ML20205A334

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Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery
ML20205A334
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 08/03/1988
From: Brinkman S, James Smith
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-2526, NUDOCS 8810250477
Download: ML20205A334 (19)
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Text

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  • E STATION PROCEDURE COVER SHE_ET A. IDENTIFICATION Number $E0P2526 Rev. 2

Title:

REACTORTRIPRE(9VERY Prepared By: S. crinkman

8. REVIEW I have reviewed the above procedure and have found 4t to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT NEAD M3*[fl en w.

u a unaut siasi t

1 C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

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

YES [ ] NO  %

(If yes, perform written USQ determir.ation and Safety Evaluation, and contact Msnager, St.fety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO%

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

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO%

F. PROCEDURE REQUIRES PORC/50RC REVIEW I

(In addition to review, items with a YES response must be documented in the PORC/SORC meeting minutes.) YES ] NO 1. ]

G. PORC/SORC APPROVAL PORC/SORC Meeting Number 25Nf3)

H. APPROVAL AND IMPLEMENTATION The attached procedure is hereb) approved, and effective on the dcte below:

% s / d ~ . __ eh/cr Effective Date Station / Service / Unit EpFh lendent O

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SF301/9/s/SES/87-12/lof1 gggoyDb 3 P .

_. - , . - = _.. _ ..- - __ . .

_ _ _ . . - _ . - . _ - . . _ . . . =

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REACTOR TRIP RECOVERY  !

Page No. Eff. Reva 1 13 2 i

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@ E0P 2526 Page 1 Rev. 2

D REACTOR TRIP RECOVERY ,

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1. PURPOSE To provide the subsequent operator actions which must be -

accomplished after the standard post trip actions have been l accomplished. The actions in this procedure are necessary to ensure the plant results in a stable safe condition.

2. ENTRY CONDITIONS
a. The Standard Post Trip Actions have been performed

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b. Plant conditions indicate that Reactor Trip Recovery is appropriate. I f

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E0P 2526 Page 2 i Rev. 2 l

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i x,) 3. OPERATOR ACTIONS NOTE Steps 3.1 through 3.4 should be performed by the Primary Plant

. Operator. Steps 3.5 through 3.13 should 'e performed by the Secondary Plant Operator. Steps 3.14 through 3.19 should be performed by the SS/SCO. The three designated operators perform their assigned actions in parallel.

PRD%RY PLANT OPERATOR Instructions Contingency Actions 3.1 Verify pressurizer pressure 3.1 trending to 2225-2300 psia (CO3) a. Manually control heaters and spray (CO3)

()

(m,/ and

b. If pressurizer pressure control is lost, Then refer to Functional Recovery of RCS Inventory and Pressure, E0P 2540C 3.2 Verify pressurizer level trending 3.2
a. Manually control to 35-45% (CO3) charging and letdown (CO2) and
b. If pressurizer level control is lost, Then refer to Functional Recovery of RCS gg Inventory and

\s_)

Pressure, EUP 2540C E0P 2526 Page 3 Rev. 2

O b) Instructions Contingency Actions 3.3 Maintain VCT level 72-86% (CO2) 3.3 Restore level per Volume Control, OP 2304C 3.4 Ensure wide range power 3.4 Continue with this indication procedure

a. Verify reactor power between 5% and .5 cps and decreasing (C04/RPS channels A-0) and
b. When the count rate falls below .5 cps for any channel, ,

.Then reconnect that channel's '

source range detector by depressing the "source

, range on-off" pushbutton

(RPS A-0)

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! (j E0P 2526 Page 4 l Rev. 2

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3 Instructioy Contingency Actions SECONDARY PLANT OPERATOR 3.5 Verify stesm dump and bypass 3.5 Manually operale valves  !

or atmospheric dump valves (C05) I are functioning to 'estore

{

RCS Tavg to 530-535  ;

(C04/5) r CAUTION Do not overreact to low steam generator level. Aad feedwater slowly to avoid . ,

a, excessive pressurizer level and pressure trans1eilt,

b. excessive cooldown rate.
c. overfilling steam generators.

