ML19312E570

LOCA, Revised Emergency Procedures

ML19312E570
Person / Time
Site:	North Anna
Issue date:	05/22/1980
From:	Cartwright W, Harvey S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19312E567	List: ML19312E566 ML19312E568 ML19312E570 ML19312E574 ML19312E579 ML19312E581
References
2-EP-2, NUDOCS 8006050333
Download: ML19312E570 (28)

Text

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2-EP-2 Page 1 of 14 05-22-80 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 LOSS OF REACTOR COOLANT ACCIDENT

REFERENCES:

1. FSAR Chapters 6 and 15.

2. 12050-LSK 28-5

3. 12050-FM-95B, C 4 12050-FM-96A, B

5. 12050-ESK 6K, 6L, 6CP, 6CQ

6. 12050-FE - 1G, lQ, 1R

7. FSAR Conunent 6.132

8. North Anna Unit #2 Facility License

9. I.E. Bulletin #79-06A,79-06C REV. 9 PAGE: Entire DATE: 05-22-80 APPROVAL: -

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APPROVED BY: -(l'(

CHAIRMANSTATIONVCpARSAFETY AND OPERATING GOMMITTEE DATE: 05-22-80 SAFETY RELATED 8006050 3%

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2-EP-2 Page 3 of 14 05-22-80 3.0 Immediate Operator Actions 3.1 2-EF-1 Immediate Actions have been completed.

NC: .: If any required Automatic Action has not occurred, it shall be manually initiated.

3.2 Manually initiate Safety Injection.

3.2.1 Verify that the emergency busses (H 2nd J) are energized and both emergency diesel generators are running.

3.2.2 Verify Phase A isolation.

3.2.3 Verify Feedwater isolation.

3.2.4 Verii) that the Auxiliary Feedwater pumps (2-FW-P-2, 2-FW-P-3A and 3B) have started and a-re flowing (FI-FW-200A, B & C). '

3.2.5 Verify high head and low head Safety Injection pumps are running and cold leg Injection Flow is indicated on FI-2961, 2962 and 2963.

3.3 Verify Main Steam Isolation if:

3.3.1 Containment pressure exceeds the intermediate high high setpoint of 17.8 psia. or, 3.3.2 Safety Injection was initiated by high steam flow-low Tave (543 ) or high steam flow-low steam pressure.

(600i/)

3.4 Verify containment high-high initiation if containment pressure exceeds 25 psia.

3.4.1 Verify Quench Spray pumps start.

3.4.2 Verify Phase "B" isolation.

3.5 Emergency Director to initiate EPIP-1.

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2-EP-2 Page 4 of 14 05-22-80 Xnitials 4.0 Long Term Operator Actions NOTE: DO NOT UNDER ANY CIRCL?! STANCES CLOSE THE C00LAlfr LOOP ISOLATION VALVES.  ;,

NOTE: The pressurizer water level indication should always be used in conjunction with other specified reactor coolant system indications to evaluate system conditions and to initiate manual operator actions.

NOTE: If the Res tor Coolant System pressure decreases in an uncontrolled manner to < 1485 PSIG, secure all reactor coolant pumps. '

NOTE: io.. see Attachment 2 to verify natural circulation upon tripping reactor coolant pumps.

NOTE: Complete step 4.5 when the criteria .for securing safety injection has been met.

i CAUTION: Do not secure seal injection.

CAUTION: If component cooling water to the reactor coolant pumps is isolated on a containment pressure signal, all reactor coolant pumps should te stopped within 5 minutes because of loss of motor bearing cooling.

CAUTION: During a safety injection when a emergency bos is being carried by its emergency diesel generator, the loading must be 5 3000kw. The emergency bus powered pressurir.er heaters shall not be re-energized until the load is <

2730 kw and actual pressurizer level is greater than 10*. Equipment which may be secured to meet this requirement are:

1. Containment Air Recire Fan (s)

2. Rod Drive Cooling Fan (s)

3. Service Water Screen Wash Pump

4. Standby Primary Grade Water Pump

2-EP-2 Page 5 of 14 05-22-80 Knitials 4.0 Long Term Operator Actions (cont.)

4.1 Verify SI ($A) and/or (QB) isolation by initiating Attachment 3.

4.2 Verify that RWST level is decreasing and containment recircula-tion sump level is increasing. If proper level changes are not evident, re-evaluation of the incident is required.

4.3 Verify three (3) auxiliary feedwater pumps, 2-FW-P-2, 2-FW-P-3A and 3B are running and that feedwater flow is indicated to the appropriate steam generators.

