a loop with a OTSG level at least 40".
15.0 g HEAT TRANSFER HAS NOT BEEN RE-ESTABLISHED, THEN INITIATE MU/HPI COOLING (IF NOT ALREADY IN PROGRESS) AND CO 'ID CP-104, OTHERWISE CONTINUE AT STEP 16.0.
S There is no heat transfer to either OTSG, attempts to T catablish heat transfer by natural circalation and forced U flow have failed. The core must be cooled by MU/HPI T _ COOLING.
Section III B DATE: 7-6-82 PAGE g
BWNP-20007 (6-76)
BABCOCK & WILCOX NUmnEn NucteAn powen oewenATON DMSON TECHICAL DOCUMENT HEAT TRANSFER HAS BEEN RE-ESTABLISHED 16.0 RECOVER FROM MU/HPI COOLING, IF INITIATED 16.1 Close PORV (RC-2A), if PORV does not close, close PORV block valve (RC-11) .
16.2 Control MU/HPI (see Specific Rule 2) .
17.0 CONTROL HEAT TRANSFER RATE 17.1 Adjust TBV or AVVs position to maintain RC temperature at present value.
18,0 F THERE IS ADEQUATE SUBC00 LING MARGIN, THEN GO TO CP-105 S- The RCS is subcooled. There may or may not be a bubble in the T pres sur ize r . OTSG heat transfer is controlled. CP-105 provides A instructions either to draw a bubble if necessary then cooldown T nomally or 'cooldown solid if a bubble cannot be drawn.
U S
19.C F I_F, THERE IS A LACK OF ADEQUATE SUBC00 LING MARGIN, THEN CO TO CP-103.
S The RCS is saturated. A small break is indicated. Cooldown
. T with the OTSGs can be performed while MU/HPI maintain RCS in-A ve nto ry .
T U
S Section III B DATE: 7 6-82 PAGE 20
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BWNP-20007 (6-76)
BABCOCK & WILCOX . u.
" " " " " " * " 74-1125531-00 TECHICAL DOCUMENT __
III C EXCESSIVE HEAT TRANSFER FOLLOW-UP ACTIONS FOR TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER 1.0 E PRESSURIZER LEVEL IS BELOW 100" AND RCS PRESSURE IS DECREASING, THEN INCREASE MAKEUP FLOW TO MAINTAIN PRESSURIZER LEVEL ABOVE 100".
2.0 ISOLATE LETDOWN.
2.1 Close MU-2B.
' ' 3.0 EA FULL SFRCS ACTUATION HAS OCCURRED , THEN GO TO STEP 7.0, OTHERWISE CONTINUE. ,
4.0 IF EITHER OTSG LEVEL IS > 95? ON THE 0*i:; RATE RANGE OR PRESSURIZER LEVEL DROPS BELOW 50 INCHES), THEN TRIP THE MFW PUFPS AND GO TO STEP 7.0, OTHERWISE CONTINUE.
.5.0 E IT IS APPARENT WHICH OTSG IS CAUSING THE OVERCOOLING, THEN CO TO STEP 23.0, OTHERWISE CONTINUE.
6.0 MANUALLY ACTUATE SFRCS WITH LOW OTSG LEVEL ACTUATION CHANNELS 1 AND 2.
5 k
Section III C DATE: ^
7-6-82 21
BWNP-20007 (6-76)
BABCOCK & WILCOX Nuusta NUCLEAR POWER GENERATPON OlVISION 7'- 2ss31-00 TECHNICAL DOCUMENT 7.0 VERIFY PROPER SFRCS ACTUATION.
7.1 Verify that all SFRCS equipmert has properly actuated in accordance wtih Table 1.
7.2 IF, the AFW system is not operating properly, THEN refer to SAD section.
8.0 g OTSG LEVELS AND PRESSURES ARE STABILIZING IN BOTH OTSGs , THEN GO O
TO STEP 18.0, OTHERWISE CONTINUE.
9.0 E OTSG LEVELS AND PRESSURES ARE STABILIZING IN ONE OTSG AND THE OTHER OTSG IS BOILING DRY, THEN a) Manually actuate SFRCS with low steam pressure actuation chanr.els 1 and 2 on steam leak OTSG AND b) Go to Step 27.0, OTHERWISE continue.
O O
O Section III C DATE: 7-6-82 PAGE 22
BWNP-20007 (6-76)
BABCOCK & WILCOX NMH NUC1tAA POwte GENERATION DIVISION 74-112n31-00 TECHNICAL DOCUMENT EXCESSIVE AFW TO ONE OR BOTH OTSG'S, OR AFW TO STEAM LEAK OTSG
-10.0 ISOLATE AFW TO BOTH OTSGs.
10.1 Close or verify closed AF-3869, AF-3870, AF-3871 and AF-3872.
11.0 IDENTIFY THE OTSG(s) WITHOUT A STEAM LEAK.
11.1 The OTSG with decreasing level and/or pressure has a steam leak.
12.0 RE-ESTABLISH AFW TO THE OTSG(s) WITHOUT A STEAM LEAK.
12.1 Open appropriate AFW discharge valve to the OTSG(s) without a steam leak (AF 3870 for SG-1 of AF-3872 for SG-2).
13.0 MAINTAIN APPROPRIATE LEVEL IN THE OTSG(s) WITHOUT A STEAM LEAK.
13.1 See Specific Rule 3 and 4.
14.0 MAINTAIN RCS TEMPERATURE CONSTANT.
14.1 Override AVV control on the OTSG(s) without a steam leak and position as necessary to maintain RCS tempe rature at present value.
14.2 E the AVV's are not operating properly, 'nlEN refer to SAD section.
15.0 g THERE IS INDICATION - 0F A SGTR, 'IMEN GO TO SGTR SECTION III D, STEP 5.0, OTHERWISE CONTINUE.
Section III C DATE: 7-6-82 PAGE 23
l BWNP-20007 (e -76)
BABCOCK & WILCOX NUctEAR POWER GENERATION OtVISION 74-ti2 n 3i-oO
- TECHNICAL DOCUMENT l
16.0 IF SUBC00 LING MARGIN IS NOT ADEQUATE, THEN GO 10 LACK OF ADEQUATE SUBCOOLING MARGIN SECTION III A, OTHERWISE CONTINUE.
I 17.0 GO TO CP-102.
S The RCS is subcooled and stable with one or two OTSGs steaming T through the AVV.
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O Section III C DATE: 7-6-82 PAGL 24
BWNP-20007 (6-76)
BABCOCK & WILCOX , , , ,
wucteAn Powen oewsRADON DMSON 74-1125531-00 TECNNICAL DOCUMENT BOTH OTSG's ISOLATED AND BOTH OTSG's PRESSURIZED WITH AFW 18.0 MAINTAIN APPROPRIATE LEVELS IN BOTH OTSGs WITH AFW, 18.1 See Specific Rule 3 and 4.
19.0 MAINTAIN RCS TEMPERATURE CONSTANT.
19.1 Ove rride AVV control and control the AVVS or both OTSGs as required to maintain RCS temperature at present value.
19.2 F the AVV's are not operating properly, THEN refer to SAD Section.
20.0 F THERE IS INDICATION OF A SGTR, THEN GO TO SGTR SECTION, STEP 5.0, OTHERWISE CONTINUE.
21.0 F SUBC00 LING MARGIN IS NOT ADEQUATE, THEN GO TO SUBC00 LING SECTION, OTHERWISE CONTINUE.
22.0 GO TO CP-102.
S The RCS is subcooled and stable with both OTSGs steaming through T the AVV's to the atmosphere.
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Section III C DATE: 7-6-82 PAGE 25
I BWNP-20007 (6-76)
BABCOCK & WILCOX Nu m te Nuct Aa rowra GtNtaADON DIVISION _ _
TECHNICAL DOCUMENT OVERCOOLING OTSG IS APPARENT 23.0 CLOSE THE MSIV AND AVV AND CONTROL MFW ON THE STEAM LEAK OTSG.
23.1 Close MS-100 or MS-101 as required.
23.2 Close ICS-llA or ICS-llB as required.
24.0 g OTSG LEVELS AND PRESSURES HAVE STABILIZED IN THE STEAM LEAR OTSG, TilEN GO TO STEP 33.0, OTHERWISE CONTINUE.
25.0 MANUALLY INITIATE SFRCS ACTUATION CHANNELS 1 & 2 FOR THE STEAM LEA _K OTSG.
26.0 VERIFY PROPER SFRCS ACTUATION.
26.1 Verify that all SFRCS equipment has properly actuated in accordance with Table 1 for low steam line pressures.
26.2 IF the AFW system is not operating properly, THEN refer to SAD Section, 9
O Section III C DATE: PAGE 26 7-6-62
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BABCOCK & WILCOX NUCLEAR POWtt OtNERATON DIVISION 74-1 23331-00 O TECHICAL DOCUMENT v
BOTH OTSG's ISOLITED AND ONE OTSG PRESSURIZED WITH AFW 27.0 MAINTAIN APPROPRIATE LEVEL IN OTSG WITH AW AND WITHOUT STEAM LEAK.
27.1 See Specific Rule 3 and 4.
28.0 ALLOW THE STEAM LEAK OTSG TO BOIL DRY. ' HEAT TRANSFER WILL BE LOST IN THE STEAM LEAK OTSG. DO NOT GO TO 1ACK OF HEAT TRANSFER SECTION.
29.0 MAINTAIN RCS TEMPERATURE CONSTANT.
29.1 Override AVV control on the good OTSG and position as necessary to maintain RCS temperature at present value.
29.2 E the AVV is not operating properly, THEN refer to SAD Section.
\ 30.0 g THERE IS AN INDICATION OF A SGTR, THEN GO 'IO SGTR SECTION, STEP 3.0, OTHERWISE CONTINUE.
31.0 E SUBC00 LING MARGIN IS NOT ADEQUATE, ,' ~ GO TO SUBCOOLING SECTION, OTHERWISE CONTINUE.
32.0 GO TO CP-102.
S The RCS is subcooled and stable with one OTSG steaming through T the AVV. The other OTSG has an unisolable steam leak.
