ML19220C679

Forwards Metropolitan Edison W/Emergency Shutdown Procedures & Preliminary Sequence of TMI-2 Accident Events

ML19220C679
Person / Time
Site:	Crane
Issue date:	04/28/1979
From:	Mccreless T Advisory Committee on Reactor Safeguards
To:	Etherinton H, Okrent D, Plesset M Advisory Committee on Reactor Safeguards
Shared Package
ML19220C680	List: ML19220C679
References
ACRS-SM-0099, ACRS-SM-99, NUDOCS 7905140023
Download: ML19220C679 (1)

Text

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NUCLEAR REGULATORY COMMISSION c-ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 7O g,, w- [y A

WASHINGTON. D. C. 205o5 April 28, 1979 Mr. Etherington Dr. Siess Dr. Okrent Dr. Park Dr. Plesset Dr. Catton Dr. Carbon Dr. Lipinski Dr. Kerr Mr. Michelson

SUBJECT:

INFDFF.ATION PRCVIDED BY GPU ON T4I-2 SH'JTDCSN PROCEDUREE AfD CN SEQUENCE OF EVFSTS OF B4I-2 ACCIDENT Attached is a copy of Metropolitan Edison Company's shutdown procedures and of GPU's preliminary sequence of events associated with the first 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of the 241-2 accident.

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w Thomas G. McCroless, Chief Project Review Branch No. 2

Attachment:

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'490514002 3 yn-s ?$

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DfI Recovery Team GPU Service Corporate

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260 Cherry Hdi Road

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Parsippar1y New Jersey 07o54 201 263-4900 TELEX 136-482 I

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April 24,1979

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Mr. T. McCreariess ACRS Washington, D.C.

Dear fir. McCrearless:

Per your request to the Metropolitan Edison Company Safety &

Licensing Group, attached are the following:

Three Mile Island Unit #2 Emergency Procedure 2202-1.1 (Revision 6 10/25/78)

Reactor Trip Emergency Procedure 2202-1.3 (Revision 11 10/06/78)

Loss of Reactor Coolant / Reactor Coolant System Pressure Emergency Procedure 2202-2.1 (Revision 7 6/21/78)

Station Blackout Preliminary Sequence of Events Report e

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) (!A R. C. ARN LD General Operations Manager GPU RCA: bas Attachment

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\\ _0gI; 79 051400 Af GPU Servce Corporaton s a sutsciary of Gerwal Pubic Utdrnes Corporaton

2202-1.1 Revision 6 10/25/78

' CON ROLLF) COPY THREE MILE ISLAND NUCLEAR STATION y A Qwl C )\\

f.,^. y UNIT #2 EMERGENCY PROCEDURE 2202-1.1 rr VinV L ' L' l I

REACTOR TRIP JO NO-~ REMOVE

^

resie of er<ective e.se, Pa:e Date Revision Pace D 9 Revision Pace Date Rekision 1.0 10/06/78 5

26.0 51.0 2.0 06/12/78 4

27.0 52.0 3.0 10/25/78 6

28.0 53.0 4.0 29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0

/

Unit 1 Staff Recommends Approni Unit 2 Staff Recommends Approval M

A Approval Date Approval Date Ccgnizant Dept. Head Cognizant Dept. Head o

Unit 1 PORC Recommends Approval Unit 2 PORC R _ommends Approval Date S A l 6MJM -

Date /0 S 2 Chairman of.PO RC V Chairrnan of PORC Unit 1 Superintenc t Approval Unit 2 Superintendent App eval k9 Date Date /0 b S U'

()

'/

/

neger Generation Cuality Anurance Approval

[

Date

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.- um 99

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2202-1.1

't kbbfl8 THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-1.1 REACTOR TRIP 1.0 SYMPTOMS 1.1 Reactor trip may be due to any of the following:

a.

Nuclear power > 105.5% of rated power.

b.

Nuclear power > 1.05 times reactor coolant flow (%) minus power imbalance reduction, c.

Nuclear Power > 50.9% of rated power during operation with one R.C. Pump operating per loop.

d.

Loss of two Reactor Coolant Pumps in one reactor coolant loop.

Reactor coolant pressure > 2355 psig.

e.

f.

Reactor coolant pressure < 1900 psig.

g.

Reactor coelant pressure < (13.00 T

-5887) out h.

Reactor coolant outlet temperature > 619 F.

i.

Reactor building pressure > 4 psig.

j.

Manual reactor, trip actuation.

1.2 Individual and group "In Limit" lights actuate.

1.3 Rapid decrease in neutron level as indicated by the Nuclear Instrumentation.

9 1.4 Main turbine master trip alarm energized.

1.5 Rapid decrease in Unit Load.

2.0 _IMMEDIATE ACTION F

1.0

2202-1.1 Revision 4 06/12/78 2.1 Automatic Action All rods insert (except Group 8) a.

b.

Turbine trip, s"np valves close cf.

Generator break?rs open d~.

Turbine by-pass valves open Source range nuclear instrumentation high voltage energizes e.

0 at 5 X 10 amps on N1-3 or N1-4.

2.2 Manual Action a.

Manually TRIP the reactor b.

Verify all "in-limit" lights are actuated (except group 8) c.

Verify that tJrbine has tripped and generator breakers are open - if turbine has NOT tripped - manually TRIP the turbine, start lift pumps & turning gear oil pump.

d.

CLOSE letdown isolation v-tve MU-V376.

e.

START second make-up pump.

Open MU-V-16B as necessary to maintain 100" in PZR.

f.

Verify turbine bypass control valves are maintaining header pressure at 1010 psig.

g.

If any feedwater stations are in hand, run stations back to maintain OTSG at 30".

h.

Verify PZR Htrs are off @ 80" in PZR.

i.

'If PZR level gets to 20" open DH-V5B and start 3rd make-up s

pump and open MU-V16C/D to increase PZR level.

3,.

I.f any of the following ICS stations are in Hand (Steam

_~

Generator / Reactor Demand, either Feedwater Demand, Main or Startup Feedwater Valve Demand, Feedpump Speed, Reactor Master, and/or Diamond) runback the appropriate ICS stations.

99 190

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2202-1.1 Revision 6

,/

10/25/78 3.0 FOLLOW-UP ACTION 3.1 Announce-on page system - Reactor Trip 3.2[Initiateemergencyborationper 2203-1.1 (Loss of Boron)

[if reactor power is not below 10% in 1 minute.

(

3.3 Monitor make-up tank level and maintain level greater than 55" by using Waste Transfer Pumps (WOL-P5A/B) and feeding from an RCBT with boron concentration greater or equal to RCS concen ~

tration.

3.4 Verify that the pressurizer heaters and spray have returned RCS pressure to normal operating pressure of 2155 psig.

3.5 Reduce pressurizer level setpoint to 100" (25%).

3.6 Verify normal electrical lineup, i.e., no substation or in-plant distribution breakers are open (except generator breakers).

3.7 Check that all RMS channels are normal and that no unplanned or uncontrolled radioactive release is in progress.

3.8 Compute shutdown inargin calculations per 2103-1.9 (Reactivity Balance Calculations).

If shutdown margin is less than 1%,

r boron should be added to the RCS.

3.9 If reactor start-up is not intended within four hours raise OTSG 1evel to 97-99% on the operating range using the feedwater valve bypass and tube sheet drains for level control.

3.10 Fill out a Reactor Trip report.

q 3.11 Notify H.P./ Chemistry to sample R.C. Letdown for Dose Equivalent

• Iodine between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after power change of greater than i

'_-15% within one hour period per Surveillance Procedure #2304-3D2.

99 k9

3. 0

24U4-1.J Revision 11 4'-

10/06/78

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THREE MILE ISLAND NUCLEAR STATION MASTER COPY

..unn a estactriCY eR0ce0uar 2202-1.3 O NO-- 1Rr n -LCSSlQF REACTOR COOLANT / REAC dguvc i

Page Date

. Revision Pace Date Revision Pace Date R Evision 1.0 06/22/77 7

2.0 05/12/78 8

3.0 12/30/77 3

4.0 12/30/77 3

5.0 06/22/77 1

6.0 03/01/78 5

7.0 09/29/78 10 8.0 05/12/78 8

9.0 06/20/78 9

10.0 05/12/78 8

10.1 05/12/78 8

10.2 05/12/78 8

11.0 06/22/77 1

12.0 06/22/77 1

13.0 04/18/78 7

14.0 10/06/78 11 15,0 04/18/78 7

16.0 12/30/77 3

17.0 06/22/77 1

18.0 04/18/78 7

19.0 12/30/77 3

20 0 12/30/77 3

21.

12/30/77 3

22.0 12/30/77 3

23.0 06/22/77 1

/

s Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Approval Date Approval d

Date Cognizant Dept. Head Cognizant Dept. Head a

Unit 1 PORC Hecon, mends Approval Unit 2 PORC Recommends Approval e oft bg_

Date 50 GW Date Chairrnan of P0RC V-Chairrnan of P0RC Unit 1 Superiatenderd Approval Unit 2 Superintendent Approval k

Date

{ f n.fr f Date /0 W

~ } t's r

j Manager Generat on Quality Assurance Approval 88 Date i

99 I92 m,,

2202-1.3

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Revision 1 06/22/77 THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-1.3

.?

LOSS OF REACTOR COOLANT / REACTOR COOLANT SYSTEM PRESSURE 9

A.

Leak or Rupture Within Capability of System Operation.

1.0 SYMPT 0MS 1.1 Initial loss of reactor coolant pressure & decrease in pressurizer level becoming stable after short period of time.

1.2 Possible reactor building high radiation and/or temp. alarm.

1.3 Possible reactor building sump high level alarm.

1.4 Make-up tank level decreasing > 1" in 3 min.

1.5 Possible makeup line high flow alarm.

1.6 RB Fan Drip Pan Level Hi Alarms.

NOTE:

The operator may distinguish between a loss of coolant inside containment, an OTSG tube rupture and a steam line break by the fol'owing symptoms which are unique to the aforementioned accidents.

/

1.