NOTE: If any of the above pumps are not running or it is determined that proper flow is not being maintained, attempt to manually start the pump and/or refer to 2-AP-22.

Throttle flow to each Steam Generator to maintain no-load level (33%). Monitor auxiliary feedwater pump suction pressures to verify > 4 psig. Maintain 2-CN-TK-1 (emergency condensate storage tank) level above the lo-lo level alarm point (> 9%) by filling from 2-CN-TK-2 (condensate storage tank) per 2-0P-31.2 4.4 Close pressurizer power operated relief valves. Close the power operated relief valve isolation valves only if a power operated relief valve cannot be closed.

4.5 Safety Injection may be terminated if all of the following criteria are satisfied.

1. Reactor Coolant pressure is > 2000 psig and increasing.

Yes No

2-EP-2 Page 6 of 14 05-22-80 fnitials 4.0 Long Term Ooerator Actions (cont.1

2. Pressurizer water level is > 50% span.

Yes No

3. At least one steam generator is operable with level in Yes No the narrow range or at least 690 gpm is being injected into the non faulted steam generators.

4. All Th and Tc are at least 50*F below the saturation I

Yes No.

temperature for the existing RCS pressure.

5. SRO/STA are in agreement with the incident diagnosis.

Yes No NOTE: If the reactor coolant pressure drop's below the pres-surizer pressure setpoint for Safety Injection or pressurizer level drops below 20% of span or If 50*F indicated subcooling cannot be established or maintained, then manually reinitiate safety injection and request that the SRO/STA re-evaluate the incident.

6. Secure Safety Injection and establish normal charging and letdown as per Attachment 1.

NOTE: If all of the listed criteria cannot be satisfied, proceed to Step 4.6 and continue to cooldown the RCS.

If all of the listed criteria is satisfied, continue with this step.

NOTE: After resetting the Safety Injection signal, automatic reinitiation will not occur since the reactor trip breakers are not reset.

j 4.6 Line up the Post Accident Thermal Hydrogen Recombiner in pre-paration for utilization as per 1-0P-63.1.

4.7 Secure waste gas release from the site:

l 4.7.1 Close WGDT release valve FCV-GW-101.

4.7.2 Inform the other units to secure containment purge and hogging operations.

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2-EP-2 Page 7 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.8 If the reactor coolant pumps have been secured due to an uncon-trolled depressurization (< 1485 psig), it is NOT petaissible to restart a reactor coolant pump until the criteria for securing safety injection has been met and plant conditions have been evaluated for starting a reactor coolant pump.

4.9 If the reactor coolant pumps have been secured, verify natural circulation as per Attachment 2.

4.10 When the containment reaches a sub-atmospheric condition:

CAUTION: Place the rad monitoring pumps 2-SW-P-5, 6, 7 and 8 to the on position and rod drive cooling fans 2-EV-37 A B C D E and F to the off position. This will prevent the pumps from stopping and fans starting when the CDA Signal is reset.

4.8.1 Reset containment spray actuation with the " RESET" switches.

NOTE: Resetting of the " CONTAINMENT SPRAY ACTUATION" does not i automatically stop safeguards equipment except the equipm4 't in the caution above after stop safeguards equipment. Stopping of the safeguards equipment is controlled by the subsequent steps of this procedure or as emergency conditions dictate.

NOTE: Subsequent to resetting the spray actuation signal should a loss of offsite power occur, manual restart of spray, and casing cooling pumps will be required.

4.11 If RCS pressure has decreased to < 600 psig, verify accumulator injection. (LI-2920, 2924, 2928) 4.12 If RCS pressure has decreased to <175 psig, verify LHSI flow (FI-2945, 2946).

4.13 If there is high activity in the service water discharge from a recire. spray heat exchanger, close the affected heat exchanger service water inlet and outlet valves (keylock switches in the l

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2-EP-2 Page 8 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

service water logic panel must be in defeat), secure the as-sociated radiation monitoring semple pump, and secure the associated recire. spray pump as indicated below:

HEAT EXCHANGER RS PUMP RAD. PUMP SW VALVES SW CABINET 2-RS-E-1A 2-RS-P-1A 2-SW-P-5 MOV-SW-203A 2-EP-CB-28H MOV-SW-204A Train A-H Bus 2-RS-E-1B 2-RS-P-1B 2-SW-P-6 MOV-SW-203B 2-EP-CB-28J MOV-SW-204B Train B-J Bus 2-RS-E-lc 2-RS-P-23 2-SW-P-7 MOV-SW-203C 2-EP-CB-28J MOV-SW-204C Train B-J Bus 2-RS-E-lD 2,-RS-P-2A 2-SW-P-8 MOV-SW-203D 2-EP-CB-28H MOV-SW-204D Train A-H Bus NOTE: Two heat exchangers are needed intially and one heat exchanger is required for long-tern cooling after the first 24 hrs.

