ML20126D130

Draft Emergency Operating Instructions EOI-O, Immediate Actions & Diagnostics

ML20126D130
Person / Time
Site:	Sequoyah
Issue date:	01/31/1980
From:	Record D, Jacqwan Walker TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20126D128	List: ML20126D126 ML20126D130 ML20126D134 ML20126D138 ML20126D142
References
EOI, EOI-0, NUDOCS 8004170227
Download: ML20126D130 (13)

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DISTRILUTION 1C Plant r! aster File E:CRGENCY OPEEATING I:!STRUCTIC:!

Superintendent 1U Assistant Superintendent (Oper.)

E01-0 1U Aas'istant Superintendent (Maint.)

Administ.,tive E': ervisor T EEDIATE ACTICNS AbD DIAGNOST!'

Maintenn' c i :' > r (")

Assistant Mainten,nce Supervisor (M)

Maintenance Supervise r (E)

Units 1&2 Assistant Maintenance Supervisor (E)

Maintenance Supervisor (I)

Results Supervisor IC Operations Supervisor Quality Assurance Supervisor Health Physics Public Safety Services Supv.

Chief Storcheeper Preop Test Program Coordinator Cutage Director Chemical Engineer (Results)

Radiochem Laboratory Instrument Shop neactor Engineer (Results)

Instrument Engineer (Maint. (I))

Mechanical Engineer (Results)

Staff Industrial Engineer (Pl. Sys.)

_lC Training Center Coordinator PSO - Chickamauga Engrg Unit - E!!P Pr: pared Ey:

J. E. k'Clher Public Safety Services - S?iP IQ Shift Engineer's Office Revised By:

N/A 1c Unit Control Room

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QA&A Rep. - SNP Submitted By: /d j M / ' M & //

Health Physics Laboratory Suppfvisor

_11'_._ Ass t Dir NUC PR (Oper), 727 ES-C 3/3l/90 Nuclear Document Centrol Unit, 6C6 EE-C 1U PORC Review:

1p Superintendent, k'BNP Date Superintendent, BFNP Superintendent, BENP TU NEB,' W9 C 174 C-K Approved By S ut

.A-JQ_LJ_i t Q Supv., NPHPS ROB, MS

~ Super endent JU NEC-IE:II Power Security Officer, 620 CST 2-C mk

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Date Approved:

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Nuclear Ma terials Coordina tor-1410 CUBS-Manager. OP-QA&A Staff I

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ic Resident NRC Inspector - S:iP ic I;SRS, 249A HEE-K 1c Technical Support Center Rev No.

Date Revised Pages Rev. No.

Date Revised Panec 0

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The last page of this instruction is Number 12 8004170 D2Qi

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This instruction presents the autematic actienc, the in.cdinte 0;crator a:tions and the dincncatic.cequence which in te te f011 cued in the i.lentificaticn of the fol-lovint,:

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A.

Spurious Actuation of Safety Injection l

B.

Loss of Reactor Coolant i

C.

Loss of Secondary Coolant l

D.

Steam Gener2 tor Tube Pupttre 1

l The reactor cutcmatic protection equipment is desi ned to safely shut down the 6

reactor in the event of any of the above emergencies. The safety injection cyctem ic i

designed to provide emergency core ecoling and boration to maintain the safe reactor j

shutdown condition. These plant safeguards systems operate with offsite electrical l

power or from oncite emergency diesel-electric pcVer should offcite pever not be i

available.

!n the cubsequent docu.ents in this ceries (EDI-1, 2 and 3), instructions for recovery from the event are presented for each particular accident.

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CTE: The process variablec referred to in this instructica are typically m:nitored by more than cne instrumentatien channel.

The red = dant channels chould be cheched for concirtency while performing the steps of thic instructicn.

A.

The fcileving cympten; are typical of thocc which may crice 1:. a plant which is undergoing a 1ccc of reactor coolant, loss of secondary cociant cr i

cteam generatcr tube rupture (cne or more symptoms mcy appear in any l

' order):

1.

Lev Preccuri::cr Prc::ure 2.

Low Pressuriner Water Level 3

High Pressuriner Water Level h.

High Containment Precsure 5

High Containment Radiation 6.