Loss of coolant inside Rx Bldg. - particulate, iodine & gas monitor alarm on HP-R-227 " Reactor Building Air Sample".

2.

OTSG tube rupture - gas ronitor alana on VA-R-748.

3.

Steam line break (1)

Low condensate storage tank level alarm - and or lcw hot "s

well level alarm.

(2)

FW Latch System Actuation.

t 2.0 IMMEDIATE ACTION 2.1 Automatic Action:

1.0 99

\\93 7

2202-1.3 Revision 8 05/12/78 2.1.1 MU-V17 will open to compensate for reduced pressurizer level.

2.1.2 Additional pressurizer heaters will come on ir, respcase to I

reduced reactor coolant pre;sure.

2.2 Manual Action 2 2.1 Verify MU-V17 cpen and pressurizer heaters on.

2.2.2 "CLOSE" MU-V376 letdown isolation valve, & " START" the backup MU oump, if required.

2.2.3 Reduce load at 10% minute & proceed with normal shutdown.

2.2.4 "LINE-UP" waste transfer pump.from a R.C. Bleed Holdup Tank &

pump to the makeup tank to maintain required level.

2.2.5 If for ar.y reason the operator cannot maintain Make-up Tank and Pressurizer levels above their respec.ive low level alarm setooi_nts, " TRIP" the reactor, " INITIATE" Sa fety In,iection manually (push buttons on panel 3), & then "Close" MU-V12.

3.3 FOLLOW UP ACTION 3.1 Safety Injection Not Initiated.

3.1.1 Initiate unit shutdown & cooldown per 2102-3.1 and 2102-3.2 respectively.

3.2 Safety Injectica Manually Initiated (HPI and LPI).

3.2.1 Verify +nat the Makeup Pumps & Decay Heat Removal Pumps start satisfactorily.

3. 2.1.1 Close MU-V12 and MU-V18.

,i 3.2.2 Bypass the SAFETY INJECTICN by DEPRESSING the Group Reset Pushbuttons & " THROTTLE" MU-V16A/B/C/D as necessary to maintain '

t.

T 220" pressurizer level and not exceed 250 GPM/HPI flow leg.

3.2.3 If MU pump flow drcps below 95 GPM, trip excess MU pumps.

2.0 99 h

2202-1.3 Revision 3 12/30/77 NOTE:

HP1 String A flow is the sum of MU 23 FEl&2.

HPI String B flow is the sum of MU23 FE 3&4.

3.2.4

, Verify that Safety Injection equipment is in its ESF position fasshowninTableA-1.

3.2.5

- CAUTION:

Continued operation depends upon the capability to

~

maintain pr2ssurizer level and RCS pressure above the 1640 PSIG Safety Injection Actuation setpoint.

{

l.

If pressurizer level can be maintained above +ba low level alann point and the RCS pressure above the Safety Injection Actuation point, then proceed to step 3.2.6.

2.

If pressurizer level cannot be maintained above the low level alarm point and the RCS pressure above the Safety Injection Actuation point, thi a tne plant has suffered a major rupture and operation should continue according to Part B - Leak or Rupture of Significan6 Size Such that Engineered Safety Features Systems are Automatically Initiated. ~

3.2.6 With the pressurizer level and RCS pressure being maintained within allowable limits, initiate plant shutdown and coollown per 2102-3.1 and 2102-3.2, respectively.

NOTE:

The HPI System is being used for makeup control and valves MU-V16A/B/C/D will have to be throttled to maintain pressuri er level. As RCS pressure d

decreases, it may be possible to return to the normal makeup flowpath and secure HPI.

If MU pump flow drops below 95 GPM as a result of throttling, "Open" MU-V36 & 37 to provide MU pump recirculation path to MU Tank.

Monitor MU Tank level and open MU-V12 as required.

99 l9J 3.0

2202-1.3 Revision 3 12/30/77 3.2.7 At the time th? DH System is to be brought on line for normal cooling only one DH string should be used for decay heat

. removal (i.e. - recirculation from the RC System).

The other DH string should be maintained on standby for use in recirculating;

~ water from the RB sump to the RC system.

NOTE:

Trip Reactor Coolant Pumps before R.C. Pressure decreases below pump NPSH (See figure 1 of 210%-

3.1/3.2.

3.2.8 When the Borated Water Storage Tank level decreases to 12' as indicated on panel 8, Shift the MU/HP1 pump (s) suction from the BWST to the RB sump if RCS Pressure is greater than 200 psig as follows:

(assume DH string A(B) is being used for decay heat removal and DH string B(A) is being maintained on standby):

3.2.8.1 If not already done, " THROTTLE" HPI string (s) flow rate to at least 500 gpm each < 250 gpm per leg) using control valves MU-V16A/b/C/D (or MU-Vl? if flow has been returned to the normal makeup flow path).fFlow rate indication and valve control in control room on Panel 8 and 3, respectively.

3.2.8.2 "0 PEN" valve DH-V7B(Al in crossover line from LPI String B(A) to HPI string B(A) (suction of HPI pumps)..

" REPOSITION" HPI flow ecatrol valves riU-V16A/B/C/D (or MU-V17 if flow has been returned to the normal makeup flowpath).

HPI i

fl'ow would increase cecause of increased HPI pump suction

~

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pres sure.

3.2.8.3_- When the BWST level decreases to 7', verify automatic transfer to the RB sump is initiated.

Verify OPEN suction valve for string B(A), DH-V6B(A) from the RB sump.

99

}hb 4.0

2202-1.3 Revision 1 06/22/77 3.2.8.4 When the suction valve from the RB sump DH-V6 B(A),

is fully open, then "CLOSE" the ECCS suction valve, DH-V5B(A), from the BSWT (valve controls and position indication in control room),

The ECCS B(A) string is now in " piggy-Back" operation providing.

makeup to the RCS from the RB sump as required.

3,2.9 After R.C.S. pressure decreases to = 200 plig, throttle HPI discharge flow by throttling MU-V16A/B/C/D. O b erve thht LPI pumps now deliver water to RC5 via DH-V4A/B.

3.2.10 When MU-V16A/B/C/D (HPI flow valves) are closed, stop the Hi pressure injection pumps & close DH-V7A & 78 from ';e LPI pump discharge. Injection flow path is now as follows:

Spill coolant to RB sump, RB sump to LPI pumps, LPI pumps to RCS via Dl!-V4A/B.

3.2.11 Throttle DH-V128A & B as required to maintain 220" pressurizer level and max.

LPI pump flow of 3000-3300 gpm.

Wit.hin about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, establish a long-term cooling circulation code as described in 2104-1.3 and listed below.

Mode 1 Forced circulation using decay Heat drop line.

Mode 2 Gravity draining reactor coolant hot leg to the Reactor Building sump via the D.H. drop line.

\\

Mode 3 Hot leg injection using Pressurizer Auxiliary

+

Spray Line.

Mode 4 Reverse flow through the Decay Heat Drop line into "B" Reactor Coolant Loop Hot Leg.

3. 2.1 $.

Evaluate radiation levels initiate action for Site Emergency as outlined in the TMI radiation emergency plan.

5.0 99 197

...s..

.....m....

2202-1.3 Revision 5 03/01/78 3.2.13 F.eactor Building Isolation Initiated 1.

Refer to Section B, 3.0 & complete all steps.

B.

' LEAK OR RUPTURE Of SIGNIFICANT SIZE SUCH THAT ENGINEERED SAFETY FbTURESSYSTEMSAliEAUTOMATICALLYI"ITIATED.

1.0 SYMPTCMS 1.1 Rapid continuing decrease of reactor coolant pressure.

(1) Lo alarm 2055 psig.

(2)

Lo-Lo-alarm 1700 psig.

(3) Safety Injection actuation at 1640 psig.

1.2 Rapid continuing decrease of pressurizer level.

(1) Lo alann 200".

(2)

Lo-Lo alarm 80" (Interlock heater shutoff).

1.3 Hi radiation alarm in Reactor Building.

1.4 Reactor Building Ambient Temperature Alarm.

1.5 Hi Reactor Building Sump level.

1.6 Hi Reactor Building pressure (R.C.S or, main steam line rupture).

1.7 Rapidly decreasing make-up tank level.

1.8 Both core flood tanks levels & pressures are decreasing.

NOTE:

The operator may distinguish between a loss of coolant inside containment, an OTSG tube rupture and a steam line break by the following symptoms which are unique to the aforementioned accidents.

\\

1.

Loss of coolant inside Rx Bldg. - particulate, iodine gas monitor alarm on HP-R-227 " Reactor Building Air Sample."

2. _- 0TSG tube rupture - Gas monitor alarm on VA-R-748.

~u t

3.

Steam break inside Rx Bldg:

60 99 198

2202-1.5 Revision 10 09/29/78 (1)

Low condensate storage tank level alarm - and or low hot well level alarm.

(2)

FW Latch System Actuation.

2.0 IMME6IATE ACTION 2.1 Autoinatic Action.

([

2.1.1 Reactor trip 1900 psig.-

2.1.2 Turbine Trip.

2.1.3 Safety Injection initiated @ 1600 psig R.C.S pressure, or 4 psig Reactor Building pressure.

2.1.4 Both Core Flood Tank levels & pressures may decrease depending upon rupture size and R.C.S. pressure. (< 600 psig).

2.1.5 Reactor Building Isolation & Cooling initiated.

(R.B. Press.

> 4 psi ).

9 2.1.6 Reactor Building Spray if the Reactor Building pressure is greater than 30 psig.

2.2 Manual Action.

2.2.1 "CLOSE" MU-V12 and MU-V18.

2.2.2 Small Break LOCA Response 2.2.2.1 Within 2 minutes of the LOCA the CR0 dedicated to recognition of a small break LOCA must ccmplete the following:

a.

Verify that small break LOCA with single failure symptoms exist.

Symptoms: 1.

SFAS initiation and only one MUP started,

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or

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2.

SFAS initiation and loss of 2-1E or 2-2E t

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}99 7.0

w-...,

Revision 8 05/12/78 b.