O

_ _ 3.6 Verify steam generator water level 3.6 trending to 70-80% (C05) a. Adjust main or auxiliary feedwater flowrate (C05) 9.E

b. If main and auxiliary feedwater are lost, Then go to Loss of All Feedwater, E0P 2537 -

O E0P 2526 Page 5 Rev. 2

hO Instructions Continaency Actions 3.7 Remove or place in service CPF 3.7 Continue with this domineralizers as necessary to procedure maintain 1300-3000 gpm through each operating domineralizer (local) 3.8 If,using auxiliary feedwater 3.8 Continue with this system Then switch to auxiliary procedure chemical addition per Secondary Chemical Addition OP 2339 (local) 3.9 Ensure CST level greater than 3.9' Replenish per Condens, ate 70% (C05) Storage and Transfer, OF 23198 3.10 Record and Reset all relay 3.10 Continue with this target drop (C09R) procedure 3.11 Verify generator field and exciter 3.11 Continue with this field breakers are open (C07) proce* <

3.12 Verify safe coastdown of Turbine 3.12 Do the following generator by

a. Main turbine turnirg gear a. Manua11y start oil pump auto start (C07) turning gear oil pump (C07)
b. Motor suction pump auto b. Manually start motor start (C07) suction pump (C07)
c. Lift pumps aufo start (C07) c. Manually start lift pumps (C07)

O E0P 2526 Page 6 Rev. 2

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Instructions Contingency Actions

d. Turning gear motor auto d. Manually start start and engages after turning gear (C07) i turbine comes to rest (C07) t
e. Manually engage  !

I turning gear (C07) 4 l

NOTES

1. Turbine should be reset as soon as conditions permit to i minimize possibility of intermediate stop valve binding.
2. EHC pump discharge relief valves are set at approximately
  • 2000 psig, ,

. r a 3.13 Cycle intermediate stop valves 3.13 g intermediate stop by the following: valves do not open, Then provide additional

a. Verify no more than 1 CEA EHC pressure by the ,

O not inserted (C04) following:

b. Verify RPS trips are clear a. Note EHC pressure (RPS) (local)  !
c. Reset and close TCBs (C04) b. Loosen lock nut on l the pressure
d. Record and reset EHC first compensator (local) hit panel (local) ,
c. Turn compensator
e. Obtain switching order from clockwise until l CONVEX. pressure is l 1900 psig (local) i i

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d. Repeat intermediate f

stop valve stroke j procedure l O E0P 2526 Page 7 L

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(3 Instructions

() Contingency Actions -

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f. Open and Block M0015G-2X1-4 e. Return EHC pressure (Unit #1/ local) to noted value (local)
g. Manually reset the following Turbine Protection relays (C07R)
1. 86G1A/15G-2U
11. 86G2A/15G-20 1

111. 86G18/15G-20 l iv. 86G29/15G-2U

h. Push turbine "Reset" e pushbutton (C07)
1. Verify intermediate step q valves stroke to full open position (C07) l
j. Close 15G-8T-2 (Unit 1) l l k. Close 15G-9T-2 (Unit 1) i l 1. Push turbine "Trip" pushbutton (C07) j l

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E0P 2526 Page 8  ;

Rev 2  !

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Instructions Contingency Actions SS/SCO 1

3.14 h r h that Standard Post Trip '3.14 Perform Standard Post Ar.tions, ECP 2525, have been Trip Actions, E0P 2525 performed l

CAUTION I SS/SCO must be notified immediately of .iny safety function 4

criteria not satisfied.

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3.15 Perform Safety Function Status 3.15 H safety function Checks status check criteria are not satisfied, Then

a. Complete OPS Form 2526-1 at i O approximately 10 minute a. Diagnose problem intervals until plant and to to appropriate conditiors stabilize E0P l and i. Many break is l b. Direct STA qualified suspected, Then

! individual to review data refer to Break and verify acceptance Identification criteria are satisfied Chart, Figure 4.1 to assist j in diagnosis.

