ML18082A934

Startup Procedure 90.2,Revision 2, Natural Circulation W/ Simulated Loss of Offsite AC Power.

ML18082A934
Person / Time
Site:	Salem
Issue date:	08/07/1980
From:	Public Service Enterprise Group
To:
Shared Package
ML18082A922	List: ML18082A920 ML18082A923 ML18082A925 ML18082A931 ML18082A933 ML18082A934 ML18082A936 ML18082A937 ML18082A938 ML18082A939 ML19331C787
References
90.2, NUDOCS 8008190535
Download: ML18082A934 (19)

Text

STARTUP PROCEDURE 90.2, Rev. 2 UNIT NO. 2 NATURAL CIRCULATION WITH SIMULATED LOSS OF OFFSITE AC POWER 8008190535 SUP 90.2 Salem Unit 2 Rev. 2

SUP 90.2 NATURAL CIRCULATION WITH SIMULATED LOSS OF OFFSITE AC POWER

1. 0 OBJECTIVES 1.1 The objectives of this test are to demonstrate tha~-following a loss of offsite AC power, natural circulation cooling can be established and maintained while being powered from the emergency diesel generators. In addition it will be verified that after offsite power is restored, the emergency loads can be transferred to offsite power and the diesel generators restored to standby status.

1.2 To provide operator training.

SUP 90.2 Salem Unit 2 Rev. 2

2.0 REFERENCES

2.1 Westinghouse Precautions Limitations and Setpoints Rev. 7, August 1979.

2.2 SUP 90.0, Special Tests Sequence Document 2.3 Salem Operating Instructions EI I-4.0 nsafety Injection Initiationn Rev. 1 EI I-4.9 "Blackoutn Rev. 8 OI II-1.3.l "RCP operation" Rev. 1 OI III-10.3.l "Auxiliary Feedwater System Operation" Rev. 1 OI IV~B.3.1 "Rod Control System - Normal Operation" Rev. 0 2.4 PSE&G Drawing 203063A 8789-5 SUP 90.2 Salem Unit 2

• Rev. 2

PREREQUISITES 3.1 The modifications to the Solid State ~rotection System have been made per SUP 90.0 Appendix A.

3.2 Brush recorders (or equivalent) are connected per section 8.2.

3. 3 The W reactivity computer is operational. Recording flux, Tc and Th (wide range) ,

and reactivity, as outlined in paragraph 8.6.

3.4 The P-250 trend blocks are set up per section 8.4.

3.5 The Test Engineer has briefed all personnel involved in the conduct of the test.

3.6 Station QA has been notified of the start of the test.

. 3. 7 SUP 90.l *"~atural Circulation" has ..been satisfactorily. comp.l~ted ... ~

3.8 The 125 V.D.C. control power has been turned off in breakers 21ASD, 21BSD, and 21CSD, so that when the normal vital power is interrupted in step 10.5, the ABT feature will be inoperative forcing the diesel generators to start.

3.9 The special operator instructions given in SUP 90.0 (ref. 2.2) section 9.1.4 are posted conspicuously on the operators console or on the main control board.

3.10 The S/G lo-lo and lo' level reactor trip setpoints have been reset to 5%.

3.11 The.NIS power range hi-level, low range (normally 25%) trip is set to 0.583 volts and the intermediate range hi-level trip is set to 28 µa (c~rresponds to 7% reactor power .

Salem Unit 2 SUP 90.2 Rev. 2

INIT.IAL CONDITIONS 4.1 The reactor is critical at ~ 1% power as determined by the single pass flux map procedure (SUP 90.0 Appendix C).

4.2 All four Reactor Coolant Pumps are in operation.

4.3 Rod Control System is in Manual (Bank D Select) with control Bank D at about 160 steps or as specified by the Test Engineer.

4.4 Pressurizer level control is in manual with level being maintained~ 26%.

4.5 Auxiliary Feedwater System is in service and operating on offsite power per OI-III-10. 3 .1.

4. 6 Steam Pres.sure is approximately 1005 psig being maintained by steam dump in pressure control mode, or alternatively by atmospheric steam dump, if the condenser steam dump is unavailable.