4.14 Continue to monitor auxiliarf feedwater flow and make-up to 2-CN-TK-1 (emergency condensate storage tank) as per 2-OP-31.2.

4.15 The emergency diesel generators should not be operated at idle speed or minimum load for extended periods of time. Verify with the System Operator that the VEPCO power system is stable, then return the station service electrical systems to normal as per 2-AP-10 and return the emergency busses and emergency diesel generators to normal as per 2-OP-6.

NOTE: In the event of a simultaneous Loss of Coolant Accident and a Loss of Station Power while only one (1) Emergency Diesel is supply power to its respective emergency bus (other emergency diesel being inoperable), DO NOT shut down the last running diesel under any circumstances until ordered by administrative authority after accident has been terminated.

2-EP-2 Page 9 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.16 Terminate the cold leg injection mode and initiate the cold leg recirculation mode when the RWST level decreases to 28.1% as follows:

4.16.1 Verify that two charging pumps are running.

4.16.2 Close MOV-2370, RCP seal water injection.

4.16.3 Open the low head safety injection pump discharge valves to the charging pump suctions (MOV-2863A, MOV-2863B).

4.16.4 Close the low head safety injection ' pump miniflow recire. valves to the RWST (MOV-2885A, MOV-2885C, MOV-2885B, MOV-2885D).

4.16.5 Open the LHSI suction valves to the containment sump i MOV-2860A, 2860B.

i 4.16.6 Close the LHSI suction valves from the RWST MOV-2862A, 28623.

NOTE: Upon receipt of the "RWST in bypass mode" alarm at 25.5%, the above actions in 4.16.3 through 4.16.6 will occur automatically.

4.16.7 Clo.e the charging pump suction valves from the RWST MOV-2115B, MOV-2115D.

l 4.17 Periodically monitor the auxiliary building area radiation l monitors for detection of leakage from the ECCS during recir-culation. If significant leakage is identified; attempt to isolate the leakage. Recirculation flow must be maintained to the RCS at all times.

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2-EP-2 Page 10 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.18 Establish high head flow-path redundancy for long term passive failure protection as follows:

4.18.1 Open the alternate cold leg recirculation path valve MOV-2836.

4.18.2 Align one charging pump to discharge only through the boron injection tank by closing its associated valve indicated below:

2-CH-P-1A MOV-2287A 2-CH-P-13 MOV-2287B 2-CH-P-lc MOV-2287C 4.18.3 Align the other operating charging pump to discharge only through the alternate path by closing its assoc-iated valve indicated below:

2-CH-P- LA MOV-2286A 2-CH-P-1B MOV-2286B 2-CH-P-lC MOV-2286C 4.18.4 Isolate the flow path around the discharge of the third (non-operating) charging pump by closing its associated discharge valves indicated bel'ow:

2-CH-P-1A MOV-2286A, 2287A 2-CH-P-1B MOV-2286B, 2287B 2-CH-P-1C MOV-2286C, 2287C 4.19 Secure the Quench Spray pumps when it is proven that the pumps are not pumping anymore water by completing the following

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, actions.

2-EP-2 Page 11 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.19.1 Stop the Quench Spray Pumps:

2-QS-P- LA 2-QS-P-1B 4.19.2 Close the Quench Spray Pumps Suction and Discharge Valves:

MOV-QS-200A MOV-QS-20LA MOV-QS-200B MOV-QS-201B 4.20 Monitor performance of the LHSI and the Outside Recire. Spray pumps by initiating the POST LOCA LOG (Attachment 4). Record data at approximately 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> intervals or as directed by the l Shift Supervisor / Emergency Director. Pay particular attention to trends developing which would indicate LHSI pumps perfor-mance degradation.

4.21 Place the Control Poom Emergency Vent System in service approx-imately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after safety injection initiation as per 1-OP-21.7.

