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Text

Rev 0 to GP-2, Normal Plant Startup
	ML20096F714
Person / Time
Site:	Limerick
Issue date:	08/31/1984
From:	Leitch S; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20096F678	List: ML20096F673; ML20096F695; ML20096F706; ML20096F714; ML20096F726;
References
	GP-2, NUDOCS 8409100186
	Download: ML20096F714 (29)
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r P

EXHIBIT 4 GP-2 Rev. O Paga 1 of 29 s

GJM/sm PHILADELPHIA. ELECTRIC ' COMPANY '

LIMERICK GENERATING STATION GP-2 NORMAL PLANT STARTUP 1.0 PURPOSE The ourpose of this procedure is to provide the proper secuence of operations to start up a unit and its associated auxiliary systems f rom a shutdown and cooled down condition to rated power output.

2.0 PREREOUISITES 2.1 Applicable portions of GP-1, Preparations for Plant Startup, completed as recuired by plant management.

Obtain approval for startup from Station Superintendent or alternate, and affix Attachment I (from Appendix I to GP-2)-to the front of this procedure.

2.2 The plant should be basically in the following conditions prior to a startup' (this list serves as a reminder and is flexible at the discretion of shif t supervision):

2.2.1 Control room, annunciators

/

operable.

Initial Date 2.2.2 No battery ground indications.

/

Initiil Date 2.2.3 No significant control room

/

instrumentation problems.

Initial Date 2.2.4 Schuylkill River and/or Perkiomen Creek makeup systems available, traveling screens

/

operable, and trash bins empty. Initial Date

[

h I,8f/

2.2.5 Service Water h

operation pe S10.1.A.

igdi.tial Date j

B409100186 840831

' ' k' b

DR ADOCK 05000

GP-2 Rev. O Page 2 of 29 GJM/sm 2.2.6 Air ejecto,rs and off-gas

/

Initial Date system available.

2.2.7 CRD system in normal operation.

/

as per procedure S46.1.A.

Initial Date

'2.2.8 Standby liould control ocuib

/

monitors lighted.

. Initial Date 2.2.9 TECW and RECW operational per procedures S14.1.A

/

and S13.1.A, res pecti vely.

Initial Date 2.2.10. Drywell floor drain and eauipment drain system

/

Initial Date i

operational per S61.1. A.

2.2.11 At least two instrument air compressors available or operating per procedure

/

Initial Date S15.1.A.

2.2.12 Reactor Water Cleanup System 4-in operation per procedure

/

Initial UEET S44.1.A.

2.2.13 Cooling tower available.

/

Initial Date 2.2.14 SGTS and reactor enclosure ventilation normal, with reactor enclosure slightly negative 4

in - pressur e (between 0

/

and -0.25 inch water).

I ni ti al DaTF 2.2.15 Drywell coolers in service

/

j.

per procedure S77.1.A.

Initial Date 2.2.16 One drywell chiller and one chilled ' water pump operating

/

Initial DiEI

[

per procedure S87.1.A.

l 2.2.17 Main Steam Line Radiation

[

Monitors not.known to be

/

a Initial UEEE 6

i inoperabl e.

~.:'

GP-2 Rev. O

[.

Paga 3 of 29 GJM/sm 2.2.18 Process liquid monitors valved in service and operating i

per the appropriate system

/

26 operating procedures.

Initial Date 2.2.19 Area radiation monitors

/

no rmal.

Initial Date 2.2.20 North and South stack radiation monitors not

/

known. to be inoperable.

Initial Date 2.2.21 Control room and radwaste building radiation monitors not known to be

/

inoperable.

Initial Date 2.2.22 Containment atmosphere sampling system not known to

/

be inoperabl e.

Initial DaEe 2.2.23 Auxiliary Steam System in operation per procedure

/

S21.1.A.

Initial Date 2.2.24 220KV (500 KV) generator output breakers closed with

~s generator disconnect open and blocked to shift supervision.

No lockout

/

relays are tripped.

