ML19312E581

Safety Injection, Revised Emergency Procedures

ML19312E581
Person / Time
Site:	North Anna
Issue date:	03/13/1980
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-5, NUDOCS 8006050341
Download: ML19312E581 (20)

Text

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2-EP-5 Page 1 of 6 03-13-80 i

l l VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 i

SAFETY INJECTION

REFERENCES:

t j 1. 12050-LSK-28-5C l

2. 12050-Df-95B, C

3. TS 3.5.1, 3.5.4.1, 3.5.5, 3.3.2.1, TABLE 3.3-3.1.b., 3.5.2, 3.5.3

4. 12050,-KSK-21-18

5. IE Bulletin #79-06A,79-06C i

i REV. NO. 5 PAGE: Entire DATE: 03-13-80 REV. NO. 6 PAGE:3,4, DAT?.: 05-22-80 _ APPROVAL:

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2-EP-5

, Page 2 of 6 03-13-80 1.0 Indications 1.1 Reactor trip.

1.2 Safety injection system initiation for no apparent reason.

l 2.0 Probable Causes 2.1 Instrument failure.

2.2 Testing of the safeguards system logic panels.

2.3 Operator error.

2.4 Spurious spiking of instruments.

f 2.5 Manual initiation.

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2-EP-5 Page 3 of 6 05-22-80 3.0 Immediate Operator Actions 3.1 Verify completion of 2-EP-1 Immediate Actions.

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 emergency diesel generators 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.

3.2.5 Verify high head and low head safety idjection pumps are I

running and cold leg injection flow is indicated on FI-2961, 2962 and 2963.

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2-EP-5 Page 4 of 6 05-22-80 Initials 4.0 Long Term Operator Actions 4.1 Define the cause of the safety injection.

CAUSE NOTE: If the cause cannot be immediately verified, request the SRO/STA to re-evaluate the incident.

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 <

2730 kw and actual pressurizer level is greater than 10%. Equipment which may be secured to meet this require-ment 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 4.2 Verify 9A isolation by initiating Attachment 3.

4.3 Commence 2-EP-1 Long Term Action.

NOTE: If the reactor coolant system pressure decreases in an uncontrolled manner to <1435 psig, secure all reactor coolant pumps. Request SRO/STA to re-evaluate the incident.

NOTE: If the reactor coolant pumps have been tripped, initiate Attachment 2 to verify natural circulation.

4.4 Safety Injection may be terminated if all of the following criteria satis #ied.

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1. Containment pressure, containment radiation, containment Yes No recirculation sump levels donot exhibit abnormally high or increasing readings.

2. Reactor coolant pressure is > 2000 psig and increasing.

Yes No

3. Pressurizer water level is > 50% span.

Yes No

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2-EP-5 Page 5 of 6 03-13-80 Initials 4.0 Long Term Operator Actions (cont.)

3. All operable steam generator levels recovering with Yes No indicated auxiliary feedwater flow.

4. All Th and Tc are at least 50*F below the saturation Yes No temperature for the existing RCS pressure.

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

Yec No NOTE: If all of the listed criteria cannot be satisfied, request the SRO/STA to re-evaluate the incident. 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.

NOTE: If reactor coolant pressure drops below the low pressu-rizer pressure setpoint for safety injection or pressu-rizer level drops below 20% of span following termination of safety injection or the reactor coolant Th increases to > normal full power Th, manually re-initiate safety injection and request that the SR0/STA re-evaluate the incident.

4.4.1 Secure safety injection and establish normal charging and letdown as per Attachment 1.

4.5 Verify with the system operator that the Vepco power system is stable, then return the station service normal and emergency electrical systems to normal as per 2-AP-10; secure the emer-gency diesel generators as per 2-0P-6.

4.6 Return the boron injection tank concentration to normal as per 2-0P-7.2.

4.7 Secure service water pumps as necessary so that one pump / header is left running; line up service water headers as desired per 1-0P-49.1.

2-EP-5 Page 6 of 6 03-13-80 Ynitials 4.0 Long Term Operator Actions (cont.)

4.8 Return the containment isolation trip valves to normal.

NorE: Verify sufficient capacity in the high level liquid waste tanks prior to resetting containment sump pump discharge valves. If high activity is suspected in the containment sump, inform HP to sample cont. sump pump discharge.

4.9 Restart containment vacuum pumps as necessary.

. 2-CV-P-3A 2-CV-P-3B 4.10 Return the emergency borate system to normal as per 2-0P-8.8, if necessary.

4.11 Restore main control room and emergency switchgear room ventila-tion to normal as per 2-0P-21.5.

4.12 Secure emergency control room and switchgear room bottled air ,

supplies as per 2-0P-21.9, and recharge the air bottles to 2 2325 psig.

4.13. Refill the RWST to normal level as per .-0P-7.7.

4.14 Return the accumulators to normal as per 2-0P-7.3, if necessary.

4.15 Depress both "SI Recir- Mio1 Reset" pushbuttons (prevents inad-vertent LHSI swapover low RWST level).

NOTE: SI must be reset and reactor trip breakers must be reclosed within 30 hr after SI initiation, or the plant must be placed in cold shutdown (Required by T.S. 3.3.2.1, Table 3.3-3, Item 1.b.)

4.16 The Shift Supervisor will initiate a special report as per T.S.

3.5.2 or 3.5.3.

Completed By:

Date:

2-EP-5 Attachment #1 Page 1 of 2 03-13-80

' Initials

Securing Safety Injection

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

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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-2380 and MOV-2381 seal water return isolations.

