ML19312E574

Loss of Secondary Coolant, Revised Emergency Procedures

ML19312E574
Person / Time
Site:	North Anna
Issue date:	05/22/1980
From:	Harvey S, Kellame J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19312E567	List: ML19312E566 ML19312E568 ML19312E570 ML19312E574 ML19312E579 ML19312E581
References
2-EP-3, NUDOCS 8006050336
Download: ML19312E574 (30)

Text

7

-m 2-EP-3 Page 1 of 16 05-22-80 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 LOSS OF SECONDARY COOLANT

REFERENCES:

1. FSAR Section 9, in 15

2. Westinghouse E:nergency Procedures.

3. S.M. File Letter 7.17

4. EPIP-6

. 5. I.E. Bulletin #79-06A,79-06C REV. 8 PAGE: Entire DATE: 05-22-80 APPROVAL: Mk

%3 1

PER{

NOT a  % [s docu %t i ,,[-oportiOf'"'

w , .; e r C O S #' I LLED .'.$r,qinia ElCOTI C - a.w w *

, , , ,, e rur=c,i bon 700.335t'g 1, ,me. f,,

M A T p* - - n r313313 - di3 1000

'~  ;

fQ.o.icca, trM l. ;,,$ contataed in If NCrg N 3 ,

, , ,, 3.,j ..u c . e *

• ,A T m r;g y;g ,c N

~

gg$g $cc=w'

• RECOMMENDED APPROVAL: w[i .</b- / stil APPROVED BY: '@ w CHAI@TATION NL' CLEAR SAFETY AND OPERATING COMMITTEE DATE: 05-22-80 SAFETY RELATED 8006050  % GP

2-EP-3 Page 2 of 16 05-22-80 1.0 Indications 1.1 ABNORMALLY LOW PRESSURE IN ONE OR ALL STEAM GENERATORS 1.2 Steam flow - feed flow mismatch.

1.3 Steam line isolation.

1.4 Increasing containment pressure and temperature (rupture in containment).

1.5 Abnormal steam generator levels.

1.6 Rapidly decreasing T,y with decreasing Pzr level and pressure.

2.0 Automatic Actions 2.1 Reactor trip on any of the following:

. 2.1.1 Low Pressurizer Pressure (1870 psig) 2.1.2 High Pressurizer Pressure (2385 psig) 2.1.3 Safety Injection 2.1.4 Power Range Hi $

2.1.5 Overpower A T 2.1.6 Overtemperature A T 2.1.7 Low-low steam generator water level (18%)

2.1.8 Steam flow feedflow mismatch (40%) with low level l

l (25%).

l l

[

l 2.2 Safety injection due to any of the following:

2.2.1 High steam line flow with low T,y (543*F) or low steam line pressure (600 psig).

I i 2.2.2 Low pressurizer pressure (1765 psig).

2.2.3 High steam line differential pressure (100 psig).

2.2.4 Containment high pressure (> 17 psia).

2-EP-3 Page 3 of 16 05-22-80

, 2.0 Automatic Actions (cont.)

2.3 Steam line isolation due to:

2.3.1 Containment intermediate high/high pressure (> 17.8 psia).

2.3.2 High steam line flow wi-5 low T,y (543*F) or low steam line pressure (500 psig).

2.4 Quench spray actuation on containment hib h/high pressure (> 25 psia).

l j

i t

l l

4

2-EP-3 Page 4 of 16 05-22-80 3.0 Immediate Operator Actions 3.1 1-EP-1 Immediate Actions have been completed.

NOTE: 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 & J) are energized, and both diesels are running.

3.2.2 Verify phase "A" isolation 3.2.3 Verify feedwater isolation 3.2.4 Verify that the auxiliary feedwater pumps (2-FW-P-2),

2-FW-P-3A and 3B) have started and are flowing (FI-FW-200 A, B, and 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*F) or high steam flow - low pressure (600 psig).

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.

2-EP-3 Page 5 of 16 05-22-80 Initials 4.0 Long Term Operator Actions NOTE: The process variables referred to in this Instruction are typically monitored by more than one instrumenta-tion channel. The redundant channels should be checked for consistency while performing the steps -f this Instruction.

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: Do not operate the coolant loop isolation valves.