DISPATCH designated LOCA Response Primary A.O. to OPEN MUP Discharge Cross-connect.

c.

PROCEED to MU-V16A & B or MU-V16C & D.

d.

Within 5 minutes of the LOCA +.he MVP discharge cross connect valve must be opened off its closed seat and one 9

of the MU-V16 valves on the side of the single failure must be opened 2 turns.

2.2.2.2 CR0 at MU-V16A & B or MU-V16C & D must ESTABLISH comunications with the Control Room.

2.2.2.3 Once in communication with the control room thc CR0 at HU-V16A

& B or C & D continue to open the valves to establish 125 gpm per leg; while the control room CR0 THROTTLES MU-V16C & D or A

& B to prevent pump runout.

NOTE:

If the LOCA was E.S. with loss of MUP all MU-V16 valves would initially be open.

The operator at the controls must in this case throttle all 4 MU-V16 valves to 125 gpm/ leg. Also in this case the CR0 dedicated to Small Break LOCA would not need to go to the MU-V16 valves.

He should go to the MUP discharge cross connect valves and assist the A.0.

to speed up the opening of the MUP discharge cross a

cor nect.

SMALL BREAK LOCA ACTION TIMES EVENT TIME From Occurance Recognition -

1 2 minutes J

CR0 to MU-16's 1 4.5 mir.utes 8-99 200 v-

ave-,.

Revision 9

~

SMALL BREAK LOCA ACTION TIMES (Cont'd)

~

TIME From Occuran/20/78 06 EVENT ce A0 to MVP Discharge X-Connects 1 3.5 minutes Communications Established With 1 5.0 minutes CR0 at MU-V16's One of.[the Single Failure Side 1 5.0 ninutes MU-V161s Open 2 turns Discharge X-Connect 0FF Closed Seat 1 5.0 i.inutes Discharge X-Connect Open i 10.0 minutes MU-V16's Throttled to 125 gpm/ leg 1 10.0 minutes 2.2.3 Verify Hi pressure injection is operating properly as evidenced by injection flow in all four legs.

(MU-V16A/B/C/D).

Flow indicated on MU23 FEl,2,3,4.

2.2.4

" TRIP" reactor coolant pumps before reaching 1200 psig.

2.2.5 Verify Reactor Building Cooling and Isolation is operating properly.

3.0 FOLLOW UP ACTION 3.1 Verify that all E.S.F. equipment is in its ESF position, by observing that all eo"ipment status lights indicate as shown in Table B-1.

3.1.1 Check locked valve status back and verify closed or close the following manual containment isolation valves MU-V330, MU-V364, UF-Vil4A, CFV1145, CF-V145. CF-V146, DH-V187, and DW-V28.

NOTE:

Should any component not operate properly, attempt to actuate it at its rer.ote switch in the Control Room.

If it still does not operate, & the component has a local control station attempt to operate the component locally.

\\

3.2 Notify Shift Forer.an, who notifies all Station personnel over the cYoss-tied P/ sstem that a site emergency has occured.

3.3 0_to 2b or 3r minr'.es past LOCA until sump recircualtion is initiated':

Control Room operator continuously monitors the following:

n 9.0 yL

2202-1.3 Revision 8 05/12/78 3.3.1 Liquid levels in the:

1.

Borated Water Storage Tank, DH-T1, (DH-3-LI 1/2).

, 2.

Sodiura Hydroxide Tank, DH-T2, (DH-7-LI).

3.3.2 f Safety Features flow rate in each of the following:

~ 1.

Two Low Pressure (Decay Heat) Injection lines, DH-1-FI 1 and 2.

2.

Four High Pressure (Makeup) Injection lines, MU-23-FI 1, 2, 3, and 4.

3.

Two Rector Building Spray injection lines, BS-1-FI and 2.

4.

Four of five reactor building emergency cooling river water lines AH-FI-5620, 5621, 5522, 5623, or 5624 respectively.

3.3.3 Reactor Building environmental indications:

1.

Temperature, recorder on Panel 25.

2.

Pressure, recorder on Panel 3.

3.4 " DEFEAT" any two channels of Reactor Building Isolation and Cooling, then bypass all three Safety Injection Channels.

CAUTION:

If normal power is lost while operating in the injection Mode from the BWST, RB Isolation and Cooling must be manually initiated, when either the BUS 2-lE or 2-2E Undervoltage alarm is received to ensure proper diesel e

generator load sequencing.

3.5 " THROTTLE" as required to prevent pump runaut:

g 1.

Hi press. inj. flow (MU-16A/B/C/D) 0-250 GPM/ LEG.

+

t. CAUTION:

If MU pump flow drops below 95 GPri trip the excess r

MU pumps.

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99 L

10.0 T

2202-1.3 Revision 8 05/i2/78 2.

Lo Press. Inj. Flow (DH-V128A/B) 3000-3300 GPM/PMP.

3.

Building spray flow (BS-VIA/B) 1400-1700 GPM/PMP.

NOTE:

Hi flow alarms should actuate as a warning to throttle flows.

7 CAUTION: The actions to be taken for switching suction from the BW5T to the R.B. sump depend upon the number of operating ECCS injection strings and the delivered flowrates in these injection strings. Based upon the existing situation, in the ECCS,,sroceed as outlined below to perform switch over of suction to the RB sump:

Situation Go to Step 1.

Both LPI strings are operating and 3.6 indicated flow in each is above 750 gpm.

2.

Both LPI strings are operating 3.7 but indicated flow in each is below 750 gpm.

f 3.

One LPI string is inoperative.

3.8 NOTE:

The main objective when switching suction from the BWST to the RB sump is to maint4in ECCS flow through a

two flow paths.

3.6 Both LPI Strings are Operating and Indicated Flow in Each is Above

.g

't50 GPM.

i Wien the BWST ievel rea~ches approximately 12', initiate the

3. 6.1 -

l following steps:

99 203 10.1

2202-1.3 Revision 8 05/12/78 3.6.2 If not already done " THROTTLE" LPI strings flow rates back to 3000 GPM each using control valves DH-V128 A &B (flow rate indication and valve control in control room).

~

3. 6. 2.1:

If not already done, THROTTLE BS pump's flows back to 1600 gpm

~

pcr pump.

This must be done prior to taking suction from the RB sump.

3.6.3

" SHUT OFF" HPI pumps (pump control in control room).

3.6.4 Verify the ECCS suction valves DH-V6A & B from RB sump automatically open at BWST level of 7'.

3.6.5 When suction valves from RB sump are full open, "CLOSE the ECCS suction valves (DH-VSA & B) from the BWST.

3.6.6

" REPOSITION" LPI flow control valves (DH-V128 A&B) to obtain 3000 GPM each string if necessary.

(Flow rate could change due to change in suction sources).

3.6.7 Proceed to step 3.9.

3.7 Both LPI Strings Are Operating But Indicated Flow In Each Is Below 750 GPM.

3.7.1 When the BWST level reaches approximately 12', initiate the following steps.

3.7.2 If not already dene, " THROTTLE" HPI strings' flow rates back to 500 GPM per pump each using control valves MU-V16A, B, C, o

and D (flow rate indication and valve control in cor'.rol

. room).

a 3.7.2.1 If not already done, THROTTLE BS pump's flows back to 1600 GPM 4

{ per pump.

T;.is must be done prior to taking suction from the

~

RB sump.

99 204 10.2 1

2202-1.3

~

Revision 1 06/22/77 3.7.3 "0 PEN" valves DH-V7A and B in crossover line from LPI line to suction of HPI pumps (valve control and position indication in

- control room).

" Reposition" hPI flow control valves (MU-t V16A,B,C, & D) to obtain 500 GPM each string. (HPI flow would increasebecauseofincreasedHPIpumpsuctionpressure).

3.7.4 VERIFY the ECCS suction valves (DH-V6A & B) from RB sump automatically open at BWST level of 7'.

3.7.5 When suction valves from RB sump are fully open, "C hse" the ECCS suction valves (DH-VSA & B) from the BUST. The ECCS is now in " piggy-back" operation.

3.7.6 Proceed to step 3.9.

NOTE:

Once the flow in each LPI string exceeds 750 gpm, the HPI pumps can be " SHUT OFF" and valves DH-V7A &

B can be " CLOSED".

3.8 One LPI String is Inoperative 3.8.1 The BWST 7' automatic transfer to the RB sump is reached in approximately 55-80 minutes from initiation of ECCS injection, depending upon reas'on for string failure (i.e. - local LPI failure or diesel failure). Prior to actuation of the lo-lo level alarm, initiate the following steps.

3.8.2 Using the controls in the control room, attempt to " START UP"

+

the non-operati_ng LPI String.

If successful, proceed to step U

3.6.

If not successful, proceed to step 3.8.3 below.

3.8.3

_ If step 2 was unsuccessful, initiate opening the DH cross-4

. connect isolation valves (DH-Vl93 A & B)_ as follows:

3.8.3.1 ENSURE SN-V188 is closed then OPEN DH-Vll2 A & B to filll the inoperable string.

11.0 99 205

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.p.

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. g :+.

a.

2202-1.3 Revision 1 5

06/22/77 NOTE:

If offsite power is lost DHVl93 A & B must be manually opened.

3.8.3.2 - Obtain the keys for the DH cross-connect isolation valves' w(DH-Vig3A and DH-Vl938) breakers from the shif t supervisor.

3.8.3.3 Proceed to 480V MCC 2-328 and MCC 2-42B.

3.8.3.4 Remove the locks from the isolation valve breakers for the DH cross-connect line.

NOTE:

Local control stations for DH-Vl93A and are located in the Aux Bldg at Elev. 280'6" near the DH vaults.

3.8.3.5 "0 PEN" the DH cross-connect isolation valve (e.g. DH-V-193A(.B)1 next to the operating LPI String.

3.8.3.6 "0 PEN" the second isolation valve (DH-Vl93A(_B).).

3.8.3.7 While opening the second decay heat cross-connect isolation valve, " THROTTLE" either DH-V128A or DH-V128B in the control room as required to achieve essentially equal flow rates in both D.H. injection lines. (Approximately 1500 gpm per LPI string).