Initial Date 2.2.25 ECCS panels indicating normal valve lin. -up l

and electrical f eeds on all v.'ves.

Note specitically and ensure that the following conditions

/

exist:

Initial UaEe a.

HPCI and RCIC l:

steam supply valves are closed if reactor pressure j

is less than

/

l 100 psig.

Initial Date-1 w'

e

-,ww

---,,e

-ee m

-=---eer wam

,-a w

--eg

,----w

+

c--wa-w-4ye-weyw----ep, wr*-+w_ era,--re rw m m.,on-.*v<ww-+e-, ems-+sM*rt-w w e e t e

-r-

303ULVVOOV e

GP-2 Rev. O Paga 4 of 29 GJM/ sm b.

Shutdown cooling i

and head spray

/

valves closed.

Initial Date 2.2.26 Bvoass Leakage Barrier Block Valves HV-41-142 (242) and 143 (243) are open and Bypass Leakaoe Barrier Vent Val ves HV-41-140 (240) and 141 (242)

/

are cl os ed.

Initial Date 2.2.27 All main steam relief valve switches are in

/

" AUTO" or "CLOSE".

Initial Date 2.2.28 Process computer is

/

operational.

Initial Date 2.2.29 No abnormal alarm : lights

/

on the Full Core Display.

Initial Date 2.2.30 Instrument nitrogen system should be in operation per S59.1.A with both instrument air

/

~g, backup valves closed.

Initial UEEe 2.2.31 The condensate and refueling water transf er system operational per

/

S08.1.A.

Initial Date 2.2.32 Fire protection system operational per procedure

/

S22.1.A.

Initial UaEF l

2.2.33 Motor operated valves on FW heater dump and drain lines

/

l opened.

Ini tial - Date 2.2.34 Generator stator and l

rotor temperature recorders and generator core monitor

/

operable.

Initial Date

(

i

~

GP-2 Rev. 0 Paga 5 of129 GJM/sm 2.2.35. Sufficient capacity exists

)

in the radwaste system for plant startup.

CST and RWST inventories compatible

/

with startup recuirements.

Initial Date 2.2.36 480 V AC systems

/

lined up per-procedures S93.1.A and S93.1.B.

Initial UEEE 2.2.37 4 KV System lined il up normally per S92.9.A and diesel generators set up for automatic

/

operation per S92.1.N.

Initial UatE 2.~2.38 13 KV System lined

/

up normally per S91.9. A.

Initial Date 2.2.39 RPS/UPS and Computer Static Inverters in service

/

per S94.1.A,B,C.

Initial Date 2.2.40 Emergency Shutdown Panel switches aligned per

/

S88.1.A.

Initial Date

~;

3.0 PROCEDURE This procedure is broken up into five sections, as delineated below.

Entry into the procedure may be made from various plant conditions depending upon previous events.

It is the intent of this procedure to be used for guidance and direction only.

However, when entering into the. procedure at some place other than the beginning, previous-steps should be verified as having been L

accomplished at some earlier time, or as not applicable, before proceeding.

SECTION 3.1 Prior to Reactor Startup SECTION 3.2 Approach to Critical and Heatup to 212 degrees F.

l-SECTION 3.3 Heatup and Pressurization to Rated Temperature and Pre.ssure (Two_ turbine bypass valves open and recombiner in-service).

L l

,.. _,..~ _, _ _.._ _..___ _,._,_._,- _.__.. _._,_,

GP-2 Rev. O Paga i cf 29 GJM/cm SECTION 3.4 Startup and Synchronization of the Unit.

~/

SECTION 3.5 Increasing Power to Rated.

3.1 PRIOR TO REACTOR STARTUP 3.1.1 Verify that Maintenance or other operations which eff ect reactor safety are complete (Work on tech. spec.

/

equipment or instruments).

Initial DaEe a.

I&C Group verify all required surveillance tests

/

are complete.

Initial Date b.