4.22 When casing cooling tank level decreases to 2.5%:

4.22.1 Verify MOV-RS-200A and B closes.

4.22.2 Stop casing cooling pumps 2-RS-P-3A and 3B.

I 4.23 Approximately 18 hrs. af ter the LOCA, terminate the cold leg i

recirculation mode and initiate the hot leg recirculation mode as follows:

4.23.1 Close the LHSI discharge valves to the cold legs, MOV-2864A, 2864C, 2890B, 2890D.

l 4.23.2 Open the LHSI discharge valves to the hot legs, MOV-l 2890A, 2890B.

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2-EP-2 Page 12 of 14 05-22-80 Xnitials 4.0 Long Term Operator Actions (cont.)

4.23.3 Stop the charging pump that is operating through the boron injection tank.

4.23v4 Close the boron injection tank isolation valves, MOV-2867A, 2867C, 2867B, 2867D.

4.23.5 Open MOV-2869B.

. 4.23.6 Restart the charging pump stopped above. Flow rate will be indicated on FI-2943, FI-2960, FI-2933, and FI-2932.

4.23.7 Stop the charging pump that is discharging through the alternate path.

4.23.8 Close the alternate cold leg S.I. valve, MOV-2836.

4.23.9 Open the charging pump discharge header S.I. stop valve, MOV-2869A.

! 4.23.10 Restart the charging pump stopped in step 4.23.7.

4.24 Between 24 and 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the LOCA has occurred, verify that redundant operating equipment is operable and then:

4.24.1 Stop one inside recire spray pump (2-RS-P-1A or IB) 4.24.2 Stop one outside recirc spray pump (2-RS-P-2A, or 2B) 4.24.3 Stop all but oae charging pump (2-CH-P-1A, or IB, or IC)

! 4.24.4 Stop the low naad safety injection pump that is powered i

by the same bus as the charging pump stopped above (step 4.23.3)

, CHARGING PUMP l STOPPED LHSI PUMP STOPPED l

2-CH-P-1A or 2-CH-P-1C (H BUS) 2-SI-P-1A 2-CH-P-1B or 2-CH-P-1C (J BUS) 2-SI-P-1B l

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- 2-EP-2 Page 13 of 14 05-22-80 '

Initials 4.0 Long Term Operator Actions (cont.)

If after going to single train operation following the LOCA one LHSI cannot supply sufficient flow per Attachment 5, restart the other LHSI pump secured above.

4.24.5 Close redundant charging pump suction valves:

Pump Verifv Open Then Close 2-CH-P-1A. MOV-2267B MOV-2267A 2-CH-P-1B MOV-2269A MOV-2269B 2-CH-P-1C (H Bus) MOV-2270B MOV-227)A 2-CH-P-1C (J Bus) MOV-2270A MOV-22 70B 4.25 Approximately 27 hrs. after the initiation of hot leg recire-ulation mode, switch over to cold leg recirculation mode as follows:

4.25.1 Close the LHSI discharge valves to the hot legs, MOV-2899A, 2890B.

4.25.2 Open the LHSI discharge valves to the cold legs, MOV-2864A, 2864C, 2890B, 2890D.

4.25.3 Stop the operating charging pump.

4.25 .4 Close MOV-2869B.

4.25.5 Open the boron injection tank isolation valves, MOV-2867A, 2867C, 2867B, 2867D.

4. 25 .6 Close MOV-2869A.

4.25.7 Open MOV-2836.

4. 25 .8 Restart the charging pump stopped in step 4.25.3. Flow l rate will be indicated on FI-2943, FI-2961, FI-2962 and l

FI-2963.

2-EP-2 Page 14 of 14 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.26 Approximately 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> after initiation of cold leg recircu-lation, switch over to the hot leg recirculation modes as follows:

4.26.1 Close the LHSI discharge valves to the cold legs, MOV-2864A, 2890C, 28648, 2890D.

4.26.2 Open the LHSI discharge valves to the hot legs, MOV-2890A, 2890B.

4.26.3 Stop the operating charging pump.

4.26.4 Close the boron injection tank isolation valves, MOV-2867A, 2867C, 2367B, 2867D.

4.26.5 Open MOV-28698.

4.26.6 Close the alternate cold leg S.I. valve, MOV-2836.

4.26.7 Open MOV-2869A.

4.26.8 Restart the charging pump stopped in step 4.26.3. Flow

. rate will be indicated on FI-2943, 2960, 2933, and 2932.

4.27 At intervals not to exceed 27 houra alternate between hot and cold leg recirculation flow by repeating section 4.25 and 4.26 as applicable.

l 4.28 Continue RCS cooldown and depressurization as per 1-OP-3 and/or I

, based on further administrative decisions.