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S Section III C DATE: PAGE 7-6-82
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EWNP-20007 (6-76)
BABCOCK & WILCOX NUMt ER NUCtfAR POWER GENERATION 01vlSION 74-1125531-00 TECHNICAL DOCUMENT ONE OTSC ISOLATED AND BOTH OTSG's PRESSURIZED WITH MFW SUPPLY 33.0 MAINTAIN APPROPRIATE LEVELS IN BOTH OTSGs, 33.1 See Specific Rule 3 and 4.
34.0 MAINTAIN RCS TEMPERATUR3 CONSTANT.
34.i Control the TBVs on the OTSG without a steam leak and the AVVs on the isolated OTSG as required to maintain RCS temperature at present value.
34.2 IF the TBS and AVV are not operating properly, THEN refer to SAD section.
35.0 I_F,THERE F IS INDICATION OF A SGTR THEN GO TO SGTR SECTION STEP 5.0, OTHERWISE CONTINUE.
36.0 I F, SUBCOOLING MARGIN IS NOT ADEQUATE, THEN GO TO SUBC00 LING SECTION, OTHERWISE CONTINUE.
37.0 GO TO CP-102.
S' The RCS is subcooled and stable with one OTSG steaming through T the TBVs to the condenser. The other OTSG is isolated because A of a stean leak downstream of its MSIV.
O Section III C DATE: 7-6-82 PAGE 28
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BABCOCK & WILCOX Numen NucteAn Powea oeNenADON Dm$10N g TECHNICAL DOCUMENT III D STEAM GENERATOR TUBE RUPTURE FOLLOWUP ACTION FOR OTSG TUBE RUPTURE
( 1.0 IF THE REACTOR IS TRIPPED, GO TO STEP 4.0, OTHERWISE CONTINUE.
REACTOR TRIP HAS NOT OCCURRED 2.0 INITIATE MU/HPI IF REQUIRED.
2.1 E pressurizer level is being maintained by the makeup system, THEN go to Step 3.0, otherwise continue.
2.2 Increase MU as required to maintain pressurizer level greater than 100".
2.3 y pressuzier level cannot be maintained, THEN trip the reactor and go to Step 4.0, otherwise continue.
2.4 Isolate letdown.
3.0 SHUTDOWN REACTOR.
3.1 Immediately begin power reduction at as fast a rate as can be controlled.
3.2 I_f, f the reactor trips during runback, THEN perform the immediate actions and verifications of Section I and
\v Section II.
3.3 Make local survey of main stean line to confirm high radiation alarms and identify the tube ruptured OTSG.
3.4 At less than 25% reactor power:
- a. Place the TBVs in manual,
- b. Ensure site loads are transferred Section III D DATE: 7-6-82 PAGE 29
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BABCOCK & WILCOX Numsen NUCLEAR POWER GENERATION DIVISION 74-1125531-00 TECHNICAL DOCUMENT
- c. Open TBVs
- d. Unioad ar.d " trip" turbine / generator.
- e. Verify reactor trip.
- f. Immediately place the TBVs back in automatic with the appropriate pressure setpoint or control header pressure in manual (at operator discretion).
- g. Continue with Step 4.0.
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O Section III D DATE- PAM 30 7-6-82
BWNP-20007 (6-76)
BASCOCK & WILCOX wumeen NWCLtAR POwet GENERATION DIVISION
'"*"~
TECHICAL DOCUMElli REACTOR TRIP HAS OCCURRED 4.0 PERN RM THE IMMEDIATE ACTIONS AND VERIFICATION OF SECTION I AND
.SECTION II.
5.0 CONTROL MU/HPI AS REQUIRED.
5.1 I_F, adequate subcooling margin is lost, THEN perform the following, otherwise continue.
- a. Trip the RCPs
'b. Initiate MU/HPI
- c. Go to Step 6.0.
5.2 IF, pressurizer level is being maintained by the MU system THEN go to Step 6.0, otherwise continue.
5.3 E pressurizer, level cannot be maintained above 100" by the MU . sys tem , THEN supplement MU s'lition with HPI and LPI' in the " piggy back" mode. IF, piggy back mode is des ired , THEN depressurize the RCS to 1700 psig (use the PORV if par spray is not available).
6.0' PREPARE FOR COOLDOWN.
6.1 Isolate letdown (MU-2B).
6.2 Turn off all pressurizer heaters.
6.3 -Ensure that local survey of main steam line is being made to confirm high radiation alarms and verify the tube ruptured OTSG.
6.4 Bypass SFRCJ during plant cooldown to prevent auto clo-sure of the Pt:Vs.
6.5 IF, MU/HPI wat initiated, THEN begin makeup to the BWST from an appropriate source.
7.0 E THE REACTOR COOLANT PUMPS ARE RUNNING, THEN C0 TO STEP 16.0, OTHERWISE CONTINUE.
8.0 g OFFSITE POWER IS AVAILABLE BUT RC PUMPS ARE NOT RUNNING, THEN GO TO STEP 13.0, OTHERWISE CONTINUE.
9.0 g' LOSS-OF-OFFSITE POWER HAS OCCURRED, THEN CONTINUE WITH STEP 10.0.
Section III D DATE: 7-6-82 PAGE 31
BWNP-20007 (6-76) l BABCOCK & WILCOX Nuusek j NUcttAR POWER GENERATION DIVI $10N 74- 125531-00 TECHNICAL DOCUMENT LOSS OF OFFSITE POWER HAS OCCURRED 10.0 MIEN OFFSITE POWER IS RESTORED, THEN 00 TO STEP 13.0, OTHERWISE CONTINUE.
10.1 Restore of fsite power as soon as possible.
11.0 BEGIN 000LDOWN AND DEPRESSURIZATION WITH LOSS-OF-OFFSITE POWER.
O 11.1 Verify that SG 1evels are increasing to the appropriate OTSG level with AFW prope rly controlled. (see Specific Rule 3).
11.2 IF a OTSG has a stream leak, THEN feed the leaking OTSG as necessary (approximately 100 gpm) through the MFW nozzles (AFW nozzles if MFW not availalbe) to maintain tube to shell AT less than 150F.
11.3 AS SOON AS the tube ruptured SG in ident i fied , feed it only as needed to maintain the low level limit, to promote natural circulation, to maintain adequate subcooling margin, or to maintain tube to stell AT requirements. Steam the tube ruptured OTSG as necessary to prorc.ote natural circulation.
11.4 VERIFY Instrument Air Compres sor running for air supply to AVVs.
11.5 Depressurize the RCS to as close as pos sible to the adequate subcooling magin curve by opening the PORV (RC-2 A) .
11.6 As quickly as possible, begin cooldown of the RCS with the AVVs (ICS-IIA and ICA-11B) initially using both stean generators if possible, 11.7 Initiate a rapid cooldown to 500F (do not exceed a C/D rate of 240F/hr).
11.8 MIEN a 50F subcooling margin is obtained, THEN depressurize the RCS to as close as pos s ible to the adequate subcooling margin curve by opening the PORV.
Section III D DATE: 7-6-82 PAGE 32
BWNP-20007 (6-76)
-BABCOCK & WILCOX NUCLEAR POwet GENERATION DIVISION 74- 123331-00 TECHNICAL ~ DOCUMENT (Increase the subcooling margin as necessary to obtain abou t 30F colder than the adequate subcooling margin curve before opening the PORV).
11.8 During the depressurization and cooldown, control the AVVs as necessary to prevent the MSSVs from opening.
12.0 GO TO STEP 17.0.
S No offsite power is available. The RCS is being depressurized T by the opening the PORV. The RCS is being cooled with the AVVs.
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Section III D DATE: A 7-6-82 33
BWNP-20007 (6-76)
BABCOCK & WILCOX NuutEt NUCLEAR POWER GfNERAiloN DIVISION 74-ii25531-00 TECHNICAL DOCUMENT REACTOR COOLANT PUMPS NOT RUNNING 13.0 WHEN ADEQUATE SUBCOOLING MARGIN IS OBTAINED, THEN RESTART RCPs.
13.1 Start one RCP in each loop (Preferred 1-2 and 2-2 running), THEN go to Step 16.0, otherwise continue.
13.2 E unable to start a RCP in one loop, THEN attempt to start both RCPs in one loop. E successful, THEN go to Step 16.0, otherwise continue.
13.3 E only one RCP was started AND the RCP is in the loop with the pressurizer spray line, THEN go to Step 16.0, otherwise continue.
14.0 BEGIN C00LDOWN AND DEPRESSURIZATION WITHOUT RCPs.
14.1 Verify that OTSG levels are increasing to the appropriate level with AFW properly controlled. (see Specific Rule 3 - ad 4 ) .
14.2 Ea OTSG has a steam leak, 'niEN feed the leaking OTSG as necessary (approximately 100 gpm) through the MFW nozzles (AFW nozzles if MFW not available) to maintain tube to shell AT less than 150F, 14.3 AS SOON AS the tube ruptured OTSG is identified, THEN feed it only as needed to maintain the low level limit.
to promote natural circulation, to maintain adequate subcooling margin, or to maintain tube to shell AT requirements. Steam the tube ruptured OTSG as necessary to promote natural circulation.
14.4 Initiate a rapid cooldown to 500F (do not exceed a C/D rate of 240 F/hr).
14.5 Use TBVs initially on both OTSGs if possible.
14.6 Use AVVs if TBVs are not available.
O Section III D DATE: PAGE 34 7-6-82
BWNP-20007 (6-76)
BABCOCK & WILCOX wu een 74-1125531-00 TECMICAL DOCUMENT 14.7 I_F, th e RCPs cannot be restarted within 10 minutes after they tripped or were tripped, THEN:
- a. Depressurize the RCS to as close as possible to the adequate subcooling margin curve by opening 'the PORV. (RC-2A)
- b. Whenever a 50F' subcooling margin is obt a i nad , de-pressuize the RCS to as close as pos s ible to the adequate subcooling margin curve by opening the PORV. (Increase the subcooling margin as necessary to obtain about 30F colder than the adequate subcooling margin curve before opening the PORV).