4.7 Steam Generator level being maintained at approximately 33% N.R. level.

4.8 Steam Generator chemistry is such that minimum blowdown can be maintained.

(Zero blow down desirable) 4.9 Excess letdown is available if required during the test.

4.10 Diesel Generators 2A, 2B and 2C are shutdown and aligned in standby status IAW OI IV-16.3.1.

__, 4.11 No. 21 control rod drive M-G set is shutdown IAW OI IV-8.3.1 "Rod Control System - Normal Operation".

4.12 No. 23 Auxiliary Feed Pump LOCAL-REMOTE switch in LOCAL.

NOTE: The preceding step will prevent automatic start of the 23 Auxiliary Feed Pump. This is necessary so that verification can be made that natural circulation can be established on emergency diesel power*.

4.13 Breaker lineups'are complete in accordance with Appendi'x B, "Pretest Breaker Positions".

4.14 Pressurizer pressure control in AUTO, controlling at 2235 psig.

4.15 21 CCW pump and 23 CHG pump are in operation.

SUP 90.2

• salem unit 2 Rev. 2

5.0 ENVIRONMENTAL CONDITIONS 5.1 Atmospheric steam dwnp will be required during the performance of this procedure.

6.0 ACCEPTANCE CRITERIA 6.1 Natural circulation can be established and maintained within the limits established in SUP 90.l "Natural Circulation Test" under emergency diesel power.

6.2 A margin of at least 20°F subcooled from saturated conditions is maintained throughout the test (see operator action points 9.1.4. of SUP 90.0).

6.3 Operators participating or observing the test are documented on Appendix A.

SUP 90.2 Rev. 2 Salem Unit 2

7.0 SPECIAL EQUIPMENT Instrument Specification Serial # Calibration 7.l Strip Chart Brush 260 (or Recorders equivalent) No. l No. 2 No. 3 7.2 Reactivity Computer Westinghouse 7.2.l Chart Recorders No. l 7.2.2 Chart.Recorders No. 2 7.2.3 Chart Recorders No. 3 7.2.4 Chart Recorders No. 4 7.2.5 Chart Recorders No. 5 7.3 Fluke digital voltmeter SUP 90.2 Salem Unit 2 Rev. 2

• 8.0 DATA COLLECTION 8.1 All data acquired as a result of performance of this procedure shall be recorded at the appropriate step, on attached data sheets or affixed as appropriate.

8.2 Connect Strip Chart recorders to the following test points.

Recorder No. l Inst. Monitor in~ Range Channel No. l FT-414 RCS Flow - Loop l 0-10% flow Channel No. 2 FT-424 RCS Flow - Loop 2 0-10% flow Channel No. 3 FT-434 RCS Flow - Loop 3 0-10% flow Channel No. 4 FT-444 RCS Flow - Loop 4 0-10% flow Channel No. 5 PT-474 Pressurizer Pressure 1600-2400 psig Channel No. 6 LT-461 Pressurizer Level 0-100%

Recorder No. 2 Inst. Monitoring Channel No. l FA-10B7 Stearn Gen 21 Aux. Feed Flow 0-300 gpm Channel No. 2 LT-517 Stearn Gen 21 Level 0-100%

Channel No. 3 PT-516 Steam Gen 21 Pressure 700-1200 psig Channel No. 4 FA-1091 Steam Gen 22 Aux. Feed Flow 0-300 gprn Channel No. 5 LT-527 Steam Gen 22 Level 0-100%

Channel No. 6 PT-526 Stearn Gen 22 Pressure 700-1200 psig Recorder No. 3 Inst. Monitorin~

Channel No. l FA-1095 Stearn Gen 23 Aux. Feed Flow 0-300 gprn Channel No. 2 LT-537 Steam Gen 23 Level 0-100%

Channel No. 3 PT-536 Stearn Gen 23 Pressure 700-1200 psig

' Channel No. 4 FA-1097 Stearn Gen. 24 Aux. Feed Flow 0-300 gpm Channel No. 5 LT-547 Steam Gen 4 Level 0-100%

Channel No. 6 PT-546 Steam Gen 4 Pressure 700-1200 psig NOTE: Recorders should be powered from a source not effected by the blackout.