NOTE: In the event of a simultaneous Loss of Secondary Coolant Accident and a Loss of Station Power while only one (1)

Emergency Diesel is supplying 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.

NOTE: If the criteria for securing safety injection can be met, proceed to Step 4.15.

NOTE: If the reactor coolant system pressure decreases in an uncontrolled manner to (<1485 psig) secure all reactor coolant pumps.

CAUTION: If component cooling water to the reactor coolant i pumps is isolated on a containment pressure signal, all

reactor coolant pumps should be stopped within 5 minutes l because of loss of motor bearing cooling.9 t

l CAUTION: If the resctor coolant pumps are stopped, the seal injection flow should be maintained.

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

l 2730 kw and acutal pressurizer level is greater than l 10%. Equipment wnich 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 l

l

2-EP-3 Page 6 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.1 Verify steam line isolation as follows, if required.

4.1.1 On "H" bus safeguards panel, checkmark the following:

(J) CLOSED (GREEN)

TV-MS-201A-1 TV-MS-2018-1 TV-MS-201C-1 TV-MS-213A-1 TV-MS-2138-1 TV-MS-213C-1 4.1.2 On J" bus safeguards panel, checkmark as follows:

TV-MS-201A-2 TV-MS-201B-2 TV-MS-201C-2 TV-MS-213A-2 TV-MS-213B-2 TV-MS-213C-2 4.1.3 If one or more TV's have not closed,'close the respec-tive S/G NRV's, if required.

S/G A NRV-MS-201A NRV-MS-203A S/G B NRV-MS-201B NRV-MS-233B S/G C NRV-MS-201C NRV-MS-203C 4.2 Verify the following equipment operating 4.2.1 One charging pump is running on each operable emergency bus.

4.2.2 Both low head SI pumps running (2-SI-P-1A and IB).

4.3 Verify safety injection flow co the core:

4.3.1 Cold leg flow (FI-2961, FI-2962, FI-2963).

4.3.2 Boron injection tank pressure (PI-2934).

i L

l 1

2-EP-3 1 Page 7 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.4 Verify feedwater isolation:

4.4.1 Main feedwater pumps trip and discharge valves close (MOV-FW-250A, 250B, 250C).

4.4.2 Main and bypass feedwater regulator valves close (FCV-2478, 2488, 2498; FCV-2479, 2489, 2499).

4.4.3 Feed reg. valve isolation valves close (MOV-254A, B, and C).

4.5 Issue attachment #3 of this procedure for SI($A) and/or CDA

($B) isolation verification.

4.6 Determine which is the affected steam generator by recording and comparing the following:

4.6.1 Steam Generator Pressures A B C 4.6.2 Steam Generator Levels A B C 4.6.3 Auxiliary Feedwater Flows A B C 4.6.4 Auxiliary Feedwater Pressures A B C 4.7 Isolate main steam flow from the affected steam generator as follows, 4.7.1 To isolate "A" Steam Generator:

Close TV-MS-201A Close TV-MS-213A l

l

l l

2-EP-3 Page 8 of 16 05-22-80 fnitials 4.0 Long Term Operator Actions (cont.)

4.7.2 To isolate "B" Steam Generator:

Close TV-MS-201B Close TV-MS-213B 4.7.3 To isolate "C" Steam Generator:

Close TV-MS-201C Close TV-MS-213C 4.8 Isolate auxiliary feedwater to the affected steam generator as follows:

4.8.1 To isolate auxiliary feed to "A" steam generator.

Close TV-MS-211A Close TV-MS-211B Close MOV-FW-200D 4.8.2 To isolate auxiliary feed to "B" steam generator.

Place 2-FW-P-3B in " Pull to Lock".

Close MOV-FW-200B.

4.8.3 To isolate auxiliary feed to "C" steam generator.

Place 2-FW-P-3A in " Pull to Lock".

Close MOV-FW-200C.

NOTE: If any steam generator, which is operable, does not have a rutning aux. feedwater pump, or is not getting proper flow, attempt to correct the problem or refer to 1-AP-22.