- c. Continue cooldown and depressurization in this manner until the RCPs can be restarted per Step 13.0. The continue with Step 16.0.
- d. IF RCPs cannot be restarted, THEN continue with Step 15.0.
15.0 CO TO STEP 17.0.
9 Section III D
- DATE: .7-6-82 PAGE 35
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BABCOCK & WILCOX Numsen NUCLEAR POWER GENERATION DIYiSION
~'*2"*~
TECHNICAL DOCUMENT REACTOR COOLANT PUMPS ARE RUNNING 16.0 BIT,1N C00LDOWN AND DEPRESSURIZATION WITH RCPs.
16.1 Ensure appropriate steam generator level is maintained (see Specific Rule 3.0). Begin depressurizing the RCS to as close as possible to the adequate subcooling margin curve by opening the pressurizer spray valve (RC-2).
16.2 Ea OTSG has a steam leak, THEN feed the leaking OTSG as necessary (approximately 100 gpm) through the MFW nozzle (AFW nozzle if MFW not availablel to maintain tube to shell AT less than 150F.
16.3 As quick 1- as po s s ib le , begin cooldown of the RCS with the TBVs iaitially on BOTH steam generators if possible.
Use AVVs if TBVs are not available.
16.4 E the SGTR leak rate is greater than the capacity of one no rmal MU pump OR the conde nse r is NOT available, THEN initiate a rapid cooldown to 5000F (do not exceed a C/D rate of 240 F/hr).
16.5 Continue spraying the pressurizer as necessary to remain as close as possible to the adequate subcooling margin.
16.6 Continue with Step 17.0.
O O
Section III D DATE: 7-6-82 PACE 36
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BABCOCK & WILCOX wuuna wucttaa powen ocNfSADON DIVISION 74-1125531-00 O TECHNICA!. DOCUMENT I
U COOLDOWN HAS BEGUN USING BOTH SGs 17.0 CONTROL THE TUBE RUPTURED OTSG TO PREVENT RADIATION RELEASE. -
17.1 IF MSIV's are shut THEN make condenser available AND open MSIV(s) on OTSG(s) without stean leak AND stean to condenser.
17.2 During the depressurization and cooldown control the TBVs as necessary to prevent the MSSVs from opening .
Use AVVs if TBVs are not available.
18.0 ISOLATE THE TUBE RUPTURED OTSG:
18.1 IF the SG without the tube rupture is not operable, THEN go to Step 19.0 and continue cooldown with the tube ruptured OTSG, otherwise continue.
18.2 AS SOON AS the tube ruptured OTSG is identified AND the RCS is below 540F, THEN isolate the tube ruptured OTSG by closing its respective valves as follows:
NAME/ FUNCTION #1 SG #2 SG MFW Stop Valve FW 612 FW 601 Atmospheric Vent Valve ICS 11B ICS 11A NOTE: If AVV is known to be leaking and is not needed for cooldown it can be isolated with the manual isolation valve. (MS 875) (MS 876)
MS Line UP-Stream Warmup Drain MS 394 (MS703) MS 375 (MS700)
MS Line' Sample Connection Isolate at STM Isolate at SIM & FD FD Sample Panel Sample Panel with with SS 350 SS 340 p MS Supply to MFPT MS 706 and bypass MS 707 and bypass f, i ST 66 and bypass ST 67 and bypass
\ '
MS Supply to AS' Reducer MS850 MS851 Section III D DATE: 7-6-82 PAGE 37 ,
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BWNP-20007 (6-76)
BABCOCK & WILCOX HUmsta HUCLtAR POWER GENERATION Div6510N 74- t i 25531-00 -
TECHNICAL DOCUMENT NAME/ FUNCTION (CONT'D) #1 SG #2 SG MS Supply to MSR Second Stage MS199 MS 314' Reheat MS199A MS314A MS2582 TBV's and Drains SP13B1 (MS714) SP13Al (MS711)
SP13B2 (MS715) SP13A2 (MS712)
SP13B3 (MS715) SP13A3 (MS713)
SP2572 (MS736) MS2575 (MS737)
ST28 and bypass ST3 and bypass ST28A and bypass ST3A and bypass MS Line Stub Header Drains MS266 (MS847) MS138 (MS841)
ST101 and bypass ST100 and bypass Turbine Stop Valve Above Seat MS1299B (MS845) MS1299A (MS843)
Warmup Line MS Supply to GS Header GS2384 GS2385 18.3 Switch BOTH auxiliary and main feed pump steam supplies O to the good OTSG.
18.4 Initiate steaming as nec es sary to maintain the SG pressure below 1000 psig and OTSG level below 95% on the operate range on the tube ruptured OTSG.
18.5 Transfer the steam supply from the auxiliary steam header to the auxiliary boilcr.
18.6 To minimize radioactive releases to the environment refer to SP 1104.45, STATION DRAINAGE System.
18.7 When 500F is reached , THEN continue with Step 19.0.
O Section III D DATE:
7-6-82
BWNP-20007 (6-76)
BABCOCK & WILCOX "
NyctEAR POWER GENERATION DIVI $loN 7'-t i 25 531-00 TECHNICAL DOCUMENT PLANT IS COOLING DOWN WITH ONE SG ISOLATED 19.0 CONTINUE C00LDOWN WITH APPLICABLE LIMITATIONS.
19.1 When RCS pres sure and le ak rate decrease AND RCS inventory and sti :ooling can be maintained by the MU G systen, THEN establish normal MU control.
19.2 Continue depressurization and cooldown at the maximum at tainable C/D rate without exceeding 100 F/hr using the OTSG without the tube rupture.
19.3 Cooldown on the tube ruptured OTSG if the other OTSG is not operable.
19.4 Decrease the RCS pressure as required to remain as close as possible to the minimum subcooling margin line.
19.5 IF, an unisolable steam line break has occurred, THEN feed G 19.6 that OTSG as necessary to provide shell cooling.
F tube to shell AT approached 100F, (or 150F if emergency condition) THEN slow cooldown as necessary.
19.7 IF the tub e to shell AT exc eed s 100F (or 150F if eme rgency condtiion) THEN stop the cooldown. Resume C/D Wen tube to shell AT is less than 100F (or 150F if emergency condtion).
19.8 Request additional C&HP personnel to check for pos s ible contanination at the site and to monitor turbine building G
radiation levels.
19.9 Place hotwell control in MANUAL and close Hotwell High Level Return Valve to the CST (CD-550B). At a later t ime , it may be neces sary to divert conde ns ate to the CSTs if the hotwell level reaches 7 feet.
19.10 Bypass SFRCS low OTSG pressure trip when OTSG pressure reaches the SFRCS bypass setpoint.
G 1
Section III D DATE: PAGE 39
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BABCOCK & WILCOX Nuusen NUCLEAR POWER GENERATION OlVl$10N 74-1125531-00 TECHNICAL DOCUMENT 20.0 CONTINUE CDOLDOWN PER PP1102.10 USING ONLY ONE OTSG. OBSERVE THE FOLLOWING PRECAUTIONS:
20.1 Stean the tube ruptured OTSG as necessay to prevent filling the OTSG.
20.2 WHEN steaming is not longer pos s ib le , THEN drain the OTSG as necessary to the condenser to prevent filling the OTSG.
20.3 Depres sur ize the RCS as close to subcooling margin line as possible to minimize the tube leak rate driving force.
20.4 Feed OTSG s as necessary to maintain tube to shell AT less than 100 (or 150F if emergency cooldown).
20.5 Ma int ain condensate demineralizer in operation to remove activity from condenste.
20.6 Continue cooldown and drain OTSGs as soon as pos sible to stop the leak.
S The tube ruptured OTSG has been identified and feeding and T steaming of the tube ruptured OTSG has been limited as much A as possible.
T U
S O
O Section III D DATE: PAGE 40 7-6-82
i BWNP-20007 (6-76)
BABCOCK & WILCOX III NUCLEAR POWER GENERATION DIVI $lON 74- 125531-00 V
] TECHNICAL DOCUMENT CP-101 A LARGE LOCA HAS OCCURRED AND THE CORE FLOOD TANKS ARE EMPTYING
, 1.0 VERIFY AUTOMATIC SFAS ACTIONS PER SECTION II.
2.0 F THE RCS PRESSURE STABILIZES ABOVE THE MAXIMUM OPERATING PRESSURE FOR LPI, THEN:
3.0 CONTROL HPI FLOW.
[
3.1 See Specific Rule 1.
3.2 See Specific Rule 2.
,/ 3.3 WHEN the BWST level drops to 8 feet THEN align HPI to take
- suc t ion from the LPI system AND stop MU pumps if the MU tank becomes unavailable for suction.
3.4 WHEN the LPI flow has been greater than 1000 gpm per line for at least 20 minutes, THEN Stop HPI.
4.0 WHEN THE BWST LEVEL DROPS TO 8 FEET, THEN ALIGN THE LPI TO TAKE SUCTION FROM THE CTMT EMERGENCY SUMP.
4.1 Ensure that CTMT spray valves throttle to 57% flow.
5.0 ISOLATE MAJOR CTMT PENETRATIONS 5.1 Close the following to isolate the steam generators:
- MFW Block Valve FW-780 FW-779 S/U FW Valve SP-7B SP-7A MSIV MS-101 MS-100 MSIV Byp. MS-101- 1 MS-100-1 5.2 Stop AFW pumps and close AFW turbine steam supply valves, s
Section CP-101 DATE: 7-6-82 PAGE 41
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BABCOCK & WILCOX Nuuset NucLtAR POWER GENERATION DIVI $ ION , ,
TECHNICAL DOCUMENT 6.0 ESTABLISH LONG-TERM COOLING.
6.1 Continue LPI cooling until further instructions are given.
6.2 Close PORV block valve, (RC-II).
6.3 Continue with unit shutdown /cooldown pe r PP 1102-10 while perferming the following steps.
6.4 g any of the following occur:
a) RB pressure is greater than or equal to 18.4 psia O_R b) RB temperature is greater than or equal to high CTMT temperature limit.