NOTE: If the cooldown is by natural circulation, continue to monitor and verify natural circulation as per attach-ment 2.

CAUTION: All parameter changes shall be performed slowly with extreme caution during cooldown on natural circulation.

Completed By:

Date:

2-EP-2 Attachment #1 Page 1 of 2 05-22-80 Initials Securing Safety Injection

1. Verify or reset safety injection train A and B by use of the control board reset pushbuttons.

2. Secure lowhead safaty injection pumps (2-SI-P-1A and IB) and Place the Control Switches to " Auto After Stoo".

3. Open MOV-2289A charging line isol. on FCV-2122.

4. Secure the second operating charging pump and place its control switch to " Auto After Stop".

5. Shift FCV-2122 (charging flow controller) to manual and run it closed.

6. Shift PQV-2145 low press letdown pressure controller to manual and set to

• 50% open

7. Open TV-2204 letdown line isolation trip valve.

8. Open MOV-2380 and MOV-2381 seal water return isolations.

9. Open LCV-2460A and 2460B letdown isolation valves from "A" loop.

10. Verify blender set for cold shutdown concentration and in auto make l

up mode.

11. Verify HCV-2310 open.

12. Verify HCV-2311 (aux. spray) closed.

13. Open 2289B (charging line isolation on FCV-2122).

14. Open charging pump recire, valves.

l MOV-2275A 2-CH-P-1A l MOV-2275B 2 CH-P-1B l MOV-2275C 2-CH-P-IC MOV-2373

• Common Recire l 15. Shift charging pumps suction from RWST to VCT as follows:

15.1 Verify VCT level > 20%.

15.2 Open MOV-2115C and 2115E.

15.3 When MOV-2115C and 2115E are full open verify MOV-2115B and l 2115D go closed.

2-EP-2 "

Attachment #1 Page 2 of 2 05-22-80 Initials Securing Safety Injection (cont.)

16. Open FCV-2122 to

• 20% open slowly.

17. Isolate flow thru Unit 1 boron injection tank by closing the fol-lowing:

MOV-2867A BIT inlet MOV-2867C BIT inlet MOV-2867B BIT outlet MOV-2867D BIT outlet

18. Open HCV-2200A (45 gpm orifice isolation).

19. Control PCV-2145 in manual to maintais 450-550 psig letdown line pressure until letdown line temperature decreases to normal.

20. Slowly adjust letdown line pressure to

• 300 psig then shift PCV-2145 to auto.

NOTE: Monitor letdown radiation readings, reisolate letdown if read-ing exceeds 1000 times original. (could indicate excessive fuel failure)

21. Control FCV-2122 to maintain s 50% pressurizer level. 60 GPM orifice isolation valves 2200B and or 2200C may be required to be open to maintain level.

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2-2P-2 Attachment #2 Page 1 of 4 05-22-80 Natural Circulation Verification Initials CAUTION: During the conduct of this instruction, the RWST level should be monitored for switchover to cold leg recir-culation, if required.

CAUTION: If the high range readings from the core exit thermo-couples are not available, a condition of inadequate core cooling exists when: the hot leg RTD's are pegged high or five or more incore thermocouples are off-scale above 700*F and SI flow is not being delivered to the RCS and AFW is not being delivered to the intact steam generators.

CAUTION: If during the verification of natural circulation it is determined that the core is not being adequately cooled, proceed to Step 10.0.

CAUTION: Trip the pressurizer heaters, containment Air Recire.

Fan (s) and the Rod Drive Cooling Fan (s) to prevent overlaading the Emergency Diesel Generators in the event that a SI occurs anytime during a balckout.

NOTE: Only one bank of backup heaters maybe required to maintain pressurizer pressure during natural cir-culation; there-fore load reduction will only be required on the diesel which will supply the heaters to be utilized.

NOTE: The pressurizer heaters are required to be in service within 1 br. of entry into natural circulation.

1.0 All operable steam generators shall be maintained in the narrow range level indication range (tubes covered) by manual control of auxiliary feed flows (prefered

• 33% level).

1.1 Verify steam generators operable by (J) check.

i "A" S/G "B" S/G "C" S/G 2.0 The AT (wide range Th - wide range Tc) for reactor coolant loops with operable steam generators should be between 25% and 80% of full power values (15*F to 56*F) as determined from TR-2413 (W.R. Th) and TR-2410 (W.R. Tc).