3.8.3.8 If flow is established at greater than 750 gpm through each LPI string, then proceed to step 3.8.5.

3.8.3.9 If flow cannot be estab11shed through each LPI string in excess of 750 gpne using the cross-connect line before ECCS e

suction must be switched to the RB sump, then proceed to step

.m 3.9.4.

3.8.4

_ If opening the DH cross-connect line fails to provide flow in 4

h eac'h LPI string in excess of 750 gpm, then place one HPI string in a modified " Piggy-Back" mode with the operating LPI string as follows (assume LPI string "A"(B) is the operating string):

99

,406 12.0

2202-1.3 u

Revisicn 7 04/18/78 3.8.4.1 If not already done, " THROTTLE" HPI string "A"(B) flow rate back to 500 GPM using control valve MU-V16A and V16B.

3.8.4.2

" THROTTLE" LPI string "A"(B) flow rate to 3000 GPM using control valve DH-V128A(B).

3.8.4.3 "0 PEN" valve DH-V7A(B) in crossover line from LPI line to suction of the operating HPI pump.

3.8.4.4

" REPOSITION" HPI flow control valves MU-V16A&B to otbain 250 GPM per leg HPI flow and reposition LPI flow control valve DH-V128A to obtain 2500 GPM LPI flow.

The LPI pump is pumping

~

design flow of 3000 GPM (2500 GPM LPI plus 500 GPM HPI).

3.8.4.5

" SHUT OFF" HPI pump in HPI string "B"(A).

3.8.4.6 Proceed to step 3.8.6.

3.8.5

" SHUT OFF" HPI pumps (pump control in control room).

3.8.6 If not already done, THROTTLE BS pump's flows back to 1600 GPM per pump.

This must be done prior to taking suction from the RB sump.

3.8.6.1 When the BWST level decreases to 7' VERIFY the ECCS suction valves (DH-V6A & 'B) from RB sump automatically open.

3.8.7 When suction valves from RB sump are full open (position indication in control room), "CLOSE" the ECCS suction valves (DH-VSA & B) from the BWST.

e 3.8.8

" REPOSITION" LPI flow control valve (s) (DH-V128A and/or B) as required to obtain proper string flowrates.

(Flow rates could change due to change in suction sources).

.g 3.9 W5en the Sodium Hydroxide Tank level reaches approximately 3 ft.

"CLOSE" DH-V8A & B.

3.10 Actuate Environmental Barrier System by opening EB-Vil.

99 n 0 ;7 c

13.0

.m

.e

-s..

...... s 2 _..,

2202-1.3 Revision 11

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10/06/78 3.11 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of ECCS initiation, establish one of the long-term cooling circulation modes described in 2104-1.3 - Decay Heat Removal System, and listed below:

Mode 1 Forced circulation using decay heat drop line.

Mode 2 Gravity draining reactor coolant hot leg to the Reactor Building sump via the D.H. drop line.

Mode 3 Hot leg injection using pressurizer auxiliary spray line.

Mode 4 Reverse flow through the decay heat drop line into "B" Reactor Coolant Loop Hot leg.

4.0 LONG TERM ACTION 4.1 Verify all previous actions and carry out additiclal actions as cutlined below.

4.2 Evaluate symptoms and determine if possible the cause of the loss of coolant.

4.3 Secure turbine, feed water, and steam systems when time pennits.

recombiner per 4.4 Monitor for H buildep and assure actuation of H2 2

2104-6.4, Hydrogen Recombiner Operations.

1 4.5 Monitor R.B. Sump for pH and add Sodium Hydroxide as required thru the decay heat removal system.

4.6 As conditions permit, evaluate unit conditions, and return all non-essential equipment to its normal line up.

fiOTE:

Refer to the following instructions and procedures for o"

additional information as required.

1.._

Radiation emergency plan site emergency in the emergency plan.

4 2,i 2104-5.4 - Coatrol Building HVAC.

14.0 99 c0,o n

0

2202-1.3

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Revision 7

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04/18/78 TABLE A-1 ESF EQUIPMENT - ESF POSITION IN THE CONTROL ROOM PANEL 13 The Wife light for each component should 'oe lit to indicate that the compcnent is in its ESF position, unless otherwise noted.

ACTUATION A ACTUATION B SAFETY INJECTION GP. I SAFETY INJECTION GP. 1 Eauipment ESF Position Equipment ESF Position DC-P-1A ON DC-P-1B ON G2-12 (f6te 1)

CLOSED G22-12 (Note 1)

CLOSED MU-P-1A (Note 2)

C; MU-P-1B (Note 2)

ON NP-P-1A (Note 3)

ON NR-P-lc (Note 3)

ON NS-P-1A (Note 4)

ON NS-P-1B (Note 4)

ON TIE-2E2 OPEN T2E-lE2 OPEN T3E-4E2 OPEN T4E-3E2 OPEN Tile-21E2 OPEN T21E-11E2 OPEN DC-V96A CLOSED DC-V96B CLOSED SAFETY INJECTION GP. 2 SAFETY INJECTION GP. 2 Equipment ESF Position-Equi pment ESF Position NR-V9A CLOSED NR-V9B CLOSED DH-V4A OPEN DH-V4B OPEN DH-VSA OPEN DH-V5B OPEN e

DH-V8A OPEN DH-V8B OPEN DH-V100A CLOSED DH-V100B CLOSED a

DH-V102A OPEN DH-V1028 OPEN

-t MU-P-1B (Note 2).

ON MU-P-lc ON NR-V40A OPEN HR-V40B OPEN NS-P-lc ON NS-P-lC (Note 4)

ON T12-22E-2 OPEN T22E-12E-2 OPEN 9

MU-V28 CLOSED HY.V55 CLOSED

,e n

'..... _ s m.

2202-1.3 Revision 3 TABLE A-1 12/30/77 ACTUATION B ACTUATION A SAFETY INJECTION GP. 3

~ SAFETY INJECTION GP. 3 Equipment ESF Position Equipment ESF Position MU-V36 CLOSED MU-V37 CLOSED HU-V16A OPEN NS-V32 CLOSED MU-V168 OPEN NS-V67 CLOSED DH-P-1A ON DH-P-1B ON NR-P-1B (Note 3)

ON MU-V16C OPEN T31E-41E-2 OPEN MU-V16D OPEN NS-V84B CLOSED NR-P-1D (Note 3)

ON NR-V42A OPEN T41 E-31 E-2 OPEN NS-V84A CLOSED NR-V42B OPEN PANE 1 8 Status Light Equipment ESF Position Indicator NS-V83A OPEN R

NS-V83B OPEN R

NS-V215 CLOSED G

NS-V216 CLOSED G

NOTE 1:

Diesel Generator Breaker will only be closed if Normal Power is lost; othemise status indication will be Open (white).

MU-P-1B will be running if normal power is available for the Actuation, NOTE 2:

-t foh the pump that it is selected to backup.

i If 31ont.al power is lost, MU-P-18 will be running, if the pump that it is selected to backup fails to start or is inoperable.

16.0 99 210

2202-1.3 Revision I 06/22/77 TABLE A-1 fiOTE 3:

The fir pump in each neader selected for ES or standby will start if a pump is not operating in that header; otherwise the operating pump will remain in service.

tiOTE 4:

flormally tis-P-1A and 1B will start; however, itS-P-1C will start if either fiS P-1A or B (depending upon which pump it is selected to backup) fails to start or is inoperable.

9

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17.0 g g

4. i i r

2202-1.3 Revision 7 TT.BLE B-1 04/18/78 ESF EQUIPMENT - ESF POSITION IN THE CONTROL ROOM PANEL 13 The Whi,te light for each component should be lit to indicate that the component is in its ESF position, unless otherwise noted.

}

ACTUATION A ACTUATION B 4

SAFETY INJECTION GP. 1 SAFETY INJECTION GP. 1 Equipment E5F Position Equipment ESF Position DC-P-1A ON DC-P-18 ON G2-12 (Note 1)

CLOSED G22-12 (Note 1)

CLOSED MU-P-1A (Note 2)

ON MU-P-1B (Note 2)

ON NR-P-1A (Note 3)

ON

.NR-P-lC (Note 3)

ON NS-P-1A (Note 4)

ON NS-P-1B (Note 4)

ON TIE-2E2 OPEN T2E-lE2 OPEN T3E-4E2 CPEN T4E-3E2 OPEN T11E-21E2 OPEN T21E-11E2 OPEN DC-V96A CLOSED DC-V968 CLOSED SAFETY INJECTION GP. 2 SAFETY INJECTION GP. 2 Equipment ESF Position Eauipment ESF Position

/

NR-V9A CLOSED NR-V9B CLOSED DH-V4A OPEN DH-V4B OPEN DH-VSA OPEN DH-V5B OPEN DH-V8A OPEN DH-V8B OPEN DH-V100A CLOSED DH-V1008 CLOSED DH-V102A OPEN DH-V102B OPEN MU-P-1B (Note 2)

ON MU-P-lC ON i

NR-V40A OPEN NR-V40B OPEN NS-P-1C ON NS-P-lC (Note 4)

ON T12-22E-2 OPEN T22E-12E-2 OPEN C;g 2]2 MU-V28 CLOSED HY-V55 CLOSED 18.0

2202-1.3 Revision 3 TABLE B-1 12/30/77 ACTUATION A ACTUATION B SAFETY INJECTION GP. 3 SAFETY INJECTION GP. 3 Equipment ESF Position Eauipment ESF Position MU-V36

{

CLOSED MU-V37 CLOSED MU-V16A OPEN NS-V32 CLOSED 4

MU-V16B OPEN NS-V67 CLOSED DH-P-1A ON DH-F-1B ON NR-P-1B (Note 3)

ON MU-V15C OPEN T31 E-41 E-2 OPEN MU-V16D OPEN NS-V84B CLOSED NR-P-lC (Note 3)