! and

11. Go to appropriate break E0P l E d-I

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} FJP 2526 Page 9 Aev. 2 A

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( ) Instructions ContingencV Actions

b. Ifdiagnosisofone event is not apparent.

Then go to Functional Recovery, E0P 2540.

NOTE

1. The pre post trip report will automat.ically be printed on the computer room printer 15-20 minutes after the trip.

Ten minutes after being demanded, the sequence of events reports will begin printing and will take 15 to 20 minutes to print on the computer room printer.

3.16 Determine cause of reactor trip 3.16 Continue with this

a. Review computer Pre-Post procedure Trip report (analog)

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b. Mark all control room

(\~- recorders to facilitate later review

c. Direct Outy Officer to complete Duty Officer Requirements After a Trip or ESF Actuation, OP 2671 E0P 2526 Page 10 Rev. 2

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t/ Instructions Contingency A::tions

d. When the Sequence of Events Report is completed. Then reset the data gathering flag by performing the following:
1) Press the "REPORTS" key on ar'y IDT membrane keypad to obtain the report menu.
2) Move the tab to select the "DIGITAL SEQUENCE OF EVENTS" report.
3) Press the "ENTER" key on .

the IDT keyboard.

4) When the SOE menu appears, Then press the "F" key, the O "RETURN" key and finally the "ENTER" key.
5) Mike sure that tne following message appears at the bottom of the CRT screen before clearing the screen:

"SOE gathering flag has been reset."

3.17 Fill out Station Form SF-10.01, 3,17 Conting with this Plant Incident Report, per procedure l ACP-QA-10.01 l

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%w EUP 2526 Page 11 Rev. 2

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(./. Instructions

  • Contingency Actions 30,,I,[

Iodine ar.u'ysis required within 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after reactor trip if power level was greater than 15% at time of trip.

3.18 Direct 'hemistry to perform 3.18 Not Applicable the following analyses 1

a. Iodine Isotopic (primary)
b. Iron (secondary) ,
c. Chlorides (secondary)
d. Conductivity (secondary) ,
e. Boron (primary) *
f. Activity (if leak suspected)
4. FIGURES 4.1 Break Ident'1fication Chart

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FIGURE 4.1 g

BREAK IDENTIFICATION CHART L)

INITIAL CONDITION: PRESSURIZER PRESSURE DECREASING EITHER YES S/G PRESSURE NO

<S00 psi?

CONTAINMENT YES NO PRESSURE INCREASING 7 CONTAINMENT YES NO PRESSURE '

INCREASING 7 . ,

SECONDARY SECONDARY SJAE BREAK BREAK OR BLOWOOW'i p/

-u INSIDE OUISIDE NO RAD M0fi! TORS YES CONTAINMENT CONTAINMENT ALARit!NG7 PRIMARY PRIMARY BREAK BREAK INSIDE OUTSIDE CONTAINMENT CONTAINPENT I 1 E0P 2536 E0P'2532 E0P 2534 EXCESS LOSS OF STEAM GENERATOR STEAtt PRIMARY TUBE RUPTURE DEPAND COOLANT UNIQUE SYMPTOMS:

.EITHER S/G PRESSURE LOW

  • HI RAD IN CONTAINMENT .H! RAD IN SECONDARY OR AUX BUILDING PLANT

.NO RAD INCREASE

.NORt%L CONTAINMENT CONDITIO!!S O 20P 2526 Page 13 Rev. 2

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, _ FORM APPROVED BY STATION SUPERINTEl&ENT EFFECTIVE DATE PORC MTG NO.

REACTOR TRIP RECOVER,Y l'(") SAFETY FUNCTION STATUS CHECK MOTES:

1. The purpose of this form is to ensure that all necessary information is reviewed wnen using E0P 2526, Reactor Trip Recov,ery. The safety ,

function statas check verifies by indepen'Jent assessment that the operator is using the correct procedure. It also assures that the procedure is satisfying all relevant safety functions and maintaining adequate core cooling.

