ML20205B175

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Rev 3 to Emergency Operating Procedure EOP 35 ES-0.1, Reactor Trip Response
ML20205B175
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/15/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-35-ES-.1, EOP-35-ES-0.1, NUDOCS 8810260199
Download: ML20205B175 (13)
v • d • e


Text

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St ph n E.

ac9 3-31-87 87-12 Form ApprovId by Statsun Superintsndant Effective D. e 50RC Mtg. No, n

STATION PROCEDURE COVER SHEET

(,)

A.

IDENTIFICATION Number: E0P 35 ES-0.1 Rev.

3_

Title:

REACTOR TRIP RESPONSE Prepared By: H.

K. Covin B.

REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD

@ II d,

(, //!f5-a 3

<f C.

SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents.

YES [ ]

NO (d (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Franch to determine need for Integrated Safety Evaluation,

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact)

YES ( )

NO ( g D.

SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response.

YES [ ]

NO ( #

(If yes, perform written Safety Evaluation and contact Manager, safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E.

INTEGRATED SAFETY EVALUATION REQUIRED YES [ ]

NO ( (

F.

PROCEDURE REQUIRES

/SORC REVIEW (In addition to review, it +swith a YES response must be documented in the PO '/50RC meeting minutes.)

YES[d,NO()

G.

SORC APPROVAL SORC Meeting Number

%Q 7- / 6'8 H.

APPROVAL AND IMPLEMENTATION The attached fore 4ure is reby approved, and effective on the date below:

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5tation/ Service / Unit Superintendent Effective Date SF 301 Rev. 9 8810260199 001007 PDR ADOCK 05000213 P

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E0P 35 ES-0.1

, age 1 i

Rev. 3 i

1 REACTOR TRIP RESPONSE i

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Page No.

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REACTOR TRIP RESPONSE E0P 35 ES-0.1 Page 2 Rev.'3 (g

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A.

PURPOSE This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.

B.

ENTRY CONDITIONS This procedure was written for Modes 1 and 2.

Using this procedu e when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.

This procedure is entered from EOP 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 4, when SI is neither actuated nor required.

OPSc64 2 3-44

r-REACTOR TRIP RESPONSE E0P 35 ES-0.1 Page 3 Rev. 3

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 0 STAINED CAUTION If SI accuation occers during this procedure EOP 35 E-0, REACTOR TRIP OR SAFETY INJECTION, should be performe1.

NOTE Foldout page should be open.

1 Check RCS Average ".emperature -

IF temperature < 557'F STABII AT OR TRf*. DING TO 557'T and decreasing, THEN a.

Check the steam dump valves closed, if not turn 0FF Steam Dump Interlock Selectors Train A/B.

b.

IF cooldown continues, THEN control total feed flow.

Maintain total

[ 'N feed flow > 525 gpm xj until narrow range level m

> 4% in at least one SG.

c.

IF cooldown continues, THEN close Steam Line Isolation Valves and Main Steam Isolation Bypass Valves.

d.

Check SG safety valve flows and atmospheric reliefs for satisfactory operation.

IF temperature > 557'T and l

it.c rea s ing, THEN 4.

Dump steam to condenser.

-Od-b.

Dump steam to atmosphere.

[h O

OP* :r 4 1 3 14

REACTOR TRIP RESPONSE E0P 35 ES-0.1 Page 4 Rev. 3 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.

Check FW Status

  • a.

Check RCS average a

Continue with Step 3.

temperatures < 564'T WHEN temperature <

564'F, THEN do Steps 2b and c.

b.

Verify FW flow control b.

Manually close valves.

, valves

  • CLOSED c.

Verify total auxiliary c.

Establish feed flow to feed l'ow to SGs SGs as necessary

> 525 uPH

1) AFW

-OR-

2) Reset Feedwater Isolation and establish Main FW on bypass.

I)

3.

Verify All Control Rods Fully IF two or more control rods

(_,/

Inserted E6Tfullyinserted,THEN immediately borate 200 ppm for each control rod not fully inserted.

O)

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oPM41 3 44 A

O REACTOR TRIP RESPONSE E0P 35 ES-0.1 Page 5 Rev.'3 STEP ACTIONiEXPLCTED RESPONSE RESPONSE NOT OBTAINED 4.