8.3 Copies of the reactivity computer trace and saturation meter recorder will be

• marked and attached as data.

8.4 The P-250 computer trend typewriter will be used to monitor the following computer points. This trend printout will be attached as data.

SUP 90:2 Salem Unit 2 Rev. 2

Computer Point Pressurizer Pressure P0480A Pressurizer Level L0480A RCS Loop l Hot Leg Temperature T0419A RCS Loop l Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature T0479A RCS Loop 4 Cold "Leg Temperature T0466A Steam Generator l Pressure P0400A Steam Generator l Narrow Range Level l L0400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level l L0420A

• Steam*Generator 3 Pressure Steam Generator 3 Narrow Range Level l Steam Generator 4 Pressure Steam Generator 4 Narrow Range Level l P0440A L0440A P0460A L0460A

~- Power Range Channel N41 N0049A Power Range Channel N42 NOOSOA Power Range Channel N43 N0051A Power Range Channel N44 N0052A Incore Thermocouples (Selected) TOOOlA through T0065A Hottest Incore Thermocouple U0090A Pressurizer Surge Line Temperature T0482A 8.5 The P-250 computer printouts of the incore thermocouple maps and single pass in-core maps used during the performance of this test will be attached.

SUP 90.2 Salem Unit 2 -a- Rev. 2

• 8.6 Reactivity Computer 8.6.l Recorder U Channel A P-computer output Channel B N-41 excore detector current Recorder 112 Channel A Loop 21 Tc TE 413 B 510-610°F 8.6.2 Channel B Loop 21 Th TE 413 A 510-610°F a.6.3 Recorder #3 Channel A Loop 22 Tc TE 423 B 510-610°F Channel B Loop 22 Th TE 423 A 510-610°F a.6.4 Recorder t4 Channel A Loop 23 Tc TE 433 B 510-610°F.

Channel B Loop 23 Th TE 433 A 510-610°F a.6.5 Recorder #5 Channel A Loop 24 Tc TE 443 B 510-610°F Channel B Loop 24 Th TE 443 A 510-610°F 8.7 The following data (as applicable) shall be recorded on each strip chart and computer listing.

a) Unit Number b) Date c) Procedure number, step number, and run number, as appropriate d) Parameter scale(s) and range (s) e) Chart speed f) Name of person recording data g) Reacor.der ID number h) Time ma:i:'.k for start of test a.a Record operator participation in the test on Appendix A

• SUP 90.2 Rev. 2 Salem Unit 2

9.0 PRECAUTION 9.1 Do not exceed 5% nuclear power, by any available indication.

9.2 Abort the test if any of the Operator Action point limits are exceeded:

As described in SUP 90.0, paragraph 9.1.4.1.

9.3 When equlibrium is established after the initial transient, avoid any sudden changes in auxiliary feedwater flow or steam generator water level.

9.4 After the reactor coolant pumps are tripped, the normal T and 6T indication avg will become unreliable due to loss of flow in the RTD bypass loops. Use wide range TH and TC to calculate these parameters.

9.5 Maintain CCW and Seal Injection flows to the RCP's during the test.

9.6 Reactor Coolant pumps should not be restarted for 30 minutes after pump trip, (per OI II-1.3.1) unless safety concerns necessitate the re-establishment of forced circulation.

9.7 Should a reactor trip take place during the performance of this test, restart

• at least one reactor coolant pump (#23) prior to closing the reactor trip breaker.

9.8 During the transient, match charging with letdown flow to maintain a constant RCS mass. Pressurizer level will rise as Tavg increases under natural circula-tion. Approximately 1% level increase per 1°F increase in T is expected avg '

(or about 30% level at 1% power) .

SUP 90. 2 Salem Unit 2 Rev. 2

10.0 INSTRUCTIONS 10.l Clear the Unit 2 control room of all nonessential personnel.

10.2 Place pressurizer heater backup groups #21 and #22 in manual - off.

. 10. 3 Start the P-250 trend points set up per paragraph 8.4

• 10.4 Start the strip chart recorders set up per paragraph 8.2.