ON l

NR-V42A OPEN T41 E-31 E-2 OPEN NS-V84A CLOSED NR-V42B OPEN R.B. ISOLATION AND COOLING GP. 1 R.B. ISOLATION AND COOLING GP 1 Equipment Position Eguipment Position AH-V81 CLOSED AH-E-llD ON AH-V101 CLOSED AH-V80 CLOSED AH-V102 CLOSED AH-V103 CLOSED

/

AH-V105 CLOSED AH-V104 CLOSED AH-V107 CLOSED AH-V106 CLOSED CF-V144 CLOSED AH-V108 CLOSED DH-V3 CLOSED CF-V115 CLOSED NM-V52 CLOSED DH-V2 CLOSED 1

NR-V51A CLOSED NM-V104 CLOSED RR-V2A I

CPEN NR-VSlB CLOSED i

\\

RR-V2B RR-VSA OPEN RR-V2C OPEN RR-V5B OPEN RR-V2D OPEN 99 2

b 19.0

2202-1.3 Revision 3 TABLE B-1 12/30/77 ACTUATION A ACTUATION B R.3. ISOLATION & COOLING GP. 1 R.B. ISOLATION & COOLING GP. 1

. Equipment Position Eauipment Position RR-V5C OPEN RR-V6C OPEN SV-V55 CLOSLD RR-V6D OPEN WDL-V1095 CLOSED RR-V6E OPEN DC-V114 CLOSED SV-V54 CLOSED WDL-V1092 CLOSED DC-V103 CLOSED DC-V115 CLOSED R.B. ISOLATION & COOLING GP. 2 R.B. ISOLATION & COOLING GP. 2 Equipment Position Equipment Position AH-E-4A ON AH-E-4B ON AH-E-llA ON AH-E-11 C ON RR-V25C CLOSED RR-V25C CLOSED BS-VlA OPEN BS-VlB OPEN CA-V10 CLOSED CA-V1 CLOSED CA-V4A CLOSED CA-V3 CLOSED CA-V9 CLOSED CA-V4B CLOSED RR-P-1 B ON CA-V8 CLOSED WDG-Vl99 CLOSED CA-V6 CLOSED WDL-V22 CLOSED RR-P-lD ON WDL-V1126 CLO5ED WDG-V2 CLOSED AH-D4092A & B RECIRC WDL-V1125 CLOSED u

AH-D40920 & E_

RECIRC WDL-V271 CLOSED 4,

ED-4098 AH-D4092A & B RECIRC AH-D4092D & E RECIRC ED-4098 RECIRC n.

{

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20.0

2202-1.3 Revision 3 TABLE B-1 12/30/77 ACTUATION A ACTUATIGN B R.B. ISOLATION & COOLING GP. 3 R.B. ISOLATION & COOLING GP. 3 Eauipment Position Equipment Position IC-V2 CLOSED IC-V3 CLOSED IC-V5 3

CLOSED IC-V4 CLOSED

~

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MU-V2A CLOSED MU-V376 CLOSED MU-V2B CLOSED MU-V18 CLOSED MU V377 CLOSED MU-V25 CLOJED NS-V72 CLOSED NS-V100 CLOSED NS-V81 CLOSED NR-P-2B ON NR-P-2A DN RR-P-1C ON NR-V144A OPEN RR-V25D CLOSED RR-P-1A ON RR-V25E CLOSED RR-V25A CLOSED AH-C-8A ON RR-V25B CLOSED AH-E-llE ON IC-P-1A 0FF AH-P-1B ON AH-C-8A ON AH-V2A CLOSED AH-F-llB ON AH-V2B CLOSED AH-E-llc ON AH-V3A CLOSED AH-P-1A ON AH-V3B CLOSED

1. H-VlA CLOSED AH-V6 CLOSED AH-VlB CLOSED AH-V61 CLOSED AH-V4A CLOSED AH-V61 CLOSED AH-V4B CLOSED AH-V63 CLOSED AH-V5 CLOSED AH-V71 C10 SED l'

AH-V60 CLOSED IC-P-1B 0FF q,

i CLOSED t

AH-V102 I

AH-V72 CLOSED

• BS-P-1A ON

• BS-P-18 ON

• If RB Pressure >30 psig.

99 215 21.0

zzc2-1.3 Revision 1 06/22/77 t

PANEL 15 Equipment ES Position Indication U)

Close G

DH-V6A O)

DH-V6B close G

MU-V378(2)

Open R

~

MS-V4A(.3)-

Open R

MS-V4B(3)

Open R

MS-7A(.3)-

Open R

MS-V7B(3)

Open R

(li This valve must be opened for sump-switchover.

Once opened, the Position / Indication becomes OPEN/R.

(2)

This valve should be closed at the operator's first chance.

Once closed, the Position / Indication becomes CLOSE/W.

(3)

These valves should be closed when the steam system is secured.

Oace closed, the Position / Indication becomes CLOSE/G.

PANEL 25 Equipment ES Position Indication AH-E12A /

Off G

AH-E123 Off G

AH-El9A Off G

AH-E19B Off G

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23.0 99 216 v

.c Revision 7

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06/21/78 I

(

',0 NT RO

_ _ D COP'( TsRee uite iStanD nuC'e4R STATION UllIT #2 EMERGENCY PROCEDURE 2202-2.1 MAS __ER COPY station 8taCx0ur

[

Table of Effective Pages

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Pace Date

. Revision Pace Date Revision Pace Date R evision

?

1.0 12/30/77 3

2.0 12/20/77 3

3.0 06/21/78 7

3.1 03/30/78 6

4.0 02/27/78 5

5.0 06/17/77 1

6.0 12/30/77 3

7.0 01/29/76 0

8.0 03/30/78 6

I Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Approval Date Approval Date Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit PORC Recommends Approval Date 7[

Date Chairman of NRC

[ 'Cha[ man of PORC 4

i Unit 1 Superintenden[, proval Unit 2 Superi tendent A proval 8

Date [

Date

,. /,

Date Manager Generat on Quality Assurance Approval i

n 99 c,,.

gg,4.,,.

Revision 3:

12/30/77 THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE #2202-2.1 STATION BLACKOUT 1.0 SYMPTOMS 1.1 Separfation from the 230KV system and Turbine Generator trip as 4

indication by:

1.1.1 Zero volts on 230KV BUS voltmeters on the Electric Control Console Panel No. 6A.

1.1.2 Generator breakers open as indicated by alarm on Control Room Panel No.18.

2.0 IMMEDIATE ACTION 2.1 Automatic Action 2.1.1 Reactor trips due to loss of voltage to the Control Rod Driu System.

2.1.2 Turbine trips.

2.1.3 Control Room DC lighting is energized.

2.1.4 Turbine Driven Emergency Feedpump starts and comences to feed the OTSG's (Once Through Steam Generators).

2.1.5 Atmospheric steam dur.:p valves, MS-V3A and 3B, control main steam pressure 1010 at psig.

CAUTION:

If a primary to secondary leak is detected, imediatel; close the affected OTSG's atmospheric dump valve isolation valve (MS-Vl A or 1B) to eliminate the potential of leakage and an unmonitored release path.

a NOTE:

The Instrument Air Compressors will not restart

+

g automatically.

Therefore, the atmospheric steam

~

dump valves, emergency feedwater regulation valves, pressurizer level control valve, and seai injection flow control valve will only function as long as the 1.0 99 2!8

"/-

2202-2.1 Revision 3 12/30/77 reserve air in the air receivers is available.

The Instrument Air Compressors should be restarted manually as soon as possible.

2.1.6 T rbine Generator DC Emergency Seal Oil Pump starts.

2.1.7 Turbine Generator DC Turning Gear Oil Pump starts.

~

2.1.8 DC Emergency Bearing Cil Pump for the Main Feedpump Turbine starts.

2.1.9 The DC Oil Lift pumps for the RC pumps start.

2.1.10 The Emergency Diesel Generators start.

DH-VSA and 5B automatically open.

2.1.11 Both Motor Driven Emergency Feedpumps start.

2.1.12 Ventilation fans in the Control Room, Cable Room, Mechanical Equipment Room, River Water Pump House and Diesel Generator Building start.

2.1.13 Make-up pumps (MU-P-1A and IC) start.

(MU-P-1B may service as Backup to either MU-P-1 A or 1C).

2.1.14 Nuclear Services River Water pumps start.

2.1.15 Nuclear Services Closed Cooling Water pumps start.

2.1.16 The Intermediate Closed Cooling Water pump starts.

2.2 Manual Action

2.2.1 Verify

2.2.1.1 The Turbine Driven Emergency Feedpump starts.

2.2.1.2 Atmospheric Steam Dump valves open when steam pressure reaches 1010 psig.

~

i 2.2.1.3 Tpe fellowing DC pumps start.

2.2.1.3.1 Tor bine Generator DC Emergency Seal Oil Pump.

2.2.1.3.2 Turbine Generator DC Turning Gear Oil Pump.

99 2l9 2.2.1.3.3 DC Emergency Bearing Oil Pump for the Main Feedpump Turbine.

2.0

2202-2.1 Revision 7

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l l

06/21/78 2.2.1.3.4 DC Oil Lift pumps for the RC pumps.

2.2.1.4 Both Diesel Generators start and the generator voltage is 4160 volts and the frequency is 59-61 Hertz.

2.2.1.5 T6e voltage available lights Unit Substations 2-llE 2-12E, 2-21E, 2-22E, 2-31E and 2-41E energize.

1 2.2.1.6 Verify the following equipment has started and the associated systems are operating properly:

2.2.1.6.1 Nuclear Services Closed Cooling Water Pumps.

2.2.1.6.2 Motor Driven Emergency Feedwater Pumps.

2.2.1.6.3 Nuclear Services River Water Pumps.

2.2.1.6.4 Make-Up Pumps and DH-V5A and B open.

2.2.2

" START" both Instrument Air Compressors per 2104-2.3A.

If tha Instrument Air Compressors do not have sufficient capacity to maintain the air pressure above 85 psia, "CLOSE" the Turbine Building Instrument Air Isolation valve, IA-V29.