4.9 Regulate the auxiliary feedwater flow to the unaffected steam generators to restore and/or maintain an indicated narrow range steam generator water level sufficient to assure that the steam generator tubes are covered. If wate- level increases in an unexplained manaer in one steam generator, go to EP-4 Steam Generator Tube Rupture.

i

-~v , y . , , , - --v- -- -. ~, -, - . - - -

2-CP-3 Page 9 of 16 05-22-80 Iaitials 4.0 Long Term Operator Actions (cont.)

NOTE: Indicated levels in the steam generator may indicate as much as 10% higher than acutal levc1 due to environmental effects on the transmitter.

4.9.1 Monitor auxiliary feedwater pump suction pressures > 4 psig, and maintain 2-CN-TK-1 level above the lo-lo level alarm point (9%) by filling from 1-CN-TK-2 or 2-CN-TK-2 (condensate storage tanks) as per 2-0P-31.2.

4.10 If reactor coolant pumps are not in operation verify natural circulation as per attachment #2.

4.11 Secure waste gas releases from the site:

4.11.1 Close WGDT release valve FCV-GW-101.

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

CAUTION: Do not secure the quench spray pumps when carrying out the long term actions of EP-3 until it is proven that the containment pressure has returned to subatmospher'.c or that tne pumps are not puming anymore water.

4.12 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 to the off position. This will prevent the pumps from stopping and the fans starting when the CDA signal is reset.

4.12.1 Reset containment spray actuation with the " RESET" i

swicches.

NOTE: Resetting of the "CONTAINME.VI' SPRAY ACTUATION" does not automatically stop safeguards equipment except the equipment in the caution above after stop safeguards

, equipment. Stopping of the safeguards equipment is controlled by the subsequent steps of this procedure or

~s emergency conditions dicate.

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

2-CP-3 Page 10 of 16 05-22-80 Xnitials 4.0 Long Term Operator Actions (cont.)

4.13 Reset @B isolation (Train "A" and "B") by use of the " RESET" switches on the control board.

4.14 When the containment pressure has returned to subatmospheric stop the following pumps, if applicable:

4.14.1 Stop the quench spray pumps.

2-QS-P-1A 2-QS-P-1B 4.14.2 Stop the recire. spray pumps.

2-RS-P-1A 2-RS-P-1B 2-RS-P-2A 2-RS-P-2B 4.14.3 Verify MOV-RS-200A and B close.

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

4.15 Perform only applicable portions for securing SI.

4.15.1 For a main steam line break < 350*F safety injection YES N0 may be terminated if all the following criteria are satisfied.

1. One wide range reactor coolant temperature TH **

1 YES NO confirmed by core exit thermocouples, if available, is less than 350*F, AND j __

2. Wide range reactor coolant pressure is gretter than YES NO 700 psig and is stable or increasing AND

3. Pressurizer water level is greater than 20* of span and l

YES N0 rising (heaters covered), AED

4. The reactor coolant indicated subcooling is greater YES NO subcooling AND l

l l

l

2-EP-3 Page 11 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

5. Auxiliary feedvater flow is isolated to all depressurized YES N0 steam generators and at least 690 gpm is being injected into the non-faulted steam generator (s) or at least one steam generator is operable with level in the narrow range. (Wide range level) > 70% should indicate that level is in the narrow range.

NOTE: If all steam generators are depressurized or depress-urizing, the safety injection flow must not be terminated until the faulted loop (s) is identified.

6. If all the above are yes then secure Safety Injection and establish normal charging and letdown as per Attach _

ment 1.

NOTE: If all wide range reactor coolant temperature indicators go above 350*F when attempting to satisfy the conditions of 4.15.1, initiate safety injection pump operation and continue operation until conditions of 4.15.; or 4.15.3 (depending on containment indications) are satisfied.

4.15.2 For a main stean line break > 350*F safety injection YES NO may be terminated if all the following criteria are satisfied.

1. All wide range reactor coolant temperature TH *#*

YES No greater than 350*F, AND

2. Containment pressure, AND containment radiation, AND YES NO containment recirculation sump levels do not exhibit either abnormally high or increasing readings, .g 3}

3. Wide range reactor coolant pressure is greater than YES NO 2000 psig, and is stable or increasing, AND

4. Pressurizer water level is greater than 20 percent of YES N0 span, AND

2-EP-3 Page 12 of 16 ,

05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

5. The reactor coolant indicated subcooling is greater YES NO than 50* subcooling, AND

6. Auxiliary feedwater flow is isolated to all depress-YES NO urized steam generators and at least 690 gnm is being injected into the non-faulted steam generator (s) or at least one steam generator is operable with level in the narrow range. (Widerange level 770% should indicate that level is in narrow range).