THEN start 2 CTMT air coolers with maximum SW to coolers.
6.5 Sample RCS and maintain fluid pH and boron per PP 1101.04.
6.6 Secure the RB Spray System when RB pr es sure decreases to 18.4 psia. Spray system may be run longer to aid in removing airborne iodine.
6.7 g any of the fcilowing occur:
a) RB radiation is greater than the high RB radiation limit 0,,R, b) RB H2 concentration is greater than .2% vol.
THEN start the CTMT recirculation system.
6.8 Monitor the hydrogen level in CTMT. Start the hydrogen dilution system and purge as required by SP 1104.54 (CTMT i RECIRC) and SP 1104.55 (CTMr hydrogen dilution).
O O
Section CP-101 DATE: PAGE 7-6-82
BWNP-20007 (6-76) ,
BABCOCK & WILCOX NUMSER NUCLEAR POWER GENERATION DIYl560N 7'- 23331-00 TECHNICAL DOCUMENT _
CP-102 NORMAL COOLDOWN 1.0 CONTROL MU/HPI 1.1 See Specific Rule 2.
2.0 ESTABLISH CONDENSER COOLING IF POSSIBLE.
2.1 SFRCS actuation may have necessitated breaking condenser vacuum, if so, draw a vacuum in the condenser if vacuum was lost.
2.2 Open the MSIV bypass on the non-s t eam leak steam generator, equalize pressure.
2.3 Transfer cooling from the atmosphere to the condenser.
3.0 START RCPs.
3.1 If natural circulation is in progress and RCP's can be started, then start one pump / loop per SP 1103.06.
4.0 IF BOTH OTSG'S ARE IN SERVICE. THEN GO TO PP 1102.10 (C00LDOWN FROM HOT STANDBY). OTHERWISE CONTINUE.
5.0 PREPARE FOR COOLDOWN WITH A DRY SG.
5.1 Calculate the existing tube to shell AT for the dry SG.
ISG Shell T/C T= _
number of T/C's T= F. This value must not exceed + 1000F.
Section CP-102
^ ' PAGE 7-6-82 43
BWNP-20007 (6-76)
BABCOCK & WILCOX NuusEn NUCLEAR POWER GENERATION DIVISION 7'- u25531-00 TECHNICAL DOCUMENT 5.2 When the AT, as determined in Step 5.1 above, is <100 F.
THEN open bypass valves on the operable SG and commence 0
cooldown. 3 NOT exceed 100 F tube to shell AT on the dry SG.
5.3 IF reactor coolant flow is natural circulation, THEN use the PORV to depressurize the RCS.
5.4 I_F F the BWST level reaches 8 feet, THEN switch to HPI piggy back with LPI providing suction from the CTKr sump.
5.5 Continue with PP 1102.10. (Cooldown with one OTSG) .
O O
O Section CP-102
BWNP-20007 (6-76) 8ABCOCK & WILCOX 'II NUCLEAR POwlt GENERATION Otvi$lON
~
TECHNICAL DOCUMENT 74-1125531-00 CP-103 4
TRANSIENT TERMINATION'FOLLOWING AN OCCURRENCE THAT LEAVES THE RCS SATURATED WITH OTSGs REMOVING HEAT 1.0 VERIFY THAT HEAT TRANSFER IS BEING CONTROLLED.
1.1 Verify maximum MU/HPI flow (see Specific Rule 1).
l.2 Control OTSG Levels per Specific Rule 3.
2.0 IF THE CORE FLOOD TANKS ARE EMPTYING DUE TO A LARGE BREAK LOCA, THEN
$ GO TO CP-101, CTHERWISE CONTINUE.
3.0 ENSUREtTHE CFT ISOLATION VALVES (CF-1A and CF-1B) REMAIN .0 PEN.
4.0 BEGIN C00LDOWN OF RCS.
4.1 Increase OTSG steaming by opening the TBVs or AVVs.
4.2 Verify that OTSGs continue to provide a heat sink for the RCS by:
a). Incore T/C temperature decreases as OTSG pressure is lowered AND b) The OTSGs remain pressurized.
4.3 . Continue saturated cooldown by decreasing OTSG pressure.
4.4 Block SFRCS on low steam line pressure as appropriate.
. 4.5 If the RCS does not cooldown as the OTSGs are depress-urized, bump a RCP to reestablish heat t rans fer .
4'6
. g the BWST level drops to a 10 ft level, THEN begin makeup to the BWST with borated water.
5.0 IF, HEAT TRANSFER TO OTSGs CANNOT BE MAINTAINED , THEN GO TO CP-104, OTHERWISE CONTINUE.
s Section CP-103 DATE: 7-6-82 PAGE 45
BWi4P-20007 (6-76)
BABCOCK & WILCOX NUCLEAR POWER GENERATION OlVi$10N 74-1125531-00 TECHNICAL DOCUMENT 6.0 g Tile RCS, BECOMES SUBCOOLED AND A RCP CAN BE OPEPATED , TilEN START A RCP AND CD TO CP -105.
6.1 Start one RCP (per SP 1103.06) preferably in the loop with pressurizer spray.
6.2 Detetuine if subcooled conditions exist by verifying s ubcooled conditions on the incore T/C, hot leg RTDs and cold leg RTDs.
7.0 g Tile RCS t(EMAINS SUBCOOLED AFTER STARTING THE RC PUMP , THEN GO TO CP-105, OTHERWISE CONTINUE.
8.0 g FOR ANY REASON THE RCS BECOMES SUPERHEATED, nlEN C0 TO THE ICC SECTION, OTHERWISE CONTINUE.
9.0 g THE RCS BECOMES SUBC00 LED AND A RCP CAN NOT BE OPERATED, THEN GO TO CP-105, OTHERWISE CONTINUE.
10.0 WilEN THE CORE FLOOD TANKS ARE EMPTY, THEN CLOSE THE CFT ISOLATION VALVES.
11.0 SELECT LPI/DHS OR OTSG COOLING. E LPI/DHS COOLING IS SLLECTED, THEN GO TO ':!EP 13.0, OTilERWISE CONTINUE WITH OTSG COOLING.
11.1 h ior to RCS being cooled to 280F and 250 psig, sample the primary coolant for isotopic analysis and notify the plant superintendent of results be fore pacing the LPI/DHS in s e rvic e .
11.2 With RCS parameters stable, do not shift LPI suc t ion to the sump until the decision has been made to complete cooldown with LPI/DHS.
12.0 WHEN LPI FLOW HAS BEEN IN EXCESS OF 1000 GPM IN EACH INJ ECTION LINE FOR AT LEAST 20 MINUTES, THEN STOP llPI PUMPC AND CONTINUE , OTHERWISE l GO TO STEP 15.0.
12.1 Establish normal MU as required.
Section CP-103
, DATE: 7-6-82 PAGE
SWNP-20007 (6-76)
BABCOCK & WILCOX Numeen NUttf AR POWER GENERATION DIVISION 74-l i 2 na t-00 TECHNICAL DOCUMENT 13.0 TRANSFER SDCTION TO CTMT SUMP.
13.1 WHEN THE BWST REACHES 8 FT (minimum time 1/2 to I hour)
THEN trans fer LPI suc tion to CTMT SUMP as follows:
. * . Verify SFAS level 5 permissive evists.
- b. Open DH-9A and DH-9B.
- c. Clore DH-7A and Dil-7B.
- d. Verify no interuption to LPI flow.
- e. Stop the makeup pump if the makeup tank is not available for suction.
14.0 CO TO STEP i6.0.
15.0 E THE CONDITIONS OF STEP 12.0 ARE NOT MET BE70RE THE BWST LEVEL DROPS TO 8 FEET OR BWST LO-LO LEVEL ALARMS (MINIMUM TIME 1/2 TO 1 Il0UR), TilEN ALIGG HPI TO TAKE SUCTION FROM THE CONTAINMENT SUMP AS FOLLOWS:
15.1 Close HPI recire valves to BWST (HP-31 and HP-32).
15.2 Open LPI to HPI valves (DH-63 and Dil-64).
15.3 Open DH-9A and DH-9B 15.4 Verify DH-7A and DH-7B close.
15.5 Le ave DH-14A and DH-14B open and throttle with HPI valves as necessary.
15.6 Stop makeup pump if the MU tank is not available for suction.
16.0 ESTABLISH CONDITIONS FOR LPI/DHR COOLING.
16.1 Continue LPI or HPI/LPI " piggyback" mode until RCS pres s ur e is 250 PSIG.
16.2 Maintain 250 psig and continue cooldown until adequate subcooling margin is established.
Section CP-103 DATE: 7-6-82 PAGE 47
BWNP-20007 (6-76)
BABCOCK & WILCOX "
NUClf AR POwth GENERATION DIYl510N 74-1125531- %
TECHNICAL DOCUMENT 17.0 MIEN ADEQUATE SUBC00 LING MARGIN IS ATTAINED , THEN ESTABLISH LPI/DHR COOLING.
17.1 g two decay heat trains are ope r ab le , THEN go to Step 17.5. E only one decay heat train is operable, THEN continue with Step 17.2.
17.2 WHEN_ the HPI/LPI piggyback operation has been supplying at least 1000 gpm to each loop for 20 min and during this 20 min the RCS pressure has been less than the maximum pressure for LPI operation alone, THEN:
- b. Establish normal MU to maintain seal injection.
- c. Stop HPI pumps,
- d. Close " piggyback" valves (DH-63 and DH-64).
17.3 WilEN two DHR systems are operable, THEN follow Steps 17.5 ,
through 17.7.
17.4 UNTIL two DHR systems are operable, continue with Step 17.7.
CAUTION DO NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY SFAS WITH-OUT REVIEW OF THE POTENTIAL RELEASE OF RADIOACTIVE GAS OR LIQUID.
17.5 MIEN two LPI pumps are operable, THEN align one pump in DHR mode and continue operating the other pump in piggyback mode.
O Section CP-103
BWNP-20007 (6-76)
SABCOCK & WILCOX m....