Check PZR Level Control a.

Level > 17%

a.

Perform the following

1) Verify letdown i=olation.

IF NOT, THEN manually isolate.

2) Verify PZR heaters off.

If NOT, THEN manually turn off.

3) Control charging to resture PZR level >

17%.

4) IF no charging pumps are in service, THEN restore RCS inventory per E0P 3506.
5) WHEN PZR level >17%,

THEN place letdown in f

)

cervice and

_j reenergize $2R heaters as necessary,

6) Go to step 4c.

b.

Verify charging and b.

Manually place in service letdown - IN SERVICE

1) Establish the normal charging flow path
2) Establish normal letdown c.

Level - TRENDING TO 25%

c.

Control charging and letdown t~ maintain level at approximate'y 25%.

1 1

REACTOR TRIP RESPONSE EOP 35 ES-0.1 Rev. 3

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~.Y STEP ACTION / EXPECTED RESPONSE RESPONSt NOT OBTAINED 5

Check PZR Pressure Control a.

  • Pressure > 1892 PSIA a.

Verify SI actuation.

IF NgT, THEN manually actuate SI.

Go to E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 5.

b.

Pressure - STABLE AT OR b.

IF pressure s 2250 PSIA TRENDING TO 2250 PSIA and decreasing, THEN

1) Verify PZR PORVS closed.

IF NOT, THEN manually close.

IF any valve can NOT be closed, THEN manually close its block valve.

2) Verify PZR spray valves closed.

IF NOT, THEN manually close.

IF valve (s)

[-s}

can NOT be closed,

\\- /

THEN stop RCP(s) supplying failed spray valve (s).

3) Verify PZR heaters on.

IF NOT, THEN manually turn on.

IF pressure > 2250 PSIA

)

and increasing, THEN

1) Verify PZR heaters off.

IF NOT, THEN manually turn off.

2) Control pressure using normal PZR spray.

IF NOT available and letdown is in service.

THEN use auxiliary spray.

IF NOT, THEN use one PZR PORV.

O C/

CPM 641 3-44

REACIOR TRIP RESPONSE E0P 35 ES-0.1 Page 7 Rev. 3

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT ORTAINED 6

Check SG Levels a.

Narrow range level > 4%

a.

Maintain total feed flow

> 525 gpm until narrow range level > 4%

in at least one SG.

b.

Control feed flow to b.

IF narrow range level in maintain narrow range any SG continues to level between 4%

increase, THEN stop feed and 50%

to that SG.

7 Verify all AC Busses -

Perf orm the following ENERGIZED BY OFFSITE POWER a.

IF necessary, THEN verify diesel generatore have assumed the foll wing loads.

1) Service Water Pump
2) RPCCW Pump
3) Charging Pump
4) AFW Pump (s)

('~'s

5) Aux Bldg Filter Exhaust Fan

(

6) Containment Air Recire Tan b.

Try to restore offsite power

1) Identify tripped fault relays and attempt to CLOSE RSSA or NSSA feeder breakers to AC busses c.

IF necessary, THEN manually load the following equipment on the AC emergency busses

1) Instrument Air Compressor
2) Spent Fuel Pool Cooling Pump
3) PZR Backup Heaters
4) Fuel Bldg Exhaust Fan d.

Energize MCC 32-3T and verify it is supplying Inverter 6 C PK68-t 3 64

REACTOR TRIP RESPONSE E0P 35 ES-0.1 Page 8 Rev. 3 7s I

$,)

STEP ACTION EXPECTED RESPONSE RESPONSE NOT OSTAINED 8

Establish SG Pressure Control IF condenser NOT available, Mode THEN dump steam to atmosphere.

a.

Establish no demand signal on Steam Pressure Controller output.

b.

Transfer condeaser Steam Dump to Pressure Control

Mode, c.

Verify Steam Dump Interlock Selectors - ON d.

Adjust Steam Pressure controller to 1092 PSIG, if necessary.