High Air Ejector Radiation i

7 High Steam Generator Blovdcun Radiation l

S.

Steam Flev/Feedvater Flov "dematch l

9 Letdevn Isolatien/ Pressurizer Heater Cutout 10.

Lov Lov Reacter Coolant System Averace Coolant Temperature 11.

High Containment Eecirculation Sump Water Level 2

12.

Irv Steamline Pressure (one or all Steamlines) 13 Lnv St en Generator Water Level lb.

Increasing Stet,s Generator Water Level 15 Rapidly Changing Beactor Coolant System Average Coolant Temperature 1

4 16.

Increaced Charging Flev

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17 High Steam Flov (one or all Steam lines) i 18.

High Containment Humidity i

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SYMPTOMS (continued) 19.

High Containment Temperature 20.

Low Feedwater Pump Discharge Pressure NOTE: The pressuriner water level indication should always be used in conjunction with other reactor coolant system indications to i

evaluate system conditions and to initiate manual operator actions.

II. IMMEDIATE ACTIONS A.

Conditions warranting reactor trip or safety injection may be characterized by a number of ancmalous situations or unusual instrument indications.

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1.

If the pltnt is in a condition for which a reactor trip is warranted and an automatic reactor trip has not yet occurred, manually trip the i

reactor.

Continue monitoring plant conditions as shown in Figure 1.

CAUTION: If there is not a rapid drop in nuclear power and the control rods are not inserted, then this is an ATWS event. Attempt to trip the reactor by other means, (see E0I-14 as needed).

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2.

If the plant is in a condition for which safety injection is warranted and an automatic safety injection has not yet occurred, manually initiate safety injection.

B.

Verify the following actions and system status:

1.

Reactor trip and turbine trip have occurred, a.

All rods inserted b.

Turbine steam stop valves closed 2.

Bus voltages indicate that the busses are energized and all intended loads are being powered.

Generator be' akers open (time delay of 30 seconds if no electrical a.

e fault) b.

Station cervice transferred 3.

Feedwater Isolation has occurred a.

F.W. Isolation valves closed b.

Main F.W. reg. valves closed c.

Main F.W. reg. bypass valves closed.

a SQNP E0I Units 1 and 2 Page 3 of 9 c,.'

Rev. 0 v.

II. IMMEDIATE ACTIONS (continued) i j

4.

Containment Isolation Phase A, containment ventilation isolation and safety injection have occurred and valves and dampers are in proper position:

j NOTE: Test all status monitor lights prior to relying on position j

indication.

1 a.

Safety injection and Phase A:

Panel 6C - Dark Panel 6D - Dark Panel 6E - Light (except for outlined)

Panel 6F - Light (except for outlined)

Panel 6G - Dark Panel 6H - Dark 5.

Auxiliary Feedwater Pumps have started and the Auxiliary Feeduater System valves are in their proper Emergency Alignment and are open or closed as appropriate for present S/G level.

6.

Safety Injection Pumps have started:

a.

Centrifugal charging pumps (hi head SI) t b.

Safety injection pumps (lo head SI) c.

RHR pumps (lo head SI)

AND Verify flow through the BIT, and as pressure falls, verify SI pumps and RHR pumps deliver flow.

7.

ERCW and Component Cooling Water Pumps have started.

8.

Emergency Diesel Generators have started.

9.

Emergency Gas Treatment and Auxiliary Building gas treatment systems have started.

C.

If any of the above automatic actions have not occurred and are required, they should be manually initiated.

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<v the reactor ecolant system when the Resctor Co:lant System Ire: Cura i; belev the high head safety injection pr.; thutcff head.

If net, j

attempt to operate equipment manually cr locally.

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?!OE : Only after steam generator water level is establi hed c.bcVe the tcp of the U-Tubes, should the kaxiliary Feedvater Eystem i

Flev be rest. lated to n.intain reequired level.

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3.

Verify ths; heat is being removed from the reactor plant via the steam u,,..,.1

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Autenatic steam du~.p to the Ocndenser is ccourring; b.

Reacter coolant average temperature is decreasing tcvards progra*.ned no-load temperature.