NOTE: The next step will simulate a loss of offsite power. Following RCP trip, the following response is expected:

Wide Range Tc slight decrease Wide Range Th increase about 16°F Core Exit T/C increase 16-20°F Tavg unreliable 6T unreliable Pressurizer Level increase to about 34%

Pressurizer Pressure increase ~ 100 psi 10.S As close to simultaneously as possible, perform the following actions, allowing only enough time for 2B DG to pick up its charging pump #21 and component cooling pump #22.

Note Time Start Step a) Trip Breaker 22 BSD Feed to 2B Vital Bus, verify 21 BSD remained open Verify the 21 CSI and 22 CCW pumps start.

b) Trip Breaker 22 ASD Feed to 2A Vital Bus, verify 21 ASD remained open c) Trip Breaker 22 CSD Feed to 2C Vital Bus, verify 21 CSD remained open d) Shut off the pressurizer heater control group e) Trip all 4 reactor coolant simultaneously Complete Step 10.6 Place condenser steam dump controls to off

. 10. 7 Verify diesel generator 2A, 2B, and 2C start, energize their respective vital buses and the following equipment starts on its respective vital bus. Place check marks where appropriate, noting any equipment that fails to start .

Salem Unit 2 SUP 90.2 Rev. 2

--1 a) 230-480V Breakers (control center loads) (3) b) Charging Pumps (2) c) Component Cooling Pumps (3) d) Auxiliary Feed Pumps (2) e) Service Water Pumps (3) f) Emergency Control Air Compressor (1) g) Chillers (3) h) Auxiliary Building Supply and Exhaust Fans (5) i) Switchgear Room Supply Fans (3) j) Reactor Shield Vent Fans (2) k) Reactor Nozzle Support Vent Fans (4)

CAUTION: If any diesel fails to start, manually restore power to that bus by closing the feeder breaker that was opened in step 10.5.

Do not transfer pressurizer heater bus 2GP to the 2C Vital supply.

Transfer would cause loss of 22 control rod drive M-G set and a Reactor Trip.

10.8 Energize Pressurizer Heater Bus 2EP Emergency Feed from 2A 460V Vital Bus (follow EI I-4.9 "Blackout").

10.9 Reset the Safeguards Loading Sequence by depressing the Emergency Loading reset pushbuttons on the control console, for 2A, 2B, 2C. Diesel Generators 10.10 Begin printing incore T/C maps and single pass incore flux maps every 15 minutes from the time of blackout initiation.

NOTE: Monitor reactor power closely and make adjustments necessary to maintain approximately 1% reactor power, and roughly constant Tc using the atmospheric steam dump controllers, in conjunction with positioning rods.

10.11 Restore steam generator level to the normal operating level of approximately 33% and maintain this level. Avoid sudden changes in auxiliary.feed flow rate .

SUP 90.2 Salem Unit 2 Rev. 2

10.12 Verify natural circulation is established in all loops. Review the guidelines of Emergency Instruction I-4.9 "Blackout" for completeness and accuracy. Main-tain steady state conditions for 30 minutes.

NOTE: Natural Circulation flow will be stable when:

a) ~T between wide range Th and Tc is constant b) ~T between wide range Tc and core exit T/C average temperature is constant c) Wide Range Th ~ core exit T/C average temperature.

10.13 Restore normal station power to the 2A, 2B and 2C Vital Buses IAW OI IV-16.3.1 10.14 Return 23 Auxiliary Feed Pump LOCAL-REMOTE switch to REMOTE.

10.15 Place stea.m dump controls to the on position and adjust to maintain approximately 1005 psig steam pressure.

10.16 Shutdown the reactor by inserting control Bank D to zero steps in Manual Bank D select.

10.17 Place pressurizer spray valves 2PS1 & 2PS3 in manual-closed and place pressurizer heater controls in auto prior to starting the first Reactor Coolant Pump.

10.18 Restart Reactor Coolant Pump #23.

10.19 When conditions stabilize after the start of #23 RCP, start #21, 22 and #24 Reactor Coolant Pumps and return pressurizer spray valves 2PS1 & 2PS3 to auto.

--<. 10.20 Turn off data recorders and digitial trend and note time on charts. Ensure that all charts are properly marked IAW paragraph 8.7.