4 l

CPSOM 1 3 64 i

s REAC10R TRIP RESPONSE E0P 35 ES-0.1 Page 9 Rev. 3 7.--

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ACTION / EXPECTED MESPONSE RESPONSE NOT OBTAINED STEP

==

NOTE RCPs should be run in thd following order of priority (2,1, then 3 or 4) to provide normal PZR spra 9

Check RCP Status - AT LEAST Try to start one RCP ONE RUNNING a.

Establish conditions for starting an RCP

1) Refer to OP-3301D, RCP OPERATION b.

Start one RCP.

IF an RCP can NOT be starte3, THEN verifi~ natural circulation.

1) RCS subcooling based on core exit TC

> 30*F

2) SG pressures - STABLE OR DECREASING
3) RCS hot leg wide range temperatures - STABLE f__/

'i OR DECREASING

4) Core exit TCs - STABLE x__

OR DECREASING

5) RCS cold leg wide range temperatures -

AT SATURATION TEMPERATURE FOR SG PRESSURE IF natural circulation RDT verified, THEN Iiic~rease dumping steam.

10 Check If Source Range Detectors Should Be Energized a.

Check intermediate range a.

Continue with Step 11.

flux < 10E-10 amps WHEN flux < 10E-10 amps, 1"tERdoSteps10bandc.

b.

Verify source range b.

Manually energize source detectors - ENERGIZED range detectors or use Post Accident nuclear instrument monitors.

c.

Transfer nuclear recorders

(' S to source range scale.

b OPW681 1 84 I

l XLALAUM IKIF KtbFON5E E0P 35 ES-0.1 Page 10 kev. 3 Ysl STEP ACTK)NiEXPECTED RESPONSE RESPONSE NOT ORTAINED 11 Shut Down Unnecessary Plant Equipment 4

a.

Place the steam plant in a shutdown lineup per AOP 3550, TURBINE /

GEKERATOR TRIPS b.

STOP dilution if in progress c.

Turn OFF and bypass BTRS d.

If desired, trip the TD Feedwater Pump (s) e.

If desired, isolate the SJAE (s) f.

If desired shutdown operating evaporators (i.t. boron recovery, radioactive liquid waste, degasifier, etc.)

g.

If desired, start an auxiliary boiler and shift auxiliary steam

/

loads to the auxiliary

( )%

boiler per OP-3331A AUXILIARY BOILER, STEAM AND CONDENSATE.

h.

IF condenser vacuum is not to be maintained, THEN break condenser vacuum per OP-3329 CONDENSER AIR REMOVAL and OP-3323D GLAND STEAM AND EXHAUST.

CPkV44 3 64

KEAGIGH TRIP RESPONSE E0P 35 ES-0.1 Page 11 Rev. 3 t'w/

STEP ACTHM4/ EXPECTED RESPONSE RESPONSE NOT OSTAINED 12 Maintain Stable Plant Conditions a.

PZR pressure - AT approximately 2250 PSIA b.

PZR level - AT approximately 25%

c.

SG narrow range levels -

BETk'EEN 4% AND 50%

d.

RCS average temperature AT approximately 557'F e.

Review the status of all control board annunciators and control systems.

Report abnormal conditions to the SS.

f.

Verify security has checked all SLCRS doors - CLOSED s.

13 Determine If Cooldown Is Desirei a.

Verity all AC busses-a.

IF offsite power cannot ENERGIZED BY OFFSITE be restored, THEN perform POWER an RCS cooldown per EOP 35 ES-0.2 NATURAL CIRCULATION C00LD0%N, to establish the following conditions:

i

1) RCS temperature <400*F
2) RCS pressure >700 psia
3) Accumulator isolation valves - OPEN
4) Cooldown rate <100'T/hr b.

Cooldown is desired b.

Maintain plant conditions in hot standby.

Calculate Shutdown Margin, per OP-3209B, REACTIVITY CALCULATION -

SHUTDOWN MARGIN.

OU OPSV41 3-44

REACIOR TRIP RESPONSE E0P 35 ES-0.1 Page 12 Rev. 3 iv STEP ACTION / EXPECTED MESPONSE RESPONSE NOT OBTAINFD c.

At least one RCP c.

Go to E0P 35 ES-02, can be operated NATURAL CIRCULATION COOLDokN d.

Go to OP-3208, PLANT COOLD0k'N FINAL r

a i

CNeo 1 3 to

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