I&C Group verified that instrument valves have been lined up in accordance with

/

approved procedures.

Initial Date c.

If a Safety Relief Valve (s) failed to function as designed as s,

r cause of or during the shutdown prior to this startup, verify

~

that the valve was replaced with a new or reconditioned valve, or that the f ailed L

valve itself was removed from service, disassembled, inspected, adjusted and pressure setpoint tested with steam (NRC IE Bulletin

/

No. 80-25).

Initial Date 3.1.2 Review zil open permits to determine their effect on plant operation (Work on tech. spec. equipment

/

or instruments).

Initial Date i.

.-~......_.-....,-...-,,,,_-..-,,e,----,....-----._.---.--,--._,---

GP-2 Rev. O

~

Paga 7 of 29 GJM/sm Review the Temporary 3.1.3 Circuit Alteration (TCA) Log to ensure that no jumpers are installed which affect

/

safe operation of Initial Date the plant.

3.1.4 Review the Locked Valve Log to ensure that valve positions are

/

satisfactory for plant Initiai DaEE startup.

3.1.5 Review outstanding MRF's to determine their

/

impact on plant Initial Date operation.

3.1.6 Complete GP-1 if required by Engineer-operations or alternate, and file with the startup package.

/

(If not required, mark Initial Date this step N/A.

3.1.7 If shutdown was due to a scram, verify that GP-18 (C.O.L.) has

/

been completed prior Initial UEEE to startup.

3.1.8 Complete ST-6-043-760-1 Recire Pump Disch. Valve Operability if it has not

/

been performed in the Initial Date last 31 days.

l CHECK LIQUID NITROGEN 3.1.9 INVENTORIES.

ORDER LN2 AS NECESSARY TO ENSURE SUFFICIENT QUANTITY TO INERT CONTAINMENT.

CONTAINMENT INERTING MUST

/

BEGIN AS EARLY AS Initial Date l

POSSIBlE PER S57.1.A.

0 s

,-m e-m,e,e,,,,-a

-,e-,--,,,-+--m--

,-m-m-we e.,-

s.

GP-2 Rev. 0 Paga 8 of 29 GJM/ sm 3.1.10 If a dryw, ell entry has been made,-verify es open position for the following locked valves by verifying open indication in the

/

control room.

Initial DIEE a.

51-lF065A,B,C,ED (2F065A,B,C,ED) -

LPlI Injection Block Valves at Panel 10C601

/

(20C601)

Initial Date b.

51-lP077 (2F077) and 51-lF060A & B (2F060A & B) -

Shutdown Cooling Suction and Return Manual Block Valves at ' Panel 10C601

/

(20C601)

Initial UEEE c.

52-lF007A & B (2FOO7A & B) -

.s Core Spray Injection Block Valves at Panel 10C601

/'

(200601 Initial Date d.

48-lF006 (2F006) -

SLC Injection Block Valve at Panel 10C603

/

^

(20C603).

Initial TGRGE 3.1.11 If a drywell entry has been made, perform an alignment of non-automatic containment isolation valves per (GP-1 (COL-3).

If this was already done with GP-1, mark this

/

"N/A".

Initial UEEe

.me

eAgrengassvengng 1

GP-2 Rev. O

{

Paga 9 of 29 GJM/cm 3.1.12 SRM Detectors.

/

Initial Date a.

Ensure that IEC performs the SRM Channel Functional Tests:

ST-2-074 -600-1( 2 ),

601-1(2), 602-1(2)

/

and 603-1(2).

Initial DaEE b.

Verify SRM detecto: s are fully inserted and perform SRM Count Rate Checks,

/ -

ST-6-074-360-1(2).

Initial Date-c.

Indicate any bypassed

- SRM channels:

/

A B

C D

None Initial UEEE 3.1.13 IRM Detectors.

a.

Ensure that IEC performs the IRM Channel Functional Tests:

ST-2-074-608-1(2),

609-1(2), 610-1(2),

611-1(2), 612-1(2) 613-1(2), 614-1(2),.

and 615-1(2).