?!CTE: If cendenser ster.m dump has been bicched due to a c:ntrol malfunction or loss of the " Condenser Available" co,ndition, decay heat remocal vill be effected by automatic actuation of the steam generator power-cperated relief valves, cr, if the e pr;ve ineffective, the steam generator ccds sr.fet'/

a'/cs;.

In this event, steam pressure vill be maintained E.t the set pressure of the centrolling valve (s) r.nd rer.ctor coolant average temperature vill stabili::e at approximately the saturation temperature for the steam pressure being maintained.

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D.

If running, stop containment building " auxiliary" flocr and equipment drain pumps (controls en M-9) and verify containment floor and equipment drain pu ps stcpped (controls en M-15).

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I!CIEDI ATE ACTIONS (Continued)

E.

Whenever the containment hi-hi pressure setpoint (2,81 psig) is reached, verify the following:

1.

Main Steam isolation valves have closed 2.

Containment spray is initiated 3.

Containment isolation phase B is initiated NOTE: Test all status monitor lights prior to relying on position ind a.

Panel 6C - Dark Panel 6D - Dark Panel 6E - Light i

Panel 6F - Light Panel 6G - Dark Panel 6H - Dark If main steam isolation valves have not closed, manually close from the control board.

If containment spray or phase B isolation have not occurred, manually initiate.

III. ACCIDENT DIAGNOSTICS (Pefer to rigure'2) 1 A.

Evaluate reactor coolant pressure to determine if it is low or decreasing in an uncontrolled manner.

If it is low or decreasing, verify that:

1.

All pressurizer spray line valves are closed and 2.

All pressurizer relief valves are closed If not, manually close the valves from the control board.

If the RCS pressure is above the low pressure reactor trip setpoint and i

is stable or increasing, go to step G.

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Sto.o AlL Reacter Coolant Pum.ns after the hich head sa.rety in4ecticn unc u

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operation has been verified and when the vide range reacter ecclant precsure decreases to 1550 psig.

CAUTION: If cer;cnent eccling water to the reactor ecclant pumps is isciated en a ecntainment Fhase 3 isclatien,all reacter ecclant pumps should be stopped within 5 minutes because of icss of

=ctor bearing cooling.

CAL' TION. If the reactor coolant pumps are stopped, the seal injection ficv should be maintained.

NOTE: The cenditions given above for stopping reacter ecolant pu=pc should be continucusly menitered throughout this instructien.

C.

IF the condenser air ejector radiation er steam generatcr blevicvn radia-tien moniter exhibit abner:211y high readings, AND containment pressure, containment radiation and centainment recirculatien surp level exhibit normal readings, THEN go to E0I-3, " Steam Generator Tute Rupture. "

D.

IE the Otcatline pretoure ic cbnormally lover in ene aten gener;tcr than in the etha" generators, TEEC go to I !-2, " Loss of seccndary

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Coclant."

E.

_IP containment pressure, OR containment radiation OR containment recircula-tien sump levels exhibit either abncr ally high readings or increasing readings, THEN to to E0I-1, " Loss of Reactor Coolant".

NCTE: For very small breakc inside the centainment building, the contain-cent pressure increase vill be very small and pessibly not recogni-cable. For very small breaks the centainment recirculation cu=p water level vill increase very s1culy and early in the transient may not indicate a level increase.

7 TZ the certainment preccure, centainr.ent radiaticn.tMD centainment recirculaticn samp water level centinue to exhibit stable readings in the normal pre-event range, THEN go to EDI-2, "Less of Secendary Coolant".

G.

In the event of a spurious safety injection signal, the sequence of reactor trip, turbine trip and safeguards actuation vill occur.

The operator must assume that the safety injection signal is non-spurious unless the following are exhibitied:

1.

Normal readings for containment temperature, pressure, radiation and recirculhtion sudp level AND l

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III. ACCIDENT DIAGNOSTICS (continued) 2.

Normal readings for auxiliary building radiation and ventilation monitoring AND 3.

Normal readings for steam generator blowdown and condenser air ejector radiation IF all of the symptoms 1 through 3 above are met and when the following 4 through 7 are exhibited:

4.

Reactor coolant pressure is greater than 2000 psig and increasing AND 5.

Pressuriner c graa:med no lead water level c

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6.