NOTE: If all steam generators are depressurized or depress-urizing, the safety injection flow must not be terminated until the faulted loops is identified.

7. If all the above are yes then secure Safety Injection and establish normal charging and letdown as per Attach-ment 1.

NOTE: If containment pressure, or containment radiation, or containment recirculation sump level exhibit either abnormally high or increasing readings when attempting to satisfy the conditions of 4.15.2, initiate safety injection pump operation and continue operation until the conditions of 4.15.3 are satisfied.

4. 15 .3 For a main steam line break 7350*F 2nd the break is inside containment RC System temperature safety injec-i tion may be terminated if all the following ciritria l

are satisfied.

1. All wide range reactor coolant temperature TH *#*

l

'IES NO greater than 350*F, AND l ___

2. Containment pressure, AND containment radiation, OR YES NO containment recirculation sump levels exhibit abnormally

! high or increasing readings, A.VD

.-c. g .e-.-= - - - - - - ,,- -

2-EP-3 Page 13 of 16 05-22-80 Initi ls l 4.0 Long Term Operator Actions (cont.)

3. Wide range reactor coolant pressure is greater than T2S NO 2000 psig, and is stable or increasing, AND

4. Pressurizer water level is greater than 50 percent YES NO AND

5. The reactor coolant indicated subcooling is greater

, YES N0 than 50' subcooling, AND

6. Auxiliary feedwater flow is isolated to all depress-YES NO urized steam generators and at least 690 gpm is injected into the non-faulted steam generator (s) or at least one steam generator is operable with level in the narrow range. (Widerange level 770% should indicate that level is in narrow range).

7. If all the above are yes then secure Safety Injection and establish normal charging and letdown as per Attach-ment 1.

CAUTION: If wide range reactor coolant pressure decreases by 200

pgi or pressurizer water level decreases by 10 percent of span from the point of safety injection termination or the reactor coolant sub-cooling drops below 50*

subcooling MANUALLY REINITIATE safety injection pump operation xo maintain reactor coolant pressure and I

pressurizer level and request the STA/SRO to reevaluate the accident.

1 l 4.16 Complete long term operator actions of 2-EP-1.

l 4.17 The emergency diesel generators should not be operated at idle speed or minimum load for extended periods of time. Verify l

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.

2-EP-3 Page 14 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

4.18 If 1-SW-P-4 or 2-SW-P-4 is running, when the service water reservoir high level alarm is received, open either MOV-SW-220A and MOV-SW-120A SW header A discharge to lake, or MOV-SW-220B and MOV-SW-120B SW header B discharge to lake. Reclose the set of service water valves that were opened above (MOV-SW-220A and MOV-SW-120A or MOV-SW-2203 and MOV-SW-120B1 when the service water reservoir low level alarm is received. Repeat this step as necessary to maintain service water reservoir level.

CAUTION: 1-SW-P-1B and 2-SW-P-1B will lose suction at a reservoir level of 305'2".

4.19 Restore component cooling water system to service, if necessary, as follows:

4.19.1 Open service water valves to component cooling heat exchangers.

(J)

MOV-SW-208A MOV-SW-2083 4.19.2 Reset and reclose stub bus breakers on "H" and "J" emergency busses.

4.19.3 Start component cooling pump (2-CC-P-1A or 2-CC-P-1B).

4.19.4 Reset and reopen the component cooling water trip ,

l valves to restore CC to reactor coolant pumps.

4.20 If the reactor coolant pumps have been secured due to a uncon-trolled depressurization to (<1485 psig), it is N22 permissible j to restart a reactor coolant pump until the criteria for secur-ing safety injection has been met and plant conditions have t

been evaluated for starting a reactor coolant pump.

I L a

2-EP-3 Page 15 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

NOTE: "A" or "C" reactor coolant pumps are prefered for pressurizer pressure control by spray.

4.21 Reset and re-open @A isolation trip valves as required.

~

4.22 Restore quench spray valve lineup, if necessary, by closing:

MOV-QS-200A MOV-QS-200B MOV-QS-201A MOV-QS-201B MOV-QS-202A MOV-QS-202B Refer to 2-0P-7.10 to restore casing cooling to normal.