Ifthe startup exceeds 7 days, these ST's must be performed once

/

per week.

Initial DEEE b.

Verify all IRM detectors are fully inserted, all console recorders are selected to IRM, all IRM range switches are on range 1, and perform IRM Channel

checks,

/

ST-6-107-590-1(2).

Initial Date 4

-='

+w,

-rw.

,,w-r wr-

..w.

w-

,---,..,-,-,,w,

.,,--.we,-.,-<-,--.

v ev e r w -->i w w w-e w yo-e-=w vg-*--e-g-+m>ww-,-g~==-yv-w--,--y w em erp"*

e,,,

GP-2 Rev. O Paga 10 of 29 GJM/sm c.

Indicate any bypassed IRM channels:

A B

C D

/

E F-G H

None Initial Date 3.1.14 APRM Detectors.

a.

Ensure that I&C performs the APRM Channel Functional Tests:

ST-2-074-616-1(2),

617-1(2), 618-1(2),

619-1(2), 620-1(2),

/-

and 621-1(2).

Initial UEte b.

Verify that each APRM,

has the minimum re-quired number of inputs L

per level and total by performing the appropri-ate section of the -

Surveillance Log,

/

ST-6-107-590-1(2).

Initial Data c.

Indicate any bypassed APRM channels:

/

A B

C D

E F

None Initial Date 3.1.15 Verify that all rods that were bypassed on l

the reactor manual control system are unbypassed per

/

procedure S73.0.E.

-Initial UEEE 3.1.16 Verify rod worth minimizer is in service and perform

/

ST-6-073-320-1(2).

Initial UEEE 3.1.17 verify the rod sequence control system (RSCS) is in service and perform

/

ST-6-073-330-1(2).

Initial Date 3.1.18 Verify the rod block monitor (RBM) is operational and ensure IEC performs

/

l l

ST-2-074-622-1( 2)and 623-1( 2). Initial Date m.+

f 1

GP-2 Rev. 0-Paga 11 of 29 GJM/cm 3.1.19 Verify _all operable control rods are fully inserted and that the rod position indication system is operational by performing

/

ST-6-107-320-1(2).

Initial Date-3.1.20 Ensure that Maintenance performs ST-4-lO7-950-1(2) to verify the CRD housing

~

support is in place after

/

1 any disassembly.

-Initial UEEe 3.1.21 Verify the ADS system including the safety relief valves are operable by

/

performing ST-6-050-760-1(2).

Initial Date 3.1.22 When both reactor recirculation pumps are operating, verify all jet pumps are operable by

-/

performing ST-6-042-360-1( 2).

Initial UEEF 3.1.23 verify that the reactor coolant is being sampled per RT-5-000-014-0 and that the chemistry meets the specifications of

/.

ST-5-041-800-1(2).

Initial Date 3.1.24 Verify the offgas system hydrogen analyzers are in normal line-up and place in service per procedures S69.1.B and

/

S69.1.C.

Initiir DEEe 3.1.25 Prior to drywell closeout, have shif t supervision perform an inspection to verify:

l a.

All insulation in place.

b.

All soaffolding removed.

c.

No foreign material in drywell.

l l

GP-2 Rev. O Pagn 12 of 29 GJM/ cm All temporary shielding d.

removed.

General cleanliness.

e.

Undervessel platform f.

locked in position

_/

appropriate for Initial Date reactor operation.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of 3.1.26 closure, perform a leak test of the primary containment air locks per If ST-1-060-320-1(2).

maintenance was performed on

/

the airlock, use Initial Date ST-1-060-470-1(2).

S F_

APPROACH TO CRITICAL AND HEATUP TO 212 3.2 Place the circulating water 3.2.1 including two

system, in cire, wtr

pumps, operation per procedure Place the

/

SO9.1.A.

water box scavenging system Initial Date in operation per 809.8.A.