NucttAt POwit GEMteADON Ofvs510N 74- u 2n 3i-00
-TECHICAL DOCUMENT 17.6 WHEN DH system flow has been greater than 1000 gpm in each line for at least 20 min THEN
- a. Trip RCP's if running, and
- c. Estab$ish over pressure protection.
W 17.7 Maintain seal water flow to all RCP's in anticipation of immediate restart should LPI flow be interrupted (one RCP loop of required). Should RCP restart be required, use jog start method.
t Section CP-103 DATE: PAGE 7-6-82 49
i l
BWNP-20007 (6-76)
BABCOCK & WILCOX Numte NUCLEAR POwta GENttAtlON OtVISION 74- H 27469-00 TECHNICAL. DOCUMENT 18.0 CONTINUE COOLDOWN ON LPI SYSTEM.
18.1 When on DHS flow, core AT is monitored by comparing DHR pump inlet and cooler outlet tempera ture or incore ther-mocouples and cooler outlet tempe ra ture .
18.2 Continue RCS cooldown to 140F with core cooling provided by DilR and RCS pressure controlled by HPI and/or pres-surizer control.
18.3 With core cooling provided by LPI, place OTSG's in wet layup as conditions permit. Stop AFPs. Ensure at least one AFP is available for restart .
18.4 g adequate subcooling margin is lost, TilEN align one LPI pump to BWST or CTefT sump. Maintain maximum flow until adequate subcooling margin is required.
19.0 ESTABLISH LOhd TERM COOLING PER CP-101 AT STEP 5.0.
O O
Section CP-103 DATE: 7-6-82 PAGE 50
BWNP-20007 (6-76)
BABCOCK & WILCOX wuusta NucteAn powta GENinADON DM$lCN _
TECHNICAL. DOCUMENT CP-104 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT LEAVES THE RCS BEING COOLED BY MU/HFI COOLING 1.0 F THE RCS IS SATURATED, THEN ENSURE MAXIW M HPI FLOW PER FIGURE 1.
1.1 (See Specific Rule 1.0).
1.2 WHEN the BWST level reaches 10 ft level, THEN begin makeup to the BWST with borated water.
2.0 OPEN OR VERIFY PORV (RC-2A) AND PORV BLOCK VALVE (RC-11) OPEN.
3.0 WHEN THE RCS BECOMES SUDC00 LED, THEN:
a) Control MU/HFI per Specific Rule 2.
b) Start an RC pump.
4.0 IF THE RCS IS SATURATED, THEN ENSURE THE CFT VALVES REMAIN OPEN.
Section CP-104 DATE: 7-6-82 PAGE 51
- _ _ _ _ _ . _ . _ _ _ _ _ . . 0
EWNP-20007 (6-76)
BABCOCK & WILCOX Nuusia NucitAn rowen otNEnADON DIVl560H , _
TECHNICAL DOCUMENT 5.0 g COOLDOWN RATE AND RCS PRESSURE ARE BEING CONTROLLED AND THE RCS IS SUBC00 LED, THEN ISOLATE THE CORE FLOOD TANKS.
5.1 WHEN the RC system pressure reaches 675 to 700 psig, ' MEN close the core flood isolation valves (CF-1 A and CF-1B).
6.0 i 3 AT ANY TIME
- a. The incore T/Cs indicate that the satur ated RCS becomes sub-cooled AND FW/SGs are still available but voids are trapped in high points or loops,
7.0 GO TO CP-103 STEP 10.0.
8.0 ESTABLISH CONDITIONS NEEDED TO RESTORE HEAT TRANSFER.
8.1 IF the RCS is NOT subcooled using core exit T/Cs OR hot leg RTD, THEN ensure maximum HPI flow per Figure 1.
9, . 2 IF NO RCPs are running, THEN try to get at least one RCP ready for bump.
8.3 Ensure that SG levels are being maintained at 93" startup range. If not, attempt to restore W and increase levels to 93".
9.0 g AT ANY TIME WHILE PERFT)RMING STEP 10.0 - 13.0, THE RCS BECOMES O
SUBC00 LED AND NATURAL CIRCULATION IS ESTABLISHED, THEN C0 TO CP-105 IF THE RCS IS SUBC00 LED OR CP-103 IF THE RCS IS SATURATED, OTHERWISE CONTINUE.
9.1 Natural circulation is verified by incore T/C tempe ra tur e decreasing when secondary pressure is decreased.
O Section CP-104 j DATE. 7-6-82 PAGE 52 1
BWNP-20007 (6-76)
BABCOCK & WILCOX wumen
"#N""*"""^"*"'""S*"
m 74-1125531-00 TECMICAL DOCUMEN 10.0 LOWER OTSC PRESSURE TO INDUCE HEAT TRANSFER.
10.1 Lower OTSG pressure by adjsuting TBVs while maintaining level, until secondary Tsat is 40 to 60F lower than core exit thermocouple temperature. Maintain this OTSG pressure.
11.0 E RCPs CANNOT BE BUMPED, THEN CONTINUE COOLDOWN WITH STEPS 1.0 through 7.0 0F THIS SECTION.
11.1 Determine RCP operability per SP 1103.06.
12.0 USE PUMP BUMPS TO INDUCE HEAT TRANSFER.
12.1 Bump a RCP, which is capable of being started, in a loop with OTSG 1evel at the low level limit or greater.
12.2 Allow RCS pressure to stabilize within i20 psig before determining if heat transfer has been reestablished.
, 12.3 Repeat Steps 12.2 through 12.3 for operable RCPs that have not-been bumped. Allow 15 minutes between pump bumps. E all operable RCPs have been bumped and heat trans fer has NOT been re-established, THEN continue with Step 13.0.
13.0 FURTHER LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
13.1 Tower SG pressure by adjusting TBVs while maintaining level until secondary Tsat is 90 to 1100F lower than core exit thermocouple temperature.
g 13.2 E at least one hour has passed since reactor trip and any RCPs are capable of being started, 'DIEN start and run one RCP, preferably in a loop with SG 1evel greater than 40".
14.0 E RCS REMAINS SUBC00 LED, THEN GO TO CP-105.
15.0 IF RCS REMAINS SATURATED, THEN CONTINUE C00LDOWN PER STEPS 1.0 THROUGH 7.0.
Section CP-104
- DATE: ^
7-6-82 53
BWNP-20007 (6-76)
BABCOCK & Wil.COX Num:En NUCitAR POWER GENttATION DIYl$10N 7'- 23531-00 TECHNICAL. DOCUMENT CP-105 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT MAY REQUIRE FRESSURIZER RECOVERY OR SOLID PLANT COOLDOWN WITH SGs REMOVING HEAT AND RCS SUBC00 LED 1.0 E THE HIGH POINT VENT VALVES HAVE BEEN OPENED , THEN CLOSE ALL HIGH POINT VENT VALVES. (RC-4608A, 4608B, 4610A, 4610B, MOV239A and MOV200) 2.0 IF THERE IS A BUBBLE IN THE PRESSURIZER, GO TO CP-102, OTHERWISE CONTINUE.
3.0 START RCPs.
3.1 E any RCPs are running, THEN go to Step 3.0.
3.2 E natural circulation is in progress THEN start RCPs pe r SP 1103.06 One RCP operating per loop preferred.
4.0 CONTROL MU/HPI FLOW.
4.1 Adjust MU/HPI flow to remain as close as possible to the adequate subcooling margin in the RCS.
4.2 Close or verify close PORV (RC-2 A) and PORV block valve (PC-II).
4.3 'ablish letdown flow.
4.4 Control MU/HPI and letdown flow to remain as close as possible to the adequate subcooling margin.
5.0 E THE DECISION IS MADE NOT TO TRY TO ESTABLISH A BUBBLE IN THE PRESSURIZER, THEN PROCEED WITH A SOLID PLANT C00LDOWN, STEP 8.0.
6.0 ESTABLISH A BUBBLE IN THE PRESSURIZER.
6.1 Turn on all available pressurizer heaters. ( _I_F, pre s sur ize r heaters are not available, THEN refer to SAD tection.
Section CP-105 DATE:
7-6-82 34
BWNP-20007 (6-76)
SABCOCK & WILCOX . , , , ,
wucteam powes oewmation oivisiON TECHNICAL DOCUMENT 10.0 LOWER OTSG PRESSURE TO INDUCE HEAT TRANSFER.
10.1 Lower OTSG pressure by adjsuting TBVs while maintaining level, until secondary Tsat is 40 to 60F lower than core exit thermocouple temperature. Maintain this OTSG pressure.
'l 11.0 E RCPs CANNOT BE BUMPED, THEN CONTINUE C00LDOWN WITH STEPS 1.0 through 7.0 0F THIS SECTION.
11.1 Determine RCP operability per SP 1103.06.
12.0 USE PUMP BUMPS TO INDUCE HEAT TRANSFER.
12.1 Bump a RCP, which is capable of being started, in a loop with OTSG 1evel at the low level limit or greater.
12.2 Allow RCS pressure to stabilize within 120 psig before determining if heat transfer has been reestablished.
12.3 Repeat Steps 12.2 through 12.3 for operable RCPs that have not been bumped. Allow 15 minutes between pump bumps. E all operable RCPs have been bumped and heat trans fe r has NOT been re-established, THEN continue with Step 13.0.
13.0 FURTHER LOWER SG PRESSURE TO INDUCE HEAT 'IRANSFER.
13.1 Lower SG pressure by adjusting TBVs while maintaining level until secondary Tsat is 90 to 1100F lower than core
, exit thermocouple temperature.
13.2 E at least one hour has passed wince reactor trip and any RCPs are capable of being started, TH3N ctart and run one RCP, preferably in a loop with SG 1evel greater than 40".