2.1 "A" Loop W.R. Th (T-2413) - W.R. Tc (T-2410) = AT F- *F = *F 2.2 "B" Loop W.R. Th (T-2423) - W.R. Tc (T-2420) = ST F- *F = *F

1 2-EP-2 Attachment #2 Page 2 of 4 05-22-80 Natural Circulation Verification (cont.)

Initials 2.3 "C" Loop W.R. Th (T-2433) - W.R. Tc (T-2430) = AT

• F - F = *F 3.0 Verify that the wide range Th indications as observed on TR-2413 are stable or decreasing.

4.0 Pressurizer pressure shall be maintained high enough to assure 2 50*F subcooling from the highest wide range operable Th indication from TR-2413, verification shall be made from the posted saturation graph.

5.0 Pressurizer level shall be maintained in manual level control.

CAUTIOL high energy break in containment can cause up to 40%

indication error in pressurizer level. To secure

safety injection under this condia. ion pressurizer level must be 2 50% and maintained there.

5.1 LI-2459 A _ ,  %

5.2 LI-2460  %

5.3 LI-2461  %

6.0 Record the incore thermocouple temperatures as required below SWITCH POSITION # CORE LOCATION TEMP. *F 4

10 J10 17 E10 18 F9 20 DS l

l 24 E4 __

33 K5 36 L6

45 M9 7.0 Print out A incore ther

nocouple map (short form-most recent) on utility typewriter (refer to page A-45 of computer codebook if uti-lity typewriter is inoperable).

l 7.1 Press "Incore T/C Map" pushbutton l

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2-EP-2 Attachment #2 Page 3 of 4 05-22-80 Natural Circulation Verification (cont.)

Initials 7.2 25 value 1 7.3 10 value 2 7.4 1 value 3 7.5 Press " Start" pushbutton NOTE: Verify that the incore temperatures all show 2 50 F subcooling from saturation, as they are the most reli-able temperature indication.

NOTE: The incore thermocouple maps should be run every N 30 min for continued verification of co.oldown.

8.0 Verify that the operable steam generator pressures are following the saturation curve for the wide range Tc using the following.

8.1 "A" Steam Generator PI-2474 psig PI-2475 psig PI 2476 psig 8.2 "B" Steam Generator PI-2484 psig PI-2485 psig PI 2486 psig 8.3 "C" Steam Generator PI-2494 psig PI-2495 psig PI 2496 psig 9.0 Make all changes in auxiliary feed water flow, and steam flow slowly to prevent upset to the thermal driving head of natural circulation during plant subsequent cooldown.

10.0 If it has been determined that the core is not being adequately cooled in natural circulation, as verified by increasing core exit thermocouple readings. Commence the following actions as required to restore adequate core cooling.

NOTE: If any of the below actions correct the malfunction refer back to Step 1.0 to verify proper cooling.

2-EP-2 Attachment #2 Page 4 of 4 05-22-80 Natural Circulation Verification (cont.)

Initials 10.1 Increase the steaming rate from the operable steam generators by:

10.1.1 Dumping steam to the main condenser via steam dumps.

10.1.2 Operation of power operated relief valves.

10.2 Open the pressurizer power operated relief valves as required.

NOTE: Open the pressurizer PORV's only if:

1. SIS or charging is available to deliver to the RCS.

2. RCS depressurization cannot be accomplished by steam relief from the steam generators.

3. Feedwater is not available to maintain the steam generator secondary water level at an effective level.

10.3 If no means for RCS depressurization are available, or if the depres-surization did not result in decreasing core exit thermocouple tem-peratures, then start a reactor coolant pump, if possible.

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2-EP-2 Attachment 3 Page 1 of 8 05-22-80 Initials VERIFICATION OF $A AND/0R OB CONTAINMENT ISOLATION FROM SI AND/OR CDA

1. SI ($A) Verification 1.1 Verify Automatic Valve Operation on "H" Safeguards Panel.

(J) OPEN (RED)

MOV-2867A BIT inlet MOV-2867C BIT outlet MOV-SW-200A SW to Spray header MOV-SW-200B SW to Spray header (J) CLOSED (GREEN)

TV-2884A BIT recire.

TV-2884C BIT recire.