2.2.3 Verify the Intermediate Closed Cooling Water pumps start.

2.2.4 Verify the Emergency Feedwater Regulation valves, EF-Vil A and B, are functioning properly and "CLOSE" EF-V32A and B.

If EF-VilA and B are not operable maintain OTSG level by manually throttling EF-V32A and B.

2.2.5 Verify the Turbine Driven Emergency Feedpump is functioning properly and "STOP" both Motor Driven Emergency Feedpumps.

2.2.6 Verify RC seal temperatures did not exceed 185 F, and that seal leakage plus seal return flow dues not exceed 1.9 gpm. If ei_ther condition exists, the RCP seals should be examined 4

b fore 'further RCP operation.

2.2.7 If any of the following ICS Stations are in Hand, Steam Generator Reactor Demand, either Feedwater Demand, Main or Startup Feedwater Valve Demand, Feedpump Speed, Reactor Master and/or Diamond Station,runbacktheapplicableICSSt$ttion gg 220 1n 7

2202-2.1 Revision 6 03/30/78 3.0 FOLLOW-UP ACTION 3.1.1 Attempt to restore one 230KV line and BUS based on direction

{fromtheDispatcher.

If at ieast one 230KV is re-energized.

're-energize plant 6900V, 4160V and 480V switchgear through the auxiliary transformer to enable s'. art of the Reactor Coolant Pumps and er,ergization of the pressurizer heaters to enable a normal cooldown per 2102-3.2.

f 1

I

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' bb 3.1

....m.

.. ~...

2202-2.1 Revision 5 02/27/78 3.1.2 If neither 230KV BUS can be energized, continue with cooldown by natural circulation using the emergency feedpumps, the OTSG's and the atmospheric dump valves to control the cooldown rate.

Remain within the limits of the curve for cooldown by natural circulat#cn (Figure #1).

NOTE:

Pressurizer spray and heaters are not available for pressure control due to power loss.

Primary system pressure decrease will be dictated by Pressurizer heat losses to ambient which will cause approximately 100 to 200 psi /hr decrease in primary system n*etture.

3.2.1 If (2) MU pumps are rungr.g.' '

3.2.2 CloseDH-VSA/B as required to maintain MU Tank level.

Trip a MU pump as required to maintain pressurizer level.

3.3 Borate the Reactor Coolant System using the Borated Water Storage Tank as follows:

NOTE:

Neither the Boric Acid Mix Tank, the Concentrated Waste Tank nor the Reclaimed Bori Acid Tank are available as a,

source of bo' rated water dt ring a loss of Normal Power situation.

3.3.1 "0 PEN" DH-VSA and SB.

3.3.2 Manually "0 PEN" the RC Letdown to Bleed Hold-up Tank Isolation Valve WDL-V46.

3.3.3 Determineto$hichR.C.BleedHold-upTanktheRCLetdownwill flow and manually "0 PEN" the RC Hold-up Tank Inlet Valve.

4 U

either WDL-V963, WDL-V964 or WDL-V965.

CAUTION:

These valves are located in a 3000 mr/hr radiation zone and exposure time must be minimized.

4.0

2202-2.1 Revision 1 06/17/7) 3.3.4 Mar.ually " POSIT 1mi" MU-V8 to the " BLEED" position.

3.3.5 "CLOSE" MU-V10.

3.3.6 "CLOSE" MU-V12.

3.3.7 Monitor RC Bleed Hold-up Tank and Borated Water Storage Tank levels.

3.4 Following the addition of boric acid, sample the Reactor Coolant for bcron concentration and verify shutdown margin per 2103-1.9.

l 3.5 During cooldown by natural circulation observe the following limits:

0 3.5.1 Upper OTSG downcomer to cold leg maximum AT=25 F.

0 3.5.2 The maximum cooldown rate is 100 F/hr.

3.5.3 Pressure to temperature limits are dictated by the curve for cooldown by natural circulation, figure fl.

l 3.6 Manually " JACK" the Main Feedpump Turbines when they have stopped.

The turbines should be jacked 180 every 20 minutes.

3.7 Manually " JACK" the Main Turbine when it has stopped.

The Main Turbine should be turned 180 every 30 minutes.

3.8 " START" one Control Building Area Fan-coil unit, AH-C-50A or B.

BUTION:

Do not exceed a load c' 3 MW on either Diesel Generator.

3.9 If the Reactor Building temperature exceeds 112 F " START" one RB Normal Cooling Unit and three RB Cooling Fans per 2104-3.1.

3.1011 the RB penetration cooling air outlet temperatures exceed 140 F

" START" one RB Fenetration Forced Air Cooling Unit, AH-C-48A or B,

. s per 2104-1.7.

3.11 " START" one Control Building River Water Booster pemp and one

~

Control Building Chiller linit if required.

3.12 Energize portions of the Heat Tracing System as required.

3.13 Between 1820 psig and 1600 psig RC System pressure, bypass all SFAS n2 n

channels for Safety Injection.

b 5.0

2202-2.1 Revision 3 12/30/77 3.14 At 700 psig RC System, assure "CLOSE" CF-VlA and B, and "0 PEN" and tag the power supplies to these valves.

3.15 At 500 psig RC System pressure rack out RB Spray pumps BS-P-1A and 1B, t[reakers to prevent unnecessary actuation and cui in low pressure instrumentation.

(RC-3A-PI2).

3.16 At 275 F RC System temperature place the NDTT "AUT0-OFF" control switch for the electromatic relief valve RC-R2 to "AUT0" to actuate the 500 psig relief set point.

3.17 When the RC System temperature is below 250 F shift cooldown from the atmospheric dump <alves to the Decay Heat Removal System as follows:

CAUTION:

Do not exceed 3 MW load on either Diesel Generator.

3.17.1 Line up the Nuclear Services River Water System for Decay Heat Service Cooler Operation per 2104-3.lF.

CAUTION:

De not start a second NSRW pump in the operating header to prevent overloading a Diesel Generator.

3.17.2

" START-UP" the Decay Heat Closed Cooling Water Loop associated with the Decay Heat Service Cooler placed operation per step 17a above.

Refer 2104-3.3.

3.17.3

" START-UP" the Decay Heat Removal Loop as:,0ciated with the operating Decay Heat Closed Cooling Water Loop.

Refer to 2104-3.3.

3.18 When the Decay Heat D'cyal System is operating properly and is capable of removii.,

' all the decay heat generated in the Reactor, q

term 5ateheatremovalwiththeOTSG'sasfollows:

t 3.18.1 "CLOSE" the Atmospheric Dump valves, MS-V3A and B.

n r.

6.0

.'r..: -

2202-2.1 Revision 0 01/29/76 3.18.2 Fill the OTSG's to the proper shutdown level.

3.18.3 "STOP" the Turbine Driven Emergency Feedpump and "CLOSE" EF-

-VilA and B or EF-V32A and B.

?

~

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v. ' -

HEAT UP/C00LDOWN CURVE Revision 6

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8.0

. A tta c ntn ent fr i ' ' ' *~"

.. c. - m.-

9 Trailer City - RiI GPU Service Corporation Ut(_. h) service April 16, 1979 260 Cherry Ha Road Parsippany New Jersey 07054 v

+

201 263-4900 TELEX 136-482 TO:

R. C. Arnold

5., -

IROM:

R.1,.Longj... '. ' '

PRELIMINARY SEQUENCE OF EVENTS

' ' DfI 2 ACCIDENT OF MARCH 28, 1979 f.ttached is a Preliminary Sequence of Events spanning the first approximately twenty hours following ?.he DII-2 accident which was initiated at 4:00 a.m. on March 28, 1979.

For this chronology of events, a reference clock vas established with the time of the turbine trip, 0400:37, defined as time zero.

The time of each event in the sequence is given as the number of hours, minutes and seconds relative to 0400:37, followed in parenthesis by the real ti=e using a 24-hour clock.

For example, 1:52:43 p.=. on March 28 would be written "9:52:06 (1352:43)."

Depending upon the accuracy of the source of data for each event, the times appear alone or with the notation " approximate."

The sequence has been reconstructed from various infor=ation and data sources, including control room legs, strip chart recorders, alarm printouts and reactimeter printouts.

Please note, however, that the alarm printer was out of service frcs 01:13:27 (0513:59) to 02:47:31 (0648:08) and during the course of the accident was running well behind the actual ti=e of events.

Efforts to annotate this chronology and to develop graphs of various plant parameters as a function of time are underway. This additional information will be provided as soon as it is available and we will keep you infor=ed.of our progress.

O]

V R. L. Io CPU CC: H. Dicekacp J. Herbein R. 'Jilson Industrial Advisory Group Data Reduction and. Manage =ent 4

M. Bezilla L. Harding C. Kunder 4

J. Iogan g

C. Miller 677 o] o (LI

/

GPU Servce Coe poranon s a su% diary of Generaf Public UtAtes Corporaton

.i..

........:*1.

7.

^

PE M NA'RY SEQUENCE'0F EVENTS

.... ~ -. - -

~

' nil 2 ACCIDENT OF MARCH 28, 1979 Issued April 16, 1979

-00:05:00 Three Mile Island Unit Two was at 97% power with the Integrated (0355:36)

Control System in full automatic.

Rod groups one thru five were

~

fully withdrawn, rod groups si.x and seven vere 95% vithdrawn and rod group eight was 27% vithdrawn.

Reactor Coolant System total flow was approximately 107.5% of design flow and the Reactor Coolant System pressure was 2155 psig. Reactor Coolant Makeup Pump B (MU-F-1B) was in service supplying makeup and Reactor Coolant Pump Seal injection flow. The Reactor Coolant Syste= soluble boron concentr'ation was approximately 1030 parts per million.

Pressurizer Spray Valve (RC-V1) and the pressurizer heaters were in manual contrcl while spraying the pressurizer to equalize boron concen-trations between the pressurizer and the remainder.of the Reactor Coolant System. Normal Reactor Coolant System letdown flow was established.