14.0 E RCS REMAINS SUBC00 LED, THEN GO 'IO CP-105.
15.0 IF RCS REMAINS SATURATED, 'lHE_N CONTINUE C00LDOWN PER STEPS 1.0 THROUGH 7.0.
Section CP-104 DATE:
7-6-82 53
BWNP-20007 (6-76)
BABCOCK & WILCOX Numseu NUCLEAR POWER GENERATION DIVI 540N
"-" 553'-
TECHNICAL. DOCUMENT CP-105 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT MAY REQUIRE PRESSURIZER RECOVERY OR SOLID P_LANT COOLDOWN_ WITH SGs REMOVING HEAT AND RCS SUBC00 LED 1.0 E THE HIGH POINT VENT VALVES HAVE BEEN OPENED , TilEN CLOSE ALL HIGH POINT VENT VALVES. (RC-4608A, 4608B, 4610A, 4610B, MOV239A and MOV200) 2.0 IF THERE IS A BUBBLE IN THE PRESSURIZER, CO TO CP-102, OT9ERWISE CONTINUE.
3.0 STARf RCPs.
3.1 IF, any RCPs are running, THEN go to Step 3.0.
3.2 E natural circulation is in progress THEN start RCPs pe r SP 1103.06. One RCP operating per loop preferred.
4.0 CONTROL MU/HPI FLOW.
4.1 Adjust MU/HPI flow to remain as close as pos s ible to the adequate subcooling margin in the RCS.
4.2 Olose or verify close PORV (RC-2 A) and PORV block valve (RC-ll).
4.3 Establish letdown flow.
4.4 Control MU/HPI and letdown flow ta remain as close as possible to the adequate subcooling margin.
5.0 E THE DECISION IS MADE NOT TO TRY TO ESTABLISH A BUBBLE IN THE PRESSURIZER, THEN PROCEED WITH A SOLID PLANT C00LDOWN, STEP 8.0.
6.0 ESTABLISH A BUBBLE IN THE PRESSURIZER.
6.1 Turn on all available pressurizer heaters. (E pressurizer heaters are not available, THEN refer to SAD section.
Section CP-105 DATE:
7-6-82 54
BWNP-20007 (6-76)
BABCOCK & WILCOX ..,,
74-1125531-00 TECHICAL DOCUMElli 10.0 LOWER OTSG PRESSURE TO INDUCE HEAT TRANSFER.
10.1 Lower OTSG presaure by adjsuting TBVs while maintaining level, until secondary Tsat is 40 to 60F lower than ccre exit thermocouple tempe ra ture. Maintain this OTSG pressure.
11.0 E RCPs CANNOT BE BUMPED, THEN CONTINUE COOLDOWN WITH STEPS 1.0 through 7.0 0F THIS SECTION.
11.1 Determine RCP operability per SP 1103.06.
12.0 USE PUMP BUMPS TO INDUCE HEAT TRANSFER.
12.1 Bump a RCP, which is capable of being startec, in a loop with OTSG 1evel at the low level limit or greater.
12.2 Allow RCS pressure to stabilize within f20 psig before s determining if heat transfer has been reestablished.
12.3 Repeat Steps 12.2 through 12.3 for operable RCPs that have not -been bumped. Allow 15 minutes between pump bumps. E all operable RCPs have been bumped and heat trans fer has NOT been re-established , THEN continue with Step 13.0.
13.0 FURTHER LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
13.1 Lower SG pressure by adjusting TBVs while maintaining level unt il eeondary Tsat is 90 to 110 F lower than core s exit thermocouple temperature.
\
b j 13.2 IF "--
at least one hour has passed since reactor trip and any RCPs are capable of being started, THEN start and run one RCP, preferably in a loop with SG level greater than 40".
0 E RCS REMAINS SUBCOOLED, THEN GO TO CP-105.
15.0 IF RCS REMAINS SATURATED, THEN CONTINUE COOLDOWN PER STEPS 1.0 THROUGH 7.0.
Section CP-104
.DATE:
7-6-82 53
BWNP-20007 (6-76)
BABCOCK & WILCOX j Numset NUCLEAR POWER GENERATON DIVI 510N 74-1 23s31-00 TECHNICAL. DOCUMENT CP-105 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT MAY REQUIRE PRESSURIZER RECOVERY OR SOLID P_LANT COOLDOWN WITH SCs REMOVING HEAT AND RCS SUBCOOLED_ _
l.0 IF, THE HIGH POINT VENT VALVES HAVE BEEN OPENED , THEN CLOSE ALL HIGH POINT VENT VALVES. (RC-4608A, 4608B, 4610A, 4610B, MOV239A and MOV200) 2.0 IF THERE IS A BUBBLE IN THE PRESSURIZER, GO TO CP-102, OTHERWISE CONTINUE.
3.0 START RCPs.
3.1 _I,F,any RCPs are running, THEN go to Step 3.0.
3.2 ,IF, F natur al circulation is in progress THEN start RCPs per SP 1103.06. One RCP operating per loop preferred.
4.0 CONTROL MU/HPI FLOW.
4.1 Adjust MU/HPI flow to remain as close as ps s ib le to the adequate subcooling margin in the RCS.
4.2 Close or verify close PORY (RC-2 A) aad PORV block valve (RC-II).
4.3 Establish letdown flow.
4.4 Control MU/HPI and letdown flow to remain as close as poseible to the adequat( subcooling margin.
5.0 IF, THE DECISION IS MADE NOT TO TRY TO ESTABLISH A BUBBLE IN THE PRESSURIZER, THEN PROCEED WITH A SOLID PLANT COOLDOWN, STEP 8.0.
I 6.0 ESTABLISH A BUBBLE IN THE PRESSURIZER.
6.1 Turn on all available pressurizer heaters. F
( I_F, pressurizer heaters are not available, THEN refer to SAD section.
Section CP-105 DATE:
7-6-82 $4
BWNP-20007 (6-76)
BABCOCK & WILCOX m....
- NUGtAR Powta GENteATION DIV $10N 74-1i 2353 t-00 O TECHNICAL DOCUMENT 6.2 Monitor the increase in pressurizer water temperature un t il pressurizer temperature reaches saturation for the existing RC pressure. At this point, a bubble will be fomed.
6.3 When a bubble is established in the pressurizer, lower pressurizer level to approximately 180 inches.
7.0 CO TO CP-102.
O 9-O Section CP-105 DATE: PAGE 55 7-6-82
I BWNP-20007 (6-76)
BABCOCK & WILCOX " '
NUCtE AR POWER GENERAflON Divi $lON 74-i i 2 n 31-00 TECHNICAL DOCUMENT SOLID PLANT COOLDOWN 8.0 CONTROL MU/HPI.
8.1 Maintain the .RCS about 30F colder than the subcooling margin by throttling MU/HPI.
8.2 F Step E.1 cannot be achieved, THEN maintain maximum MU/llPI flow per figure 1.
8.3 Close letdown isolation valve (MU-1B).
8.4 See Specific Rule 2.
9.0 BEGIN C00LDOWN.
9.1 Using small incremental steps, open the turbine bypass valves to attain a cooldown rate such that adequate subcooling margin is not violated.
9.2 Further adjustment of HPI flow and turbine bypass valve pos i t ion should be acc ompli shed so as to maintain the cooldown rate less than 100F/hr while maintaining adequate subcooling margin.
9.3 Continue cooldo.in while attending to overall plant cooldown per PP 1102.10.
O O
Section CP-105 DATE: PAGE 7-6-82 56 I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
BWNP-20007 (6-76)
BABCOCK & WILCOX
- NUCitAR POWER GENERATION DIVISION 7'-l ' 25 5 3 t-00 TECHICAL DOCUMEllT SPECIFIC RULE 1 - INITIATION OF MU/HPI I. SUBCOOLINC RULE FOR LOSS OF SUBCOOLING MARGIN 1.0 IF the RCS subcooling margin is exceeded THEN,
- a. Two makeup pumps must be run at full MU system capacity taking suction from the BWST, a.1 Start the second make-up pump.
a.2 Verify the make-up flow control valve (MU-32) is open.
a.3 shift MU pump suction to the BWST if required by closing MU-3971.
AND
- b. Two HPI pumps must be run at full HPI system capacity if the reactor coolant pressure is below the low RC pressure SFAS actuation setpoint.
k b.1 _IF_ RCS pressure drops to < 1650 PSIC, THEN verify both HPI pumps start. Verify flow thru HP-2A, HP-2B, HP-2C, and HP-2D as RCS pressure decreases per Figure 1.
b.2 Balance HPI flows (between the two line in each HPI train) to keep the flows approximately equal such that the highest flow is lest than 1.5 times the lower flow by throttling only the line with abnormally high flow.
Do not throttle below the minimum flow line shown in Figure 4.
Specific Rules DATE: 7-6-82 PAGE 57
_ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ __ _. )
BWNP-20007 (6-76)
BABCOCK & WILCOX NumiER NUCLEAR POWER GENERATION DIYl510N 74- 25531-00 TECHNICAL DOCUMENT SPECIFIC RULE 2 - H_P,1, FLOW CONTROL
- 1. GUIDELINES FOR TERMINAT_I,ING HPI, 1.0 HPI operation may be terminated if the LPI system h7s been started and has been flowing at a rate in excess of 1000 gpm in each injection line for 20 minutes.
2.0 HPI may be terminated any time the RC subcooling margin is restored and pressurizer level is above 100 inches and increasing. Nonaal makeup should be started.
Exception, - If core cooling is provided by MU/HPI cooling.
I1. CUIDELINES FOR THROTTLING _H,PI,AND M_U_
l.0 g action is necessary to balance HPI flow, THEN throttle the high flow line to balance injection flow but not below the limit in Figure 4.
2.0 The HPI low flow limit is 35 gpm. Total pump flow should not be throttled below this limit.
3.0 MU and HPI should be throttled to prevent exceeding "he .
reactor vessel pressure tempe rature limit of Figure 2 during once through cooling or MU/HPI cooling.
O' O
Specific Rules DATE:
7-6-82 58
BWNP-20007 (6-76)
SASCOCK & WILCOX wumeen NUCLEAR POwta GtNERADON DIVl510N 7'-1i25331-o0 g TECHICAL DOCUMEllT SPECIFIC RULE 3 - FEEDWATER THROTTLING METHODS
- 1. AFW FLOW CONTROL CUIDELINES 1.0 Maintain continuous full AFW flow until the appropriate level setpoint is reached. Do not allow the OTSG 1evel to decrease if level is still below the appropriate level.