4.23 Restore recire. sp sy valve lineup, if necessary, by closing:

MOV-RS-255A MOV-RS-255B MOV-RS-256A MOV-RS-256B 4.24 Restore service water system to normal, as follows:

4.24.1 Stop radiation monitor sample pumps on the recire.

spray heat exchangers, if running.

2-SV-P-5 2-SW-r- 7 l

2-SW-P-6 2-SW-P-8 4.24.2 Isolate service water flow thru the recire. spray heat exchangers as necessary, by closing the following l valves:

2-EP-3 Page 16 of 16 05-22-80 Initials 4.0 Long Term Operator Actions (cont.)

MOV-SW-201A MOV-SW-201B MOV-SW-201C MOV-SW-201D MOV-SW-205A MOV-SW-205B MOV-SW-205C MOV-SW-205D

~ '~

4.24.3 Secure service water pumps as required to get one pump running per header.

4.24.4 Lineup service water system as per 1-0P-49.1 as desired.

4.25 Continue RCS cooldown and depressurization as per 2-0P-3.2 and/or 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:

l l

l l

l

2-EP-3 Attachment r/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 safety injection pumps (2-SI-P-1A and IB) and Place the Control Switches to " Auto After Stop".

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-238C 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 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 MOV-2275B 2-CH-P-1B MOV-2275C 2-CH-P-1C MOV-2373 Common Recire 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 2115D go closed.

l

2-EP-3 Attachment #1 Page 2 of 2 05-22-79 Initials Securing Safety Injection (cont.)

16. Open FCV-2122 to s 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 ot.tlet

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

19. Control PCV-2145 in manual to maintain 450-550 psig Jetdown 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 feel failure)

21. Control FCV-2122 to maintain s 50% pressurizer level. 60 gpm orifice isolation valves 1200B and/or 1200C may be required to be opened to maintain level.

]

2-EP-3 Attachment #2 Page 1 of 4 05-22-80 Natural Circul. tion Verification Initials CAUTION: During the conduct of this instre; tion, the RWST level should be monitored for switchover to coli 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 overloading the Emergency Diesel Generators in the event that a SI occurs anytime during a blackout.

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

NOTE: The pressurizer heaters are required to be in service within 1 hr. 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 (4) check.

l l "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 50*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 I

• F - *F = *F l

2.2 "3" Loop W.R. Th (T-2423) - W.R. Tc (T-2420) = $T or - *F = *F 2.3 "C" Loop W.R. Th (T-2433) - W.R. Tc (T-2430) = AT

• F - *F = *F

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

Initials 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 manuallevel control.

CAUTION: A high energy break in containment can cause up to 40%

indication error in pressurizer level. To secure safety injection under this condition 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 10 J10 17 E10 18 F9 20 D5

24 E4 l

33 K5 l

36 L6 45 M9 7.0 Print out A incore thermocouple map (short form-most recient) on utility typewriter (refer to page A-45 of computer codebook if uti-i lity typewriter is inoperable).

1 I

7.1 Press "Incore T/C Map" pushbutton 7.2 25 value 1 7.3 10 value 2 7.4 1 va he 3 7.5 Press " Start" pushbutton i

I

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

Initials NOTE: Verify that the incore temperatures all show 2 50*F subcooling from saturation, as they .ce the most reli-able temperature inidication.

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

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.

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

10.1.1 Dumping steam tu .ne main condenser via steam dumps.

10.1.2 Operation of S/G power operated relief valves.

10.2 Open the pressurizer power operated relief valves as required.

2-EP-3 Attachment #2 Page 4 of 4 05-22-80 Natural Circulation 7erification (cont.)

Initials 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.

l l

l l

2-EP.-3 Attachment 3 Page 1 of 8 05-22-80 Initials VERIFICATION OF QA AND/0R QB CONTAINMENT ISOLATION FROM SI AND/0R 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) (4) (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 IA j 200C 250C 200A 200E 200A 200U 209A 201A 201A BD SI LM LM TV MS TV SS IA 200E _ 201 _ 200A _ 200G _ 2519A _ 210A _ 2859 _ 202A _ 202A _

SV SV 202-1 202-2 Valve Monitor #3 light off

2-2P-3 '

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

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

(l) OPEN JROD)

MOV-2867B BIT inlet MOV-2867D BIT outlet (J) CLOSED (GREEN)

TV-2884B BIT recire.