Steam Generator parameters were as shown in th'e following table:

/

Steam Generator A Steam Generator B Loop Feedwater 5.7459 MPPH*

5.7003 MPPH*

Operating 1,cvel 56%

57.4%

Startup Level 158.8 inches 163.4 inches Steam Pressure

'910 psig 889.6 psig

)

Feedwater Temperature 462.7F 462.7F

-+

i

~_

't.'MPPH is Hillion Founds Per Hour nnO 9 h

l. L U

~'

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' ' *h. :...

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~

Steam Generator Feedwater Pumps (W-P-1 A and W-P-1B) were in

~

service, Condensate Booster Pumps (CD-P-2A, CO-P-2B and CO-P-2C) were in service, and Condensate Pumps (CO-P-1A and CC-P-1B) bere in service.

An attempt v'as being made to clear a clogged -

.r

~

resin transfer line in the standby demineralizer.

-00:00:01 Condensate Pump A (CD-P-IA) stopped.

(0400:36)

-00:00:01 Feedwater Ptaps (W-P-1A and W-P-13) stopped at essentially the (0400:36) same time resulting in a loss of feedwater flow to both steam generato,rs.

00:00:00 Main Generator was tripped followed by a turbine trip.

(0400:37) 00:00:00 Wree Emergency F edvater Pumps (EF-P-1, 2A, 2B) started.

(0400:37) 00:00:03 The Electromatic Relief Valve (RC-RV2) opened at the setpoint (0400:40)

Approximate of 2255 psig.

00:00:08 Reactor tripped on high pressure at 2345 psi. Setpoint is 2355 psi.

(0400:45) 00:00:08 The operator placed.the Pressurized Spray Valve (RC-V1) and pres-(0400:45)

Approximate surizer heaters under automatic control.

00:00:13 h e operator started the Reactor Coolant Makeup Pump A (MU-P-IA),

opened High Pressure Injection Isolation Valve A (MU-V16A) and iso ated letdown flow in anticipation of the expected pressurizer ti level decrease.

-t i.

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00:00:13 The Electromatic Palief (RC-RV2) solenoid de-energized giving (0400:50)

Approximate a non-open indication to the control room operators. De Elec-

,tromatic Relief Valve (RC-RV2) should have rescated at about this

f. time (closure set;xsist of 2205 psig).

00:00:14 he Emergency Feed Pumps (EF-P1, 2A and 2B) achieved normal dis-(0400:51) charge pressure.

00:00:15 Water hammer in the condensate piping occurred.

(0400:52)

Approximate 00:00:30 Pressurizer Safety Valve (RC-KV13) and Electromatic Relief Valve (0401:07)

(RC-RV2) discharge line temperature alarms printed out.

00:00:38

' Steam Generator A level reached the 30-inch setpoint where the (0401:15)

Approximate Emergency Feedwater Valves (EF-VllA and EF-V11B) open.

Feedvater was not admitted because Emergency Feeduater Block Valves (EF-V121 and EF-V12B) were shut.

00:00:39 Reactor Coolant Maieup Pump A (MU-P-1A) was stopped.

(0401:16) 00:00:40 Stean Generator B Ievel reae.hed the 30-inch setpoint where the (0401:17)

Apprcximate Emergency Feedwater VaTves (EF-VilA and EF-VilB) open.

Feedvater e

was not admitted because Evargency Feedwater Block Valves (EF-V12A and EF-V12B) were shut.

\\\\

00:00:41

,Rezetor Coolc.at Ma".:eup Pump A (MU-P-1 A) wa s res tarted.

With

.)

(0401:18) g

'.Reac' tor Coolant Maicup Pumps and B (MU-P-1A and MU-P-13) oper-ating, pressurizer level rate of decrease slowed.

99 230

. _ ~.

.J

- - 3.. ~.._."'.-..

.g

~

. ~; ;.. zf. :, ;.'..~. *c. - ~.?.'... 4.. i.,..

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'. 00':01:00 Pressurizer level started increasing.

Reactor Coolant System hot (0401:37)

Approximate leg and cold leg temperatures reached 575F.

Reactor Coolant Drain Tank pressure was increasing.

5he Pressurizer Safety Valve (RC-RVIA) high discharge 'line temper _~

00:01:00 (0401:37) b ature alarm was received.

00:01:26 Reactor Coolant Drain Tank temperature normal alm printed out.

(0402:03) 00:01:45 Steam Generators A and B have boiled dry at this time.

(0402:22)

Approximate 00:02:01 Reactor Coolant Makeup Pump B (MU-P-13) was stopped due to (0402:38)

Engineered Safeguards actuation.

00:02:04 High Pressure Injection Pump C (MU-P-lC) started atitomatically.

(0402:41) 00:03:12 Reactor Coolant Drain Tank Relief Valve (WDL-Rl) lifted at 120 psig.

(0403:49)

Approximate 00:03:14 High Pressure Injection portion of Engineered Safeguards was manually (0403:51) bypassed.

Both Reactor Coolant Makeup Pucps A and C (MU-lP-1A and MU-P-1C) were operating.

00:03:26 Reactor Coolant Drain Tank high temperature alarm received at 127.2F.'

(0404:03) 00:04:38 React r Coolant Makeup Pump C (MU-P-lC) was stopped.

(0405:15) 4 00:04:38 "Ihe operator throttled the High Pressure Injection Isolation Valves (0405:15)

~

Approximate (MU-V16's).

99 23i -

p.:-..-

-~

,r.'-

.s ':. */ ' ~ ' - :' -" -= * - #.

6 ".; '~

00:04:52 Intermediate Closed Cooling Pump (IC-P-1A) started.

(0405:29) 00:04:58 First alarm indication received that letdown had been secured.

, (0405:35) 00:05:06 Presurizer level stopped its sharp increase at 376 inches and (4405:43) began to turn down.

It reached a minimum of 372 inches and then started back up at 5 minutes, 21 seconds into the transient.

00:05:15 Condensate Booster Pump B (CO-P-23) tripped.

(0405:52) 00:05:50 Reactor Coolant System pressure stopped its sharp decrease and began (0406:27)

Approximate to turn up.

Minimum value reached was approximately 1350 psig.

00:05:54 Pressurizer level increased beyond the range of the instrument (0406:31) indication.

00:06:58 Letdown flow of 71.4 gallons per minute was re-established.

(0407:35) 00:07:31 Aeactor Building Sump Pump A (WDL-P-2A) started.

(0408:06)

/

00:05:00 Emergency Feedvater Block valves (EF-V12A and EF-V12B) were opened..

(0408:37)

Approximate r

00:08:15 Reactor Coolant System hot leg and cold leg temperatures began to (0408:52) decrease.

00:08:30

_ Reactor Coolant System pressure began to decrease.

4 (0409:07) n, g

00:10:00 Pressurizer level came on scale.

(0410:37) 99

,4.)9 u

- s+ \\'

.N* :,

u'.

-': k~ ;;.- :;4-t _

. 00$1.0:19 Reactor Building Sump Pump B (WDL-P-2B) started.

(0410:56) 00:10:24 Reactor Coolant Makeup Pump A (MU-P-1A) tripped.

(0411:01)

~

00:10:27

. Reactor Coolant Makeup Pump A (MTT-P-1A) was started.

(0411:04) 00:10:28 Reactor Coolane !;axeup Pu=p A (MU-P-1 A) tripped.

(0411:05) 00:10.40 Reactor Building Sump high level alarm received.

Setpoint is (0411:25) 4.650 feet.

00:11:40 Reactor Coolant Makeup Pump A (MU-P-1A) was started.

(0412:17)

/

/

00:14:50 The Reactor Coolant Drain Tank rupture diaphragm (WDL-U26) failed.

(0415:27) 00:24:58 The operator requested computer printout of the Electromatic (0425:35 Relief Valve (RC-RV2) outlet temperature.

The reading was 285.4F.

00:25:00

. Intermediate Cooling Syste:s high radiation alarm annunciator (0425:37)

Approximate received at the Radiation Monitor Panel.

00:36:03 Emergency Feedwater Pump 2B (EF-P-2B) was stopped.

(0436:41) 9 00:38:10 Reat.or Building Sump Pump A (WDL-P-2A) was stopped.

(0438:47) 0

-00:38:11 Reactor Building Sump Pump B (WDL-P-2B) was stopped.

(0438:48) y t.

p 01:10:54 eactor Building air cooling coils emergency discharge alarm (0511:31) printed cut.,

=

99 n4.) 3

~

w-

.,,.-~.h..m

~ - '.

'O'1 13:29 Reactor Coolant Pump 2B (RC-P-2B) was stopped.

(0514:06) 01:13:42 Reactor Coolant Pump 1B (RC-P-1B) was stopped.

(0514:19) 01:13:27

.The alarm printer became unavailable at this time and remained (0513:59) out of service until 02:47:31 (0648:08).

01:20:31 Operator requested printout of the Electromatic Relief Valve (RC-RV2) outlet temperature. The reading was 283.0F.

01:40:37 Reactor Coolant Pump 2A (RC-P-2A) was stopped.

(0541:14) 01:40:45 Reactor Coolant Pump 1A (RC-P-1A) was stopped.

(0541:22) 01:42:00 Operator started raising Steam Generator A level fr'om 30 inches (0542:37)

Approximate on the Startup Range to 50% on Operating Range.

Reactor Coolant System Loops A and B cold leg temperatures both started decreasing.

Reactor Coolant System pressure started decreasing.

01:54:00 Reactor Coolant Syst,em Loop A hot leg temperature began increasing.

(0554:37)

Approximate 02:00:00 Steam Cenerator A level reached 50% on Operating Range.

(0600:37)

Approximate 02:00:00 Reactor Coolant System Loop B hot leg temperature began ' increasing. I (0600:37)

.g 02:12:00 peactor Coolant System Loop B hot leg temperature increased to (0612:37) fiscale at 620r.

-77 L J 'i e

.,.q.....

. _,. w.......,., _ g.. o n.

f 02:17:53 Operator requested Electromatic Relief Valve (RC-12) outlet i

(0618:30) temperature. The reading was 228.7F.

02:22:00 The Electromatic Relief Block Valve (RC-V2) was shut.