Verify the Main Steam to

/

Hotwell Steam Spargers Valve Initial Date 3.2.2 HV-01-109(209) is closed.

Verify the main condenserHV-07-142(242),

3.2.3 vacuum breakers, 143(242), 144(244), and 145(245),

and the steam packing l

exhauster steam inlet valves, I

B ( 240A,B), are l

HV-07-140A, Verify the mechanical closed.

vacuum pump and the steam

/

packing exhauster blowers are Initial Date I

"OFF."

Fill and vent the condensate

_/

3.2.4 and feedwater systems Initial Date per procedure 805.3.A.

,.,.w-.

.--,n,,,,e,,,-,m,

,, - _,, - - +, -.,,,,,

h' 3830200880

-~

GP-2 Rev. 0-Paga 13 of 29 GJM/cm 3.2.5 Place the' condensate system in operation with one cond.

/

pump running per S05.1.A.

Initial UEEe 3.2.6 Verify the RFP and reactor vessel level controllers are in " MANUAL" with bias adjusts set

/

at 50%.

Initial UEEe t

3.2.7 Place the feedwater system in long path recirculation and flush all piping and components per procedure

/

S06.5.A.

Initial UEEE 3.2.8 Verify the reactor. node switch is in " SHUTDOWN"

./

or " REFUEL".

Initial UEEE 3.2.9 Verify the " Discharge Volume Hi Water Bypass" key switch

/

is in " NORMAL".

Initial UEEE 3.2.10 Operate the NSSSS isolation reset switches to ensure NSSSS logics are reset

/

and alarms have cleared.

Initial Date i

3.2.11 Verify the master recirculation flow controller is in " MANUAL" and set at minimum

/

U output.

Initial Date 3.2.12 Place the reactor recirculation system in operation (with both recire. pumps, if possible) per procedure

/

S43.1.A.

Initial UEEE 3.2.13 Perform Operational Hydrostatic Test per GP-lO as necessary.

Excess flow check valve testing and scram time testing may also be

' performed at this time

/

if necessary.

Initial Date

-m a e

a m.-

w m

e n--

,w--w-,---ewr,.,

-w*-

y e-.----.c.--.e3-w9.-gr.-r-e-+nwwy--g3y,e-ms.,,gw wy,eggmvwy -,3% mw w-,me-v - rw +- - my ww. qey-e.,,