MOV-2381 Seal water return (4) (/) (/) (/) (4) (/) (l) (J) (l) (/)

BD CV DA LM LM RM SI SS SS SS 200B 250B 200B 200D 201B&D 200C 200B 200B 203B 2123 BD CV DG LM VG RM MS SS IA 200D 250D 200B 200F 200B 200D 209B 201B 201B BD SI LM LM MS TV TV SS IA 200F 2936 200B 200H 210B 2204 2842 2023 2023 SV 203 __

i

., .n-,- , ., --- ,--- ~,

2-EP-3 J

Attachment 3  ;

Page 3 of 8 05-22-89 Initials 1.0 SI (0A) Verification (cont.)

1.3 Verify Automatic Valve Operation on "Benchboard".

(J) OPEN (RED)

MOV-2115D RWST to Chg. pumps MOV-2115B RWST to Chg. pumps (J) CLCSED (GREEN) dOV-2115C VCT to Chg. pumps MOV-1115E 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 (J) CLOSED ON LOW PZR LEVEL (GREEN) (< 15% Level)

LCV-2460A Letdown isolation LCV-2460B Letdown isolation 1.4 Verify Automatic Valve Operation on " Backboard" (J) CLOSED (GREEN)

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

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

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

w - - - _ - - , -r - , e--.-,- ,

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

1.5 Verify the following Automatic Actions:

1. 2 Ventilation Panel:

(J) CLOSED (GREEN)

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

1. 1 Ventilation Panel:

(J) CLOSED (GREEN) l 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).

l 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.

r

-_ m.-_-. ..,. . - -._, .-.. z_ . - , . . , ,-- - ,- . - _ _ - - - -

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

(/) CLOSED (GREEN)

C/) (J) (/) (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-SW-208A Component cooling

(/) OPEN (RED)

MOV-SW-203A RS EX A supply MOV-SW-203D RS EX D supply MOV-SW-204A RS HX A return MOV-SW-204D RS HX D return MOV-SW-201A RS HX header supply MOV-SW-201C RS EX header supply MOV-SW-205A RS EX header return MOV-SW-205C RG EX 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) l l 2-RS-P-2A Outside recire. spray pump starts after 3 \

min. T.D.

L.

2-EP-3 Attachment 3 Page 6 of 8 Initials 05-22-80 2.0 CDA (9) Verification (cont.)

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

(V) CLOSED (GREEN)

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

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 Compenent cooling

(/) OPEN (RED)

MOV-SW-203B RS EX A supply MOV-SW-203C RS EX D supply MOV-SW-204B RS HX A return MOV-SW-204C RS EX D return MOV-SW-201B RS HX header supply MOV-SW-201D RS EX header supply MOV-SW-205B RS HX header return MOV-SW-205D RS EX header return MOV-QS-200B QS pump suction MOV-QS-201B QS pump discharge MOV-QS-202B From chem. add. tank (5 min. T.D.)

MOV-RS-256B 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-23 Outside recire. spray pump starts af ter 3 \

min. T.D.

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

2.3 Verify the following Automatic Operations on the bottled air /

casing cooling panel.

(J) 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

MOV-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 (J) TRIPPED 2-HV-F-1A Air recire. fan 2-HV-F-1C Air recire. fan t

j 2-HV-F-37A CRDM cooling fan 2-HV-F-37B CRDM cooling fan 2-HV-F-37C CRDM cooling fan (J) CLOSED (GREEN)

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

A0D-HV-228 Sfgd. Bldg.

I

2-EP-3 Attachment 3 Page 8 of 8 Initials 05-22-80 2.0 CDA (CB) 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

(/) 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 l 2.5 Verify Automatic starts on radiation monitoring panel.

(J) 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 EX 2-RS-E-1B 2-SW-P-7 for RS EX 2-RS-E-1C 2-SW-P-8 for RS EX 2-RS-E-ID 2.6 On the Main Control Board verify that the component cooling

! water pumps trip (/) .

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

_ . _ . . _ .