(0622:37)

Approxima te Operator started increasing Steam Generator 3 fros 30 inches on 02:30:00 (0630:37)

Startup Range to 50% on Operating Range.

02:45:00 Several radiation alarms were received.

(0645:37)

Approximate Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.

02:45:00 (0645:37)

Appr oxi=a te Operator opened Main Steam Isolation valves (MS-V13 and MS-V7Bi-02:45:00 (0645:37)

Appr oxima te 02:50:00 Site Emergency was declared.

Notifications to offsite authorities (0650:37)

Approxi:at e and organizations were initiated.

02: 51:57 Operator attempted to start Reactor Coolant Pump 21 (RC-P-2A).

(0652:34)

Pump would not start.

Operator attempted to start Reactor Coolant Pump 13 (RC-P-1B).

02:53:39 (0653:33) e Pump would not start.

02:54:09 Operator started Reactor Coolant Pump 2B (RC-P-23).

i (0654:46) 4 high Pressure Injection Engineered saf eguards acte 2 tion logic 02:54:49 (0655:25)

N reset on incre. sing Reactor Coolant System pressere.

~ gg n?C

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bJJ

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

.m......

,,..._.m.,_

02':56:19 Steam Generator B was isolated.

Main Steam Isolation valses

~

(0656:56)

(MS-v4B and MS-V7B) were shut.

Approximate 03:00:00 Reactor Coolant System pressure increased to 2130 psig.

(0700:37)

Approximate ".

03:03:39 Steam Generator A pressure control was shifted from the Turbine Byp' ass (07n4:16)

Approximate Valves (MSV-25A and B and MSV-26A and B) to the Power Operated Emergency Main Steam Dump Valves (MSV-31 and B).

03:10:27 Emergency Feedvater Pump 2A (EF-P-2A) vissstopped.

(0711:04) 03:12:28 Electromatic Relief Block valve (RC-V2) was opened.

(0713:05)

Approximate 03:12:53 Reactor Coolant Pump 2B (RC-P-23) was stopped.

(0712:53) 03:20:13 Reactor Coolat.t Makeup Pump C (MU-P-IC) was started.

Reactor Coolant (0720:41)

Makeup Pumps C and A (SU-P-C and A) were operating.

03:23:23 General Emergency was declared. Notificz: ions to offsite (0724:00)

/

Appr ox ima te authorities and organizations were initiated.

03:30:00 Electromatic Relief Block Valve (RC-V7) was shut.

(0730:37)

Approximate 9

03:35:08 Emergency Feedvater Pump 2A (EF-P-2A) was started.

(0735:43) i 03:37:00

' Reactor Coolant Makeup Pump C (MU-P-1C) wa s stopped.

i (0737:37)

J t

03:51:00 Electromatic Relief Block Valve (RC-V2) vas opened.

(0751:37)

Approximate n?(

99 LJ9 -

" 03:55:39 Engineered Safeguards actuated on lov RCS pressure.

Setpoint is (0756:16) 1640 psig.

03:55:39 The Reactor Building high pressure isolation signal actuated (0756:16) send isolated the Reactor Building.

The Reactor Building isolation -

set point is 4 psig.

03:56:04 Reactor Coolant Makeup Pump C (MU-P-lC) was started.

(0756:41) 03:59:23 Reactor Building Emergency Cooler B was shutdown.

(0800:00) 03:59:53 Reactor Building Emergency Cooler B was started.

(0800:30) 04:06:00 Electromatic Relief Block Valve (RC-V2) was shut.

(0806:37) 04:08:37 Reactor Coolant Pump 1A (RC-P-1A) was started.

(0809:14) 04:09:14 Reactor Coolant Pusp 1A (RC-P-1A) was stopped.

(0809:51)

/

04:17:17 Reactor Coolant Makeup Pump A (MU-P-1A) was stopped.

(0817:54) 04:17:22 Reactor Coolant Makeup Pump C (MU-P-1C) vas stopped.

No makeup pumps operating.

04:18:17 Operator attempted t o start reactor Coolant Makeup Pump A (MU-P-1A).-

(0818:54)

The pump would not start.

-t

- i.

04:18:30 Electromatic Religf Block Valve (RC-V2) was opened.

(0819:07)

Approximate 10 -

v

~

04:21:53 Reactor Coolant Makeup Pesp B (MU-P-1B) was started.

(0818:30) 04:26:59 Reactor Coolant Makeup Pump C (MU-P-lC) was started, tripped, (0827:36)

Approximate

~and was restarted.

?

04:30:00 The Electromatic Relief Block Valve (RC-V2) was shut.

(0830:37)

Approximate 04:30:45 Condenser Vacuum Pumps lA and IC (VA-P-1A and VA-P-lC) were (0831:22) stopped and vacuum was broken.

04:30:45 Power Operated Emergency Main Steam Dump Valve (MS-V3A) was opened.

(0831:22)

Approximate 04:54:00 The Electrcnatic Relief Block Valve (RC-V2) was opened.

(0854:37)

Approximate 05:18:00 The Electromatic Relief Block Valve (RC-V2) was shut.

(0918:37) 05:54:00 Operator commenced filling Steam Generator A to 99% on the Operating (0954:37)

Approximate Range instrumentation.

07:30:00 Electromatic Relief Block Valve (RC-V2) and the Pressurizer Spray (1130:37)

Approximate Valve (RC-V1) were opened.

08:11:26 Core Flood Tank A high level alarm was received.

(1212:03) j hPowerOperatedEmergencyMainSteamDumpValve (MS-V3A) was shut. i 08:30:00 (1230:37) 1 11 -

99 670dJO M W W-e*% er" sh. ems em e ow h

,m

,g

08:31:06 Decay Heat Removal Pumps IA and IB (DH-P-1A and DH-P-1B) were (1231:43) started.

08:54:56 (1255:33)

- Core Flood Tank A alarm printed out at a level of 13.13 feet.

09:04:18 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.

(1304:55) 09:49:44 Reactor Building Isolation and Containment Spray were actuated by (1350:21)

Engineered Safeguards.

Engineered Safeguards actuation started Reactor Coolant Makeup Pump C (MU-P-lC) and Reactor Building Spray Pumps A and 3 (BS-P-1A and BS-P-1B).

09:49:50 Reactor Building Spray Valves (BS-VlA and BS-VilB). opened.

(1350:27) 09:49:58 Reactor Coolant Pumps lA and IB (RC-P-1A and RC-P-1B) inlet air (1350:35) temperature high alarms annunciated and Pressurizer Safety Valves (RC-RIA and RC-RIB) discharge line temperature high alarms annun-ciated.

09:50:24 Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.

(1351:01) 09:55:30 Reactor Building Spray Pumps A and B (BS-P-1A and BS-P-1B) were (1356:07) stopped.

9 09:56:58 Decay Heat Removal Pumps A and B (DH-P-1A and DH-P-1B) were (1357:35)

O stopped.

-t

- -10:24:(0 i Reactor Coolant System hot leg Loop A temperat are decreased to'

-t.

(1424:37)

Approximate within the instrumentatica range.

67O 99 dJi

~~

12 -

.=

= =%. e

.... ='

o-

-..-====

_==*=.m==..si

.==o=-m=

e--

. --==

.=

- = = - - ~

10:31:25 Reactor Coolant Makeup Pump C (MU-P-1C) was started.

Reac tor (1432:02)

Coolant pressure was approximately 440 psig.

10:35:55

] Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.

(1436:32) 11:06:00 Pressurizer level started decreasing.

(1406:37)

Approximate 11:12:00 Reactor Coolant System cold leg Loop A temperature started to (1512:37)

Approximate increase from 200F to 400F, Reactor Coolant System hot leg Loop A

~

temperature decreased from above the instrument range to 560F, 11:18:34 Reactor Coolant Makeup Pump C (HU-P-1C) was started.

(1519:11) 11:24:00 Pressurizer level stopped decreasing at 180 inches and started (1524:37)

Approximate increasing, going off scale during the next hour.

11:28:12 Reactor Coolant Makeup Pu=p C (MU-P-1C) was stopped.

(1528:49) 11:32:37 Reactor Coolant Makeup Pump C (HU-P-1C) was started.

(1533:14) 11:35:48 Reactor Coolant Makeup Pump C (HU-P-1C) was stopped.

(1536:25) 9 11:36:00 Operator commenced filling Steam Generator B to 97% on the Operating (1536:37)

Approximate Range in s t rumen t a t ion.

y 12:00:00 i

4 i

,Stea6 Cenerator A level was 97% on the Operating Range.

(1600:37)

Approximate 12:48:00 Pressurizer level came on scale.

(1648:00)

Approximate 7}3 L a V

' l2f:02:23 Condenser Vacuum Pump IC (VA-P-lC) was started.

^

'(1763:00) 13:08:22

. Normal steam gen nator feedwater supply was put in service.

(1708:59)

Approximate 13:13:10 Condenser Vacuum Pump 1A (VA-P-1A) vas started.

(1713:47) 13:23:04 Reactor Coolant Makeup Pump C (.W-p--1C) was started.

(1723:41) 14:43:15 Reactor Cec. ant Makeup Pump C (MU.~--lC) was stopped.

t (1843:52) 14:54:00 RCS pressure reached 2350 psig.

(1854:37)

Approximate 15:24:00 Reactor Coolant Pump 1A (RC-P-1A) sus started.

(1924:37) 15:24:10 Reactor Coolant Pump 1A (RC-P-1A) s2s stopped.

(1924:47)

Approximate 16:04:00 Reactor Coolant Pu=p 1A (RC.P-1A) s s started.

(2008:37) f 22:15:00 Reactor Coolant System and Steam Ge:erator conditions were:

(0215:37)

Approximate Reactor Coolant System pressure = l 65 psig.

Pressurizer Temperature = $51F (pressurizer heaters maintaining temperature).

E Pressurizer Level = 397 inches, desector Coolant System cold leg Loop A temperature a 288F i

i.

li 4

Sfeam Generator A steaming to the F.2in Condenser.

14 -

O h 99 29.

9

............... u..