EXCEPTION - E excessive primary to secondary heat trans fe r exists THEN stop AFW flow to the steam generator (s) being overcooled.
O O
Specific Rules DATE: 82 AGE 59
BWNP-20007 (6-76)
BABCOCK & WILCOX Numien NUCLEAR POWER GtNERAftON DIVISION 7'- 25531-00 TECHNICAL. DOCUMENT SPECIFIC RULE 4 - SG LEVEL SETPOINT I. OTSG LEVEL RULE FOR LOSS OF SUBC00 LING MARGIN 1.0 E the subcooling margin is lost, THEN levels in the operating steam generators must be raised to 93" on the start up range using AFW flow.
Exception - E the loss of subcooling margin was due to a loss ;
of seconda ry steam pressure control, THEN do not attempt to raise level in the affected steam generator (s) unt steam pr essure control is regained.
II. GUIDELINES FOR OTSG LEVEL CONTROL 1.0 E any RCPs are running THEN maintain the 1.ow level limit (35" en the startup range).
2.0 IF no RCPs are runnir.g with adequate subcooling margin, THEN maintain 40" on the startup range.
3.0 E SFRCS has actuted AND SFAS Level 2 has not actuated THEN maintain 40" on the startup range (44" in only the OTSG without a s tean le ak , if AFW cross connected).
4.0 E SFRCS has actuated AND SFAS Level 2 has actuated THEN maintain 93" on the startup range (97" in only the OTSG without a s t e an le ak , if AFW cross connected).
5.0 Due to the large level error band of AW level control (14" of se t po in t ) , it may be necessary to place the AFW pump controls in manual to control OTSG 1evels within a tighter band to reduce primary pressure swings.
O Specific Rules l
DATE: PAGE 7-6-82 60
BWNP-20007 (6-76) it BABCOCK & WILCOX ..,,
NuctsAa Powen GENEGAflON DIYl510N , ,
TECHNICAL DOCUMENT SECTION ICC FOLLOWUP ACTIONS FOR INADEQUATE CORE COOLING 1.0 INITIATE MU/HPI & LPI.
1.1 See Specific Rule 1.
1.2 IF LPI is delivering flow, THEN increase LPI flow to maximum.
2.0 INCREASE SG LEVELS TO 93".
3.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
3.1 Depressurize OTSG(s) while maintaining level to achieve secondary T-sat 90 to 110F lower than incore TC tem-perature and maintain this AT.
. 4.0 ENSUP.E CORE FLOOD TANK ISO 1ATION VALVES (CF-1 A and CF-1B) ARE OPEN.
5.0 TAKE ACTION BASED ON FIGURE 3.
5.1 Average the five highest reading incore T/C temperature.
5.2 Determine which region of Figure 3 that the RCS is in based on Step 5.1.
5.3 Using the region determined in Step 5.2 take action s according to the following table.
REGION ACTION 1 Go to CP-103 2 Continue Step 1.0-4.0 above 3 Go to Step 6.0 4 Co to Step 11.0
)
Section ICC DATE: PAGE 7-6-82 61
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BWNP-20007 (6-76)
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BABCOCK & WILCOX l l
NUcit AR POWER GENERATION DIVI $loN 74-1125531-00 TECHNICAL DOCUMENT INCORE THERMOCOUPLE TEMPERATURE IS IF REGION 3 6.0 START ONE RCP PER LOOP IF POSSIBLE.
6.1 Do not override normal RCP interlocks.
7.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER AND RAISE SG LEVELS TO 95%
ON THE OPERATE RANGE 7.1 Depressurize operating steam generators as rapidly as possible to 400 psig or further as necessary to achieve a 100F decrease in secondary Tsat, d.0 OPEN ALL HIGH POINT VENT VALVES. ( RC -4608 A, 4608B, 4610A, 4610B, MOV239A and 10V200) 9.0 IF PRIMARY TO SECONDARY HEAT TRANSFER IS NOT ESTABLISHED, THEN OPEN THE PORV (RC2A) AND GO TO CP-104.
9.1 Allow RCS to depressurize until MU/HPI/LPI/CFTs return incore thermocouple temperatures to saturation.
9.2 Co to CP-104. (C00LDOWN SECTION)
It .0 IF PRIMARY TO SECONDARY HEAT TRANSFER IS ESTABLISHED THEN GO TO CP-103. (000LDOWN SECTION) 10.1 Maintain the primary to secondry heat traas fe r by cycling the PORV to keep RCS pressure 25-60 psi greater than SG pr e s s ur e .
t O
Section ICC DATE: PAGE 62 7-6-82
BWNP-20007 (6-76)
BABCOCK & WILCOX . . ,
g MucttAR POWie GENteATION DIVI $lON 74- 23331-00 TECHNICAL DOCUMENT INCORE THERMOCOUPLE TEMPERATURE IS IN REGION 4 11.0 START ALL RCPs.
11.1 Starting interlocks should be defeated if necessary.
11.2 Do not defeat 1.he overload trip circuit.
\
12.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER AND RAISE SG LEVELS TO 93%
ON THE OPERATE RANGE.
12.1 Depr es sur ize the ope rative OTSG(s) as quickly as pos sible.
Do not go below the minimum steam pressure necessary to power the steam driven AFW pump unless one of the following is available.
- a. Stean form aux boiler being supplied to the AFW pumps.
13.0 DEPRESSURIZE THE RCS ' AND OPEN ALL HICH POINT VENTS.
13.1 Open the PORV (RC-2AT and PORV block valve (RC-11) and leave open.
13.2 Depressurize the RCS until LPI restores core cooling.
13.3 Leave high point vents open until all non condensible gases are vented (RC-4608A, 4608B, 4610A, 4610B, MOV239A and MOV200).
14.0 .WHEN INCORE THERMDCOUPLE TEMPERATURE RETURNS TO THE SATURATION TEMPERATURE FOR THE EXISTING RCS PRESSURE, y CONTINUE WITH STEP 15.0.
k Section ICC DATE: PAGE 63 7-6-82 L_____--___-___. ____-_______ __-_________________ ______________
BWNP-20007 (6-76)
BABCOCK & WILCOX Nuusen NUCLEAR POWit GENERAtlON DIYi$lON 7'- 125n t-00 TECHNICAL DOCUMENT COOLDOWN FOLLOWING ICC (INCORE TEMPERATURES HAVE BEEN IN REGION 4 NOW SATURATED) 15.0 DECREASE RUNNING RCPs TO ONE PER LOOP.
16.0 CLOSE THE CORE FLOOD TANK ISOLATION VALVES (CF-14 and CF-1B).
17.0 MAINTAIN FEEDWATER FLOW.
17.1 IF,F using AFPs, do not reduce OTSG pressure below the minimum steam pressure necessary to power the steam driven AFW pump until one of the following is available.
- a. Steam from aux. boiler available to AFW pumps. }
18.0 WHEN LPI FLOW HAS BEEN IN EXCESS OF 1000 GPM IN EACH INJECTION LINE FOR AT LEAST 20 MINUTES, THEN STOP HPI PUMPS IF RUNNING AND CONTINUE WITH 19.0 OTHERWISE GO 10 STEP 21.0.
CAUTION DO NOT ESTABLISH A " LOW PATH IN ANY SYSTEM ISOLATED BY THE ES WITHOUT REVIEW OF THE POTENTIAL RELEASE OF RADIOACTIVE GAS OR LIQUID.
O Section ICC DATE: PAGE 7-6-82
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BWNP-20007 (6-76)
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BABCOCK & WILCOX "'
NucteAn Powee ceNeRADON DmSION _
f k
TECNNICAL DOCUMENT 19.0 TRANSFER LPI SUCTION TO RB SUMP.
19.1 WHEN the BWST level drops to approximately 8 feet or the low-low BWST level alarm sounds (minimum time 1/2 to I hour) THEN transfer LPI suction to the RB sump as follows:
- a. Open containment sump suction valves (DH-9A and DH-9 B) .
(n) b. Close BWST outlet valves (DH-7A and DH-7B) to prevent pumping BWST dry.
20.0 CONTINUE LPI COOLING UNTIL FURTHER INSTRUCTIONS ARE GIVEN.
21.1 F THE CONDITIONS OF STEP 18.0 ARE NOT MET BEFORE THE BWST LEVEL DROPS TO 8 FEET OR THE LOW-LOW BWST LEVEL ALARM SOUNDS (MINIMUM TIME 1/2 to 1 HOUR), THEN ALIGN HPI PUMPS TO TAKE SUCTION FROM THE RB SUMP USING THE LPI SYSTEM TO PROVIDE HPI PUMP SUCTION.
21.1 Shutdown the MU pumps if MU tank not available, r+ 21.2 Close HPI recire valves to BWST (HP-31 and HP-32).
21.3 Open decay heat pump discharge valves (DH-63 and DR-64).
21.4 Open DH-9A and DH-9B, shut DH-7A and DH-7B.
21.5 Leave DH-14A and DH-14B open and throttle with HP-2 A, 2B, 2C, 2D if necessary.
22.0 ESTABLISH CONDITIONS FOR LPI COOLING.
22.1 ,I_F, F primary temperature can be controlled by steaming the SG(s) THEN go to Step 22.4 otherwise continue.
\
22.2 Continue HPI/LPI "pige,yback" mode until RCS pressure is 250 psig.
22.3 When RCS pressure < 250 psig THEN go to Step 22.7 22.4 .Cooldown the RCS by steaming the operable OTSGs while maintaining HPI/LPI flow until RCS pressure is 250 psig.
22.5 Throttle HPI/LPI flow to prevent exceeding limits of Figure 2.
\
Section ICC DATE: 7-6-82 PAGE 65
BWNP-20007 (6-76)
BABCOCK & WILCOX NUcttAt PowtR GENitAfloN DIVl$loN 74- 25531-00 TECHNICAL. DOCUMENT 22.6 Close the PORV (RC-2A) and cycle as necessary to maintain 250 psig RCS pressure.