MOV-2380 Seal water return (J) (J) (4) (/) (J) (J) (J) (J) (/) (J)

BD CV DA LM LM RM SI SS SS SS 200A 250A 200A 200C 201A&C 200A 200A 200A 203 212A BD CV DG LM VG RM MS SS SS IA 200C 250C 200A 200E 200A 200B 209A 201A 204A 201A BD SI LM LM TV MS TV SS SS IA 200E 201 200A 200G 2519A 210A 2859 202A 206A 202A SV SV 202-1 202-2 Valve Monitor #3 light off

_ _ _.- - . , _ _ _ _ . _ , ~ . . _ . . , _ _ . . _ , _ _ _ _ _ . _ _ , _ _ _ . _ _ _ , _ . _ _ _ _ . _ . . _ _ _ _ . - _ _ _

2-EP-2 Attachment 3 Page 2 of 8 05-22-80 Xnitials 1.0 SI (oA) Verification (cont.)

1.2 Verify Automatic Valve Operation on "J" Safeguards Panel.

(l) OPEN (RED)

MOV-2867B BIT inlet MOV-2867D BIT outlet

(/) CLOSED (GREEN)

TV-2884B BIT recire.

MOV-2381 Seal water return (l) (/) (/) (l) (/) (/) (/) C/) (/) (/)

BD CV DA LM LM RM SI SS SS SS 200B 250B 2008 200D 201B&b 200C 200B 200B 203B 212B l

BD CV DG LM VG RM MS SS SS IA 200D 250D 200B 200F 200B 200D 209B 201B 204B 201B l

BD SI LM LM MS TV TV SS SS IA 200F 2936 200B 200H 210B 2204 2842 202B 206B 202B SV 203 __

l

2-EP-2 Attachment 3 Page 3 of 8 05-22-80

Initials, 1.0 SI ($A) Verification (cont.)

1.3 Verify Automatic Valve Operation on "Benchboard".

(/) OPEN (RED)

MOV-2115D RWST to Chg. pumps MOV-2115B RWST to Chg. pumps

(/) CLOSED (GREEN)

MOV-2115C VCT to Chg. pumps MOV-2115E VCT to Chg. pumps MOV-2289A Normal charging header MOV-2289B Normal charging header MOV-2373 Common recire.

HCV-2200A Letdown orifice HCV-2200B Letdown orifice HCV-2200C Letdown orifice

(/) CLOSED ON LOW PZR LEVEL (GREEN) (< 15% Level)

LCV-2460A Letdown isolation LCV-2460B Letdown isolation 1.4 Verify Automatic Valve Operation on " Backboard".

(/) CLOSED (GREEN)

MOV-2275A 2-CH-P-1A Recire.

MOV-2275B 2-CH-P-1B Recire.

MOV-2275C 2-CH-P-1C Recire.

i 2-EP-2 Attachment 3 Page 4 of 8 05-22-80 Initials 1.0 SI ($A) Verification (cont.)

1.5 Verify the following Automatic Actions:

1. 2 Ventilation Panel:

(/) CLOSED (GREEN)

A0D-HV-160-2 Control room vent A0D-HV-161-2 Control room vent

1. 1 Ventilation Panel:

(/) CLOSED (GREEN)

A0D-HV-160-1 Control room vent A0D-HV-161-1 Control room vent 1-HV-F-15 (Tripped) Control room exhaust fan 1.6 Verify auto initiation of the bottled fresh air supply to the control room (PI-HV-1311, PI-HV-2311), and positive pressure in the control room (PDI-HV-100, PDI-HV-200).

1.7 Verify that the containment vacuum pumps trip (2-CV-P-3A, 2-CV-P-3B).

1.8 Verify 1-SW-P-1B and 2-SW-P-1B started and that 1-SW-P-1A or 1-SW-P-4 and that 2-SW-P-1A or 2-SW-P-4 started.

a 0

2-EP-2 Attachment 3 Page 5 of 8 Initials 05-22-80 2.0 CDA ($B) Verification (This section is to be completed only if required) 2.1 Verify the following Automatic Operations on "H" Safeguards Panel.

(/) CI,0 SED (GREEN)

(/) (J) (4) (J)

CC CC CC CC 205A 202A 204A 201A CC CC CC CC 205B 202C 204B 203A CC CC CC

• 205C 202E 204C MOV-SW-210A Air recire. cooler MOV-SW-214A Air recire. cooler MOV-Sti-208A Component cooling (J) OPEN (RED)

MOV-SW-203A RS HX A supply MOV-SW-203D RS HX D supply MOV-SW-204A RS HX A return MOV-SW-204D RS EX D return MOV-SW-201A RS HX header supply MOV-SW-201C RS HX header supply MOV e'l-205A RS HX header return MOV-SW-205C RS HX header return MOV-QS-200A QS pump suction MOV-QS-201A QS pump discharge MOV-QS-202A From chem. add. tank (5 min. T.D.)