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

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.

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

l 15. Shift charging pumps sucti.on 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.

2-EP-5 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 5IToutlet MOV-2867D BIT outlet

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

19. Control PCV-2145 in manual to maintain 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

• 50% pressurizer level 60 gpm orifice isolation valves 2200 B and/or 2200C may be equired to be open to maintain level.

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2-EP-5 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 recircu-lation, 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 AFV 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 circu-lation; 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 hr. of entry into natural circulation.

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l 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 N 33% level).

1.1 Verify steam generators operable by (J) check.

"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) aad TR-2410 l (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) = AT

• F - F = *F l

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j 2-EP-5 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 er 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-24'.3, verification shall be made from the posted saturation graph.

5.0 Pressurizer level shall be maintained in manual level 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 DS 24 E4 33 K5 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-lity typewriter is inoperable).

7.1 Press "Incore T/C Map" pushbutton 7.2 25 value 1

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2-EP-5 Attachment i/2 Page 3 of 4 05-22-80 Natural Circulation Verification (cont.)

Initials 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 inidication.

NCTE: The incore thermocouple maps should be run every

• 30 min for continued verification of cooldown.

S.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:

2-EP-5 Attachment #2 Page 4 of 4 05-22-80 Natural Circulation Verification (cont.)

Initials 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 depress 2rization cannot be accomplished by steam relief from the steam generators.

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

10.3 If no means for RCS deprer,surization 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.

2-EP-5 Attachment 3 Page 1 of 8 03-22-80 Initials VERIFICATION OF $A AND/OR $B CONTAIVMENT ISOLATION 30M SI AND/OR CDA

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

(/) OPEN (RED)

MOV-2867A BIT inlet MOV-2867C BIT outlet MOV-SW-200A SW to Spray header MOV-SW-200B SW to Spray header .

(/) CLOSED (GREEN)

TV-2884A BIT recire.

TV-2884C BIT recire.

MOV-2380 Seal water return

(/) (/) (d) (J) (J) (J) (4) (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-5 I

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

I Initials i 1.0 SI ($A) Verification (cont.)

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

(J) OPEN (RED)

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

(/) CLOSED (GREEN)

TV-2884B BIT recire.

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

BD CV DA LM LM RM SI SS SS SS 2008 250B 2008 200D 201B&D 200C 200B 200B 203 2123 BD CV DG LM VG RM MS SS SS IA 200D 250D 200B 200F 200B 200D 209 201B 204B 201B BD SI LM LM MS TV TV SS SS IA 200F 2936 200B 200H 210 2204 2842 202B 206B 202B SV 203 _

i 2-EP-5 Attachment 3 Page 3 of 8 05-22-80 Initials 1.0 SI ($A) Verification (cont.)

j 1.3 Verify Automatic Valve Operation on "Benchboard".

4 (/) OPEN (RED)

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

(/) CLOSED (GREEN)

MOV-2115C VCT to Chg. pumps l

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 (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".

1 (J) CLOSED (GREEN)

MOV- 2275A 2 ~H-P-1A Recire.

MOV-2275B 2-C1'-P-1B Recire.

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

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2-EP-5 Attachment 3 Page 4 of 8 03-13-80 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.

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2-EP-5 Attachment 3 Page 5 of 8 Xnitials 03-13-80 2.0 CDA (9B) V'erification (This section is to be completed only if required) 2.1 Verify the following Automatic Operations on "H" Safeguards Panel.

(J) CLOSED (GREEN)

(J) (J) (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 (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 HX ' return MOV-SW-201A RS EX ueader supply MOV-SW-201C RS HX header supply MOV-SW-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 af ter 3 k min. T.D. (Verify rotation by blue light lit) 2-RS-P-2A Outside recire. spray pump starts af ter 3 \

min. T.D.

2-EP-5 Attachment 3 Page 6 of 8 Initials 03-13-80 2.0 CDA (08) Verification (cont.)

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

(/) CLOSED (GREEN)

(/) (/) (/) (/)

CC CC CC CC 200A 202B 204A 201B CC CC CC CC 2008 202D 204B 203B CC CC CC 200C 202F 204C MOV-SW-210B Air recir'c. cooler MOV-SW-214B Air recirc. cooler MOV-SW-208B Component cooling

(/) OPEN (RED)

MOV-SW-203B RS EX A supply MOV-SW-203C RS HX D supply MOV-SW-204B RS HX A return MOV-SW-204C RS EX D return MOV-SW-201B RS EX header supply MOV-SW-201D RS EX header supply MOV-SW-2053 RS EX 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-2553 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.

2-EP-5 Attachment 3 Page 7 of 8

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Initials 2.0 CDA (08) Verification (cont.)

2.3 Verify the following Automatic Operations on the bottled air /

casing cooling panel.

(/)

2-RS-P-SA 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 "OV-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-228 Sfgd. Bldg.

2-EP-5 Attachment 3 Page 8 of 8 Initials 05-22-80 2.0 CDA ($B) Verification (cont.)

2.4.2 "J" Bus Powered Section

(/) 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.

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

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

2-SW-P-5 for RS EX 2-RS-E-1A 2-SW-P-6 for RS EX 2-RS-E-1B i

l 2-SW-P-7 for RS EX 2-RS-E-1C l

2-SW-P-8 for RS EX 2-RS-E-1D 2.6 On the Main Control Board verify that the component .ooling water pumps trip (J).

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

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