09 d WCA V U 99 M

~~~~ ~

GP-2 Rev. 0 Paga 14 of 29 GJM/cm 3.2.14 Verify the reactor head

-vents, HV-41-lF001 (2F001) 1F002 (2F002),'lF005 (2F005) are open.

If the MSIV's are open, the pre-ferred vent path is through IP005 (2F005) to the

/

main condenser.

Initial Date 3.2.15 Verify the Main Steam Line Drains.HV-41-lF016 (2F016),

1F019 (2F019), 1F020 (2F020)

/

and IF021 (2F021) are open.

Initial Date 3.2.16 Place the other tao circulating water pumps in service to ensure their

/

operability early.

Initial Date 3.2.17 Startup the. Steam ; Seal System per procedure S37.1.A and establish main turbine seals.. Seal the RFP turbines by opening the 1A, B, C (2A, B, C) RFPT Steam Seal Admission MOV's HV-07-110A, B, C (210A, B, C) and opening each RFPT Exhaust Valve, HV-06-116A, B, C

/

(216A, B, C).

Initial UEEe 3.2.18 Commence drawing a vacuum with the air ejectors supplied from auxiliary steam (per procedure SO7.1.C) or-with the mechanical vacuum t

pump (per procedure S07.1.B).

Place the Recombiner and the Charcoal Delay Offgas Systems in service per procedure S69.1.D and S70.1.C,

/

respecti vely.

Initial DEYe 8

'.h

--,--e-~--

u--

.3830200880 GP-2 Rev. O Paga 15 of 29 GJM/sm 3.2.19 commence ' containment inerting per procedure S57.1.A so that oxygen concentration is L-less than four percent by volume within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of placing the Reactor Mode

/

Swi tch into "RUN".

Initial DaEe 3.2.20 Verify or place the Reactor

/

Mode Switch in "STARTUP".

Initial Date

[

VERIFY THE REACTOR COOIANT SYSTEM TEMPERATURE AND PRESSURE ARE WITHIN TECH. SPEC. LIMITS BY PERFORMING ST-6-107-640-1( 2) WITHIN 15 MINUTES

,~

PRIOR TO CONTROL ROD WITHDRAWAL AND DURING THE SYSTEM HEATUP.

3.2.21 When the "RNM Rod Seqpence" for startup has been received from the Reactor Engineer or alternate, make the following announcement over the plant public address system:

" UNIT ONE (TWO) REACTOR IS READY FOR STARTUP.

90D WITHDRAWAL WILL BEGIN IN

/

TWO MINUTES."

Initial Date i

~-

3.2.22 Commence rod withdrawal in accordance with the "RWM Rod Sequence" for startup.

Take the reactor critical and commence adding heat per

/

t~

Appendix I to GP-2.

Initial DEEe FOLLOW BOTH PROCEDURES GP-2 AND GP-2, APPENDIX I CONCURRENTLY.

3.2.23 Close or verify closed the reactor head vent to CRW valves HV-41-lFOO1 (2F001) and 1FOO2 (2F002) before o

reaching a vessel water

/

temperature of 200 degrees F.

Initial Date w

..-_____ _____,.~ _ _._ _ _ _.._____.-_ _.__._. _.. _ _ _ _ _ _. _ _

~

3830200880 GP-2 Rev. O Paga 16 of 29 GJM/sm 3.2.24 continue ' rod withdrawal until 212 degrees F has been reached and the console reactor pressure indicators begin to

/

respond.

Ynitial-Date HE' TUP TO RATED TEMPERATURE AND PRESSURE

3. 3 -

A Plant status is the same as.in the beginning of Section 3.2 with the following additions:

the reactor is critical at 212 degrees F, the head vents to CRW are closed, the SRM's are withdrawn, the IRM's. are nominal midscale on range 8, all four circulating water pumps are running, condenser vacuum is established, the main and RFP turbines are sealed, and the mode switch is in "STARTUP".

IRM RESPONSE TO INDIVIDUAL ROD WITHDRAWAL IS LOCAL -

AND RATHER SLOW UNTIL A " BLACK AND WHITE" ROD PATTERN IS REACHED.

WHEN THE FIRST INTERIOR ROD IS WITHDRAWN AFTER-ACHIEVING A BLACK AND WHITE PATTERN, IRM RESPONSE IS SIGNIFICANTLY MORE PRONOUNCED, AND RODS SHOULD NO LONGER BE FULLY WITHDRAWN IN THE CONTINUOUS NOTCH OVERRIDE MODE.

3.3.1 Continue rod withdrawal and maintain slightly less than 100 degrees F/hr

/

heatup rate.

Initial Date 3.3.2 Prepare the main turbine for operation per procedure

/

S01.1.A.

Initial URT FOLLOW S01.1. A CONCURRENTLY WITH GP-2.

d I

s e

A.