The reactor coolant indicated subcooling is greater than 40 F.

AND 7.

Water level in at least one S/G is stable and increasing as verified by auxiliary feedwater flow to that S/G. Auxiliary feedwater flow to the unaffected S/G's should not be reduced below 400 GPM until indicated level is returned to within the narrow range level instru-ment.

NOTE: Pressurizer water level should trend with reactor > coolant system temperature.

If the pressurizer water level is low enough to prohibit pressurizer heater operation, re-establish water level by operating the charging system. Energize the heaters.

TIEN 8.

Reset safety injection and stop safety injection pumps t ot r. ceded for j

normal charging and RCP seal injection flow.

CAUTION:

Automatic reiniitiation of safety injection will not occur since the reactor trip breakers are not reset.

CAUTION.

Subreq"ent t: this step, chculd loss of offsite power e :ur, manual action (e.g., manual safety injection initiation) will be required to load the safeguards equipment onto the diesel powered emergency busses.

9.

Place all safety injection pumps not needed to provide normal changing flow in standby mode and maintain operable safety injection flowpaths...

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4 SQNP E0I Units 1 and 2 Page 8 of 9 Rev. 0 III. ACCIDENT DIAGNOSTICS (continued) 10.

Isolate safety injection flow to RCS Cold Legs via Boron Injection Tank and estabiish normal charging flow.

Close seal injection water flow control valve FCV-62-89.

a.

b.

Open the charging pump suction valves from the VCT FCV-62-132 and 133 c.

Close the charging pump suction valves from the RWST FCV-62-135 and

136, d.

Open the centrifugal charging pumps miniflow isolation valves FCV 98 and 99.

e.

Close the BIT inlet isolation valves FCV-62-39 and 40 and outlet isolation valves FCV-62-25 and 26.

f.

Open the charging line iscaltion valves FCV-62-90 and 91.

g.

Open seal vater heat exchanges inlet isolation valves FCV-62-61 and 63.

h.

Gradu lly open the seal injection water flow control valve FCV 89. Adjust the seal water flow to S GPM per RCP.

11.

Reestablish normal makeup and letdown (if letdown is unaffected) to main-tain pressurizer water level in the normal operating range and to maintain reactor coolant pressure at values reached when safety injection is terminated. Ensure that water addition during this process does not result in dilution of the reactor coolant system boron concentration.

a.

Open the letdown line isolation valve FCV-62-77 b.

Open FCV-62-81 2 25% on hand and immediately open FCV-62-73 (45 GPM orifice isolation valve). Immediately adjust FCV-62-81 fer desired letdown pressure setting, then place pressure control on auto.

(Normal pressure is 2 320 PSIG @ normal letdown temp.)

NOTE: After charging and letdown have been established, additional letdown may be increased as condition permit.

12.

Reestablish operation of the pressurizer heaters. When reactor coolant pressure can be. controlled by pressurizer heaters alone, return makeup and letdown to pressurizer water level control only.

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Rev. O III. ACCIDENT DIAGNOSTICS (Continued)

NOTE:

If af ter securing safety injection and attempting to transfer to normal pressurizer pressure and level control, reactor coolant pressure drops below the low pressurizer pressure setpoint for safety injection actuation (1870 psig) OR if pressurizer water level drogs below 10% of span, OR the reactor coulant sub-cooling drops below 40 F, THEN SAFETY INJECTION MUST BE MANUALLY REINITIATED Rediagnose plant conditions and proceed to the appropriate emergency instruction.

CAUTION:

Stopping and starting of the high head safety injection pumps and low head safety injection pumps can cause pump motor overheating or reduced motor life.

Hence if the pumps are restarted once after termination, an additional 15 F of sub-cooling should be added to the requires sub-cooling prior to the second termination of the high head pumps.

NOTE:

IF after security safety injection and transferring the plant to normal pressurizer pressure and level control, the reactor coolant pressure does not drop below the low pressurizer pressure setpoint for safety injection actuation (1870 psig) AND the pressurizer water level remains above 10% span, AND the reactor coolant indicated subcooling is greater than 40 F, Tl[EN go to AOI-19 for recovery from inadvertent gafety in-jection.

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