MOV-RS-256A RS pump discharge MOV-RS-255A RS pump suction 2-QS-P-1A Quench spray pump starts 2-RS-P-1A Inside recire, spray pump starts after 3 h min. T.D. (Verify rotation by blue light lit) 2-RS-P-2A Outside recire. spray pump starts after 3 \

min. T.D.

2-EP-2 -

4 Attachment 3 Page 6 of 8 Enitials 05-22-80 2.0 CDA ($) Verification (cont.)

2.2 Verify the following Automatic Operations on "J" Safeguards panel.

(J) CLOSED (GREEN)

(J) (J) (J) (J)

CC CC CC CC 200A 202B 204A 201B CC CC CC CC 200B 202D 204B 203B CC CC CC 200C 202F 204C MOV-SW-210B Air recire. cooler MOV-SW-214B Air recire. cooler

_ ,_ MOV-SW-208B Component cooling (Jj OPEN (RED)

MOV-SW-203B RS HX A supply

_ _,_ MOV-SW-203C RS HX D supply MOV-SW-204B RS HX A return MOV-SW-204C RS HX D return MOV-SW-2013 RS HX header supply MOV-SW-201D RS HX header supply MOV-SW-205B RS HX header return MOV-SW-205D RS HX header return MOV-QS-200B QS pump suction I QS pump discharge MOV-QS-201B MOV-QS-202B Trom chem add. ta,nk (5 min. T.D.)

MOV-RS-2568 RS pump discharge MOV-RS-255B RS pump suction 2-QS-P-1B Quench spray pump starts 2-RS-P-1B Inside recire. spray pump starts after 3 h min. T.D. (Verify rotation by blue light lit) 2-RS-P-2B Outside recire. spray pump starts after 3 min. T.D.

m . __ -.

9 2-EP-2 Attachment 3 Page 7 of 8 05-22-80 Initials 2.0 CDA (0) Verification (cont.)

2.3 Verify the following Automatic Operations on the bottled air /

casing cooling panel.

(/)

2-RS-P-3A casing cooling pump starts 2-RS-P-3B casing cooling pump starts MOV-RS-200B casing cooling supply open MOV-RS-201A casing cooling supply open ROV-RS-200A casing cooling supply open MOV-RS-201B casing cooling supply open 2.4 Verify the following Automatic Operations on Ventilation Panel.

2.4.1 "H" Bus Powered Section

(/) TRIPPED 2-HV-F-1A Air recire. fan 2-HV-F-1C Air recire. fan 2-HV-F-37A CRDM cooling fan 2-HV-F-37B CRDM cooling fan 2-HV-F-37C CRDM cooling fan

(/) CLOSED (GREEN)

TV-SW-201A Air recire. cooler supply TV-SW-201B Air recire, cooler return .

MOV-SW-210A Air recire. cooler return MOV-SW-214A Air recire, cooler return DIVERT TO IODINE FILTER A0D-HV-107B Aux. Bldg.

A0D-HV-22S Sfgd. Bldg.

2-EP-2 Attachment 3 Page 8 of 8 Xnitials 05-22-80 2.0 CDA ($B) Verification (cont.)

2.4.2 "J" Bus Powered Section (J) TRIPPED 2-HV-F-1B Air recire, fan 2-HV-F-1C Air recire. fan 2-HV-F-37D CRDM cooling fan 2-HV-F-37E CRDM cooling fan 2-HV-F-37F CRDM cooling fan (J) CLOSED (GREEN)

TV-SW-201A Air recire. cooler supply TV-SW-201B Air recire. cooler return MOV-SW-210B Air recire. cooler return MOV-SW-214B Air recire. cooler return DIVERT TO IODINE FILTER A0D-HV-107A Aux. Bldg.

A0D-HV-228 Sfgd. Bldg.

l 2.5 Verify Automatic starts on radiation monitoring panel.

l t

(/) SAMPLE PUMPS RUNNING (After 2 min. T.D.)

(Verify red " low flow" lights not "0N".)

2-SW-P-5 for RS HX 2-RS-E-1A 2-SW-P-6 for RS HX 2-RS-E-1B 2-SW-P-7 for RS EX 2-RS-E-1C 2-SW-P-8 for RS HX 2-RS-E-1D 2.6 On the Main Control Board verify that the component cooling water pumps trip (J).

2-CC-P-1A 2-CC-P-1B

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