22.7 Maintain 250 psig and continue cooldown unt il adequate subcooling margin is established.
23.0 WHEN ADEQUATE SUBCOOLING MARGIN IS ATTAINED, THEN ESTABLISH LPI COOLING.
23.1 E two decay heat trains are ope rable , g go to step 23.5. E only one decay heat train is operable, THEN continue with Step 23.2.
23.2 WHEN the HPI/LPI piggyback operation has been supplying at least 1000 gpm to each loop for 20 minutes AND, during this 20 minutes the RCS pressure has been less than the maximum pressure for LPI operation, THEN:
- a. Verify that t.he LPI to RC3 valve (DH-1A and DH-1B) is open,
- b. Establish normal MU to maintain seal inj ect ion.
- c. Stop the HPI pumps.
23.3 WHEN two DHR systems are operable, THEN follow Steps 23.5
-- 2 3 . 7 .
23.4 Until two DHR systems are operable, continue with Step 23.7.
CAUTION DO NOT ESTALBISH A FLOW PATH IN ANY SYSTEM ISOLATED BY THE SFAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF RADIOACTIVE GAS OR LIQUID.
O Section ICC DATE: AGE 66 7-6-82
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, BWNP-20007 (6-76) 2ABCOCK & WILCOX wu.,u "C""""""^** '**
74-1125531-00 TECHICAL DOCUMENT 23.5 WEN two LPI pumps are operable, THEN align one pump in DHR mode and continue operating the other pump in
" piggyback" mode.
23.6 WEN DH system flow has been greater than 1000 gpm in each line for at least 20 minutes, THEN:
- a. Trip RCP's, if running.
- b. Teminate HPI.
- d. Establish over pressure protection per PP 1102.10.
23.7 Maintain seal water flow to all RCP's in anticipation of imediate restart. Should LPI flow be interrupted start j RCPs. (one RCP per loop is desired)
Section ICC DATE: 7-6-82 PAGE 67
BWNP-20007 (6-76)
BABCOCK & WILCOX wusste wucteam rowta otwenanos oms' " 74-1125531-00 TECHNICAL DOCUMENT 24.0 CONTINUE COOLDOWN ON LPI SYSTEM.
24.1 WHEN on DHS flow, IEEN core AT is monitored by comparing DHR pump inlet and cooler outlet temperature or incore thermocouples and cooler outlet temeprature.
24.2 Continue RCS cooldown to 140F with core cooling provided by DHR and RCS pressure controlled by HPI and/or pressurizer control.
24.3 With core cooling provided by LPI, place OTSG's in wet layup as conditions permit. Stop AFPs. Insure at least one AFP is available for reatart .
24.4 IF adequate subcooling margin is lost, THEN align one LPI pump to BWST or CTMT sump. Maintain maximum flow until adequate subcooling margin is required .
25.0 ESTABLISH LONG TERM COOLING PER CP-101 AT STEPS 5.0.
O O
Section ICC DATE: ^
7-6-82 68 ,
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I BWNP-20007 (6-76)
BABCOCK & WILCOX Nuuien NUCitAR POwtR GENERATION OlVISION 74- 125531-00 TECHNICAL DOCUMENT SAD SECTION SYSTEM SAD DWG. NO.
HPI ED3-0113-011-013 CTMT Spray EDS-0113-011-014 AFW EDS-0113-011-105 Chemical Addition I'DS-0113-011-106 LPI EDS-0113-011-107 CTMT Air Cooling EDS-0113-011-111 CTMT Vessel Isolation EDS-0113-011-112 Turbine Control (EHC) EDS-0113-011-113 Turbine Bypass EDS-0113-011-114 RCS Pressure Control EDS-0113-011-115 r
SAD Section DATE: 7-6-82 PAGE 69
Figure 1 HPI FLOW VS. RC PRESSURE O
1800 -
1600 - BOTH HPl TRAINS OPERATING O n 1400 -
5 j 1200 -
E C
E 1000 -
HPl TRAIN WITH PUMP 1-2 E
E 800 -
0
~
HPl TRAIN WITH PUMP 1-1 0 400 -
NOTE: CURVES BASED ON HPl PUNP(S)
RECIRC l.INE BEING OPEN.
200 -
0' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' l 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 13 17 RC System Pressure at HPI Nozzle X 100 (PSIG) 74-1125531-00
Figure 2 RC PRESSURE / TEMPERATURE LIMITS O
2400 2200 I !
G 2000 !
l 1800 I
' /
r 1600 g
^
(TYPICAL)
G 1400 NORMAL COOLDOWN D REACTOR VESSEL P-T LlHIT j /
= FROM TECHNICAL SPECIFICATION f
1000 I
UNACCEPTABLE ,
800 y SUBC00 LING -- (
EGO !
l 7
/ MARGIN j
' " "' ~ - ~
UNACCEPTABLE f
400 -
f j
200 e 7 O l 100 200 300 400 500 600 Reactor Yessel Temperature (*F)
O 74-112333j.00
l 1
Figure 3 CORE EXIT FLUID TEMPERATURE FOR I INADEQUATE CORE COOLING lO 2600 RC 2400 - SUPERHEATED RC SUBC00 LED 2200 TCL A0 > 1400F 1800 -
^
- o. REGION I REGION 2 REGION 3
[ 1600 -
I 1200 - p u
T CLAD o
E 1000 - C f!' REGION 4 800 - 4 s b
600 -
8 O 400 -
200 400 500 600 700 800 900 1000 1100 1200 1300 Core Exit Tnermocouple Temperature (F)
O 71-1125531-00
Figure 4 HPI THROTTLING LIMIT (FOR HIGH FLOW HPI LINE)
O 1600 -
1400 -
l 1200 -
y 1000 -
si 800 -
O ac 600 -
400 -
200 -
0 ' ' '
0 100 200 300 400 HPl Flow, gpm O ,
7 d - 112 55 31 - 0 0
7 I
l l
l f Table 1 SFRCS EQUIPMENT ACTUATION I (SHEET 1 0F 2)
ACTUATION CHANNEL 1 Mif 11:1P:
. mm u,r uw max
. uu ex um1.
. uu W w sc 6P om sa:
IG-118 AVV DLM #1 P6-101-1 Elf BYPASS #1 E-3% 16 DRAIN fl FIAJ, TRIP:
. swa um i . m u uw livn. . ums or ium =F.
uu Pusm e uu u w Eo au
~
UM16-RID 1E NTifW) 4 SITAM LIE 2 ilu PLESS 043X 9erf: OBX 9tfr: OHX 9tfr:
105-115 AW IAW #1 ICS-i t B AW IDF #1 AP-3869 fl AN 10 DISQt EWUL P2 16-101-1 EtV BYPASS #1 96-101-1 PFilV BYPALS #1 P6-10hA f2 P6 E AWrl EWEB MS-Y4 pH 1 RAIN #1 96-394 961*AIN fl GUI (MN:
17-7a Su W GMT Vl# #1 :P-75 SU IV GNr Vl# #1 AP408 AW1 D13011D SG-1 fW612 ftV SitF VLV $1 M 12 t9V S1rF VLV #1 96-106 #1P6TOART
\
96-10b 017610 AFTT #1 E-10h4 f2 t610 A&rl XDWat AF-3870 ANI Dtadt 1D E-l
- 6-IDI PEIV #1 t6-101 EIV #1 M:
m-600 PE!V #2 m-100 PEIV #2 MUM TINLDE AP-3870 ANI DISQt 10 E fl AP-3869 AW1 DISOL RWD1 f2 W-7tio stv aut VL4 #1 FW781 MFW BlJC VlX #1 AMOS AW1 DIS 0110 SG-1 SP 4A 96V GWT VLV #2 SP4A tev GET VIV F2 OMY OPFN: OMX OPIN Per-10b #17610 AITT 1 E-H1hA f2 PG 10 AWrl XDW.R AP-3870 AW1 DISat to E fl AP-Yt69 ANI DISQt EMA F2 AfMJ. AW1 DISQt 10 SG #1 f
(
x 7 4= 112 55 31 - 0 0
l Table 1 SFRCS EQUIPMENT ACTUATION
( (SHEET 2 0F 2) l I
l ACTUATION CHANNEL 2 HAIF 1 RIP:
> sIzm uE la PESara o IN O!SG 11VEI.
IC-11A AW Inf f2 i
16-100-1 161V BfPASS #2 7 10 -375 16 DRAIN #2
( FUIL TRIP:
e FIEAM 1.IE 2 e Ors; IN IEVEI.
o IESS OF FOUR RfPs la PRESSJRE e Im FW 10 SG AP GLY (0YER-RIDDC ACILATDC) e STEAM I.DE I IN PRESS QEXX SIUT: ORKX SILT: GEQt SILT:
ICS-IIA AW DLDe #2 ICS-IIA AW Ulte #2 AP-3871 AN2 DISQt ID X0VER #1 16-10>l 161V BYPASS #2 16-100-1 EIV BYPASS #2 16-107A #1 E 10 AFPI2 XDVER 76-375 E DRAIN #2 16-375 16 IEAIN #2 QEOC OPDI SP-7A SU W Q NT VLV #2 SP-7A SLI W QBff V!X #2 M-599 Ani2 DISol D SG-2
,/
) FW-401 IfW SItP VLV #2 W-601 IWW S10 V!X #2 16-107 #216 ID AFFI2 D6-107 1610 AFPI2 16-107A #1 r610 Af?I2 XDVER M-3872 AFW2 DIS 0110 SI #2 16-101 EIV #1 16-101 MIV #1 TRIP:
16-100 PSIV #2 16-100 EIV #2 MADE TUREDE M-1872 A N2 DISQt SC2 M-3871 AFW2 DISQt X0VER #1 FW-779 IfW BtX V!X #2 FW-779 MPW BIK VLV #2 SP-6B PfW (Diff VLV fl 5%B IfW Culfr VLV #1 a M-599 AFW2 DISOI SC2 GEat 0PDI: DECK OPEN MS-107 #2 2 10 APPI ?
D6-107A #17610 AFFT2 XDVER fr-3872 AFW2 DIS 0110 !L #2 M-3871 APW2 DIS 01 XDVER #1 AF-5a9 AN2 DIS 011D SG-2 O
'7461125531-00
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