10.21 Return pressurizer heater bus 2EP to its normal supply.

10.22 Return pressurizer level control to automatic.

10.23 Collect recorder charts and computer outputs and attach as data.

10.24 Remove the block of input logic of safety injection on Hi steam line ~P in accordance with SUP 90.0 Appendix A unless the next test to be performed requires the block to be installed. If this is the case; disregard this step, place N/A in the signature line and initial *

• SUP 90. 2 Salem Unit 2 Rev. 2

10.25 Remove modification to Hi Steam Flow coincident with Lo S/G pressure or Lo Tav input to safety injection in accordance .with SUP 90.0 Appendix A 4

unless the next test to be performed requires the modification to be made.

If this is the case, disregard this step, place N/A in the signature line and initial.

l0.26 Remove block of automatic initiation of safety injection in accordance with SUP 90.0 Appendix A unless the next test to be performed requires the modi~

fication to be made. If this is the cas~, disregard this step, place N/A in the signature line and initial

• SUP 90.2 Salem Unit 2 Rev. 2

11.0 TES7 COMFLE7lON ll. l Comments ll. 2 Char.ges to SP!-:

l l .:

5/S Da~e QA QC

-c::-*

SUP 90.2 Salem Unit 2 Rev. 2

APPENDIX A SRO's Participating In Test SRO's.Observing Test SUP 90. 2 Salem Unit 2 Rev. 2

APPENDIX A (cont.)

RO'* Participating In Teat J

RO's. Observing Test SUP 90.2 Salem Unit 2 Rev. 2

.. c SUP 90.2 Appendix B "Pretest Breaker Positions" BKR POSITION 21 ASD 21 STA PWR XFMR INFEED TO 2A 4KV VITAL BUS 0 22 ASD 22 STA PWR XFMR INFEED TO 2A 4KV VITAL BUS x 21 BSD 21 STA PWR XFMR INFEED TO 2B 4KV VITAL BUS 0 22 BSD 22 STA PWR XFMR INFEED TO 2B 4KV VITAL BUS x 21 CSD 21 STA PWR XFMR INFEED TO 2C 4KV VITAL BUS 0 22 CSD 22 STA PWR XFMR INFEED TO 2C 4KV VITAL BUS x 2 ADD 2A DIESEL GENERATOR BREAKER 0 2 BDD 2B DIESEL GENERATOR BREAKER 0 2 CDD 2C DIESEL GENERATOR BREAKER 0 2 A4D 2A 4KV VITAL BUS FEED TO 2A 460 & 230V BUS XFMRS x 2 B4D 2B 4KV VITAL BUS FEED TO 2B 460 & 230V BUS XFMRS x 2 C4D 2C 4KV VITAL BUS FEED TO 2C 460 & 230V BUS XFMRS x 2 EX 2E 460V BUS INFEED BREAKER x 2 GX 2G 460V BUS INFEED BREAKER x 2 GXA 2G - 2E 460V BUS TIE BREAKER 0 2 AHGD 2A AUX PWR XFMR INFEED TO 2H 4KV GROUP BUS 0 21 HSD 21 STA PWR XFMR INFEED TO 2H 4KV GROUP BUS x 2 AEGD 2A AUX PWR XFMR INFEED TO 2E 4KV GROUP BUS 0 21' ESD 21 STA PWR XFMR INFEED TO 2E 4KV GROUP BUS x 2 BFGD 2B AUX PWR XFMR INFEED TO 2F 4KV GROUP BUS 0 22 FSD 22 STA PWR XFMR INFEED TO 2F 4KV GROUP BUS x 2 BGGD 2B AUX PWR XFMR INFEED TO 2G 4KV GROUP BUS 0 22 GSD 22 STA PWR XFMR INFEED TO 2G 4KV GROQP BUS x 2 Al4X 2A 460V VITAL BUS EMERG FEED TO 2EP PZR HTR BUS 0 2 E6D 2E 4KV BUS FEED TO 2E 460V BUS XFMR&2EP PZR HTR BUS x 2 EPX 2EP 480V PZR HTR BUS INFEED BREAKER x Man. Disc. SW 2A 460V BUS EMERGENCY FEED TO 2EP PZR HTR BUS 0 Salem Unit 2 App. B SUP 90.2 Rev. 2 I~