2. Safety function status is considered satisfied when all of the parameters of any one condition meet their criteria. .
3. With the int 1 grated compute,r system functional, the' safety function status may be determined from the SPOS displays. The SS/SCO shall ensure the correct recovery E0P number is selected at the SPOS CRT. The safety function status should be logged below approximately every 10 minutes until plant conditions stabilize.

Safety Function Status (YES/NO)

Reactivity Inventory Pressure Heat Removal ,

Containment Integrity _

Vital Auxiliaries Time 4 If the integrated computer system is nA functional, then completion of the rest of this form is necessary at approximately 10 minute intervals until the plant conditions stabilize.

5. Parameters marked with an asterisk require meter readings to be logged.

All other parameters are responded to by yes or ne.

OPS Form 2526-1 Rev. 2

., Page 1 of 5

REACTOR TRIP RECOVERY

[)

gj SAFETY FUNCTION--STATUS CHECK CAUTION SS/SCO must be notified immediately of any safety function critaria nct satisfied.

TIME /0ATA ACCEPTANCE PARAhi!..; CRITERIA / / / / / / /

1. REACTIVITY CONTROL Condition 1 - CEAs Inserted
a. Reactor Power a.

f; (C04) 1. < 5%

_and ii.Decreasi g

b. CEA Position b. No more than _ __

(C04) one CEA not inserted OPS Form 2526-1 Rev. 2 Page 2 of 5 -

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'1.'337

1 m ACCEPTANCE I ) VARAMETER CRITERIA DATA .

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'l REACTIVITY t.ONTROL (conti Condition 2 - Boration

a. Reactor Power a. .

(C04) 1. < 5%

and ti. Decreasing 6

b. BAST level b. A l

(C02) 1. level B .

decreasing" (adding boron to RCS) .

O 11. shutdown

=

margin established per OPS Form 2208-13

2. RCS INVENTORY CONTROL
a. Pressurizer level a.

(CO3) 1. 20-65%*

and

11. Trinding l to 35-45%  :

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l b. All RCS Subcooling b. > 30'F* __ l

, (ICC cabinets)

OPS Form 2526-1 Rev. 2 Page 3 of 5

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f- 3 ACCEPTANCE f i PARAMETER CRITERIA DATA

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3. RCS PRESSURE CONTROL
a. Pressurizer Pressure a. 1900-2350 psia
  • _ _

(CO3) and

b. Trending to 2225-2300 psia 1

4, RCS HEAT REMOVAL

a. RCS Tavg a. 530-550*F*

(C04) .

b. Steam Generator b.

Level (Feed Flow)

(C05) 1. 10-80%* A, f) and B Trending to 1, 70-80% B_ , _ , . _

E it.i&eu flow A 1 __

c. Steam Generator c. 880-1050 psia
  • A Pressure (C05) B
d. CST level (C05) d.
i. > 70%*

E

11. Action being taken to restore level __

OPS Form 2526-1 Rev. 2 Page 4 of 5 YL 11; ' . '

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ACCEPTANCE l
y PARAMETER CRITERIA DATA  ;

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5. CONTAINMENT INTEGRITY 3
a. Containment f Pressure (Col) < 2 psig _ l I Sump Level (C06) no abnormal 1

. Increase

Normal Radiation (RC14) < alarm ,

setpoint f l  !

I b. Secondary Plant Radiation

< alars f SJAE(RC14) _

f setpcint ,

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! Blowdown (R*14) < alarm l

setpoint  ;

) Main Steam Line (RC05E) < alarm [

- setpoint .

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c. Stack Radiation j

i Unit 1 Wide Range < alarm (

setpoint l

Unit 2 Wide Range.(C101) < alarm  !

l i 1etpoint

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p VITAL AUXILIARIES l

6. i

, a. Buses, 24C and 5. Energized i f

, 240 (C08) a l I e i b. Buses, 201A and b. Energized i l 2018 (C08) f,

c. Instrument Air c. > 90 psig ,

j Pressure (C06) {

lO i OPS Form 2526-1 k

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. Rev. 2 i Page 5 of 5 l i

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