'w--we-e---ee-%

y-rN#em--g v

weg t-eeowp e.vywsgmyw+rw-t==-twow w w---umr mwwww we -t w w w yw

-3 ww we V dMNNT-we'e-1*r**"*-'

W wpyin y-,

w-g-+-er---

y.----ww-wn+4---*--w,,,

--L-te*Nasw ++mer-e e

3830200880

'GP-2 Rev. O Page 17 of 29 GJM/sm 6

3.3.3 Place the main steam.

to Hotwell Steam Spargers in service by opening HV-01-109 (209) and by opening the controllers HV-C-05-110A,B,C (210A,B,C) as necessary to maintain respective condenser dissolved oxygen concentration within the limits

. prescribed by the plant chemist.

This can be monitored in the MCR on Panel 10C652 (20C652) at ARSH-23-110 ( 210) but.

should be backed up by periodic sampling and analysis.

(

References:

Letter entitled Deaerating Assist Steam Spargers",

D.A. DiPaolo, 7/4/83, File:

Equip 1-12-5; GE SIL No.136, Supplement 3,'

Revision 1

/

Appendix A).

Initial UEEe 100 psig

'3.3.4 As soon as the 100 psig isolation resets on the HPCI turbine, open the steam supply valves to both the HPCI and RCIC turbines slowly.. Attempt to minimize thermal shock to the piping by pressurizing the steam supply lines through the warmup valve, over a nominal half hour period, per procedures

/

S55.1.B and S49.1.B.

Initial UEEE i

O Y

l l

i l

l i

~

GP-2 Rev. O s

Paga 18 of-29 s

GJM/cm

_f 3.3.5 When reactor vessel level

~

can no longer be maintained by CRD and RWCU systems, secure the RWCU blowdown flowpath by closing the Dump Valve Manual control Valve HV-C-44-1F033 (2F033) and the Discharge to Main Condenser Valve HV-44-lF034 (2F034) or the Discharge to.Radwaste Valve HV-44-lF035 (2F035), i f applicable.

Close. the Orifice Bypass Valve'HV-44-lF031 (2F031),

if open.

Ensure the RWCU Return Shutoff Valve HV-44-lF042 (2F042)is full open to return all RWCU flow to the

/

y I

reactor vessel.

Initial UEEe 3.3.6 If it is desired to manually control RPV level, commence. feeding the reactor through the RFP Startup Bypass Valves HV-C-06-120 (220),

' 06-1019 ( 2019) and.

(06-1C18 (2018).

Modulate HV-C-05-120 (220) as necessary to maintain RPV level at a, nominal

,g 30 inches.

The 1A r (2A) RFP Discharge Bypass Valve LV-C-06-138A ( 238A)

T should be placed in i

" MANUAL" 'and closed to prevent the valve f rom

/

modulating.

Initial Date s

- T

+

1 0

5 r

Y

\\

t

. _. _ _ _ _ -... - -. _.: m _ _... _._. _ _ _..._ _.._......,,_,--_.., -.. - _.____._..___ _,_. _.-

,______.-m

g o gy z y g e c y ;

GP-2 Rev. 0 Pag 3 19 of 29 GJM/sm

3. 3. 7 -

If it is desired to automatically control RPV level, ens ure LV-C-06-13 9A ( 23 8A).

'is in " AUTO", with its setpoint at 30 inches.

This will, allow flow to pass through the 1A (2A) RFP to

/

maintain RPV level.

Initial Date IF SMOOTH OPERATION OF LV-C-06-138A ( 238A) IS NOT IMMEDIATELY EVIDENT, IT MAY BE NECESSARY TO COMROL RPV LEVEL WITH LIC-06-138A (238A) IN " MANUAL" UNTIL A TURBINE 3W ASS VALVE IS AT LEAST 10 PERCE M OPEN.

150 psig 3.3.9 Verify EHC pressure regulator operational by observing bypass valve opening while reactor pressure is maintained

/

at 150 psig.

Initial BaEe 13.3.10 Transf er the operating set of air ejectors steam supply and the recombiner preheater steam supply to main steam per procedures S07.1.D and S69.1.D,

/

respecti vely.

Initial FIEe 3.3.11 continue rod withdrawal to one full turbine bypass valve open if HPCI or RCIC operability test is required (once per-operating cycle).

l Perform these tests per l

ST-6-055-320-1( 2) or ST-6-049-320-1(2) if ne cessary.

If no surveillance is required, proceed to next step as soon as turbine bypass

/

valve. starts to open.

Initial Date P

L l

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3830200880 GP-2 Rev. O Paga 20 of 29 GJM/sm

~i, p

/

R

],

3.3.12 ' Using the' bypass jack, open

' ua one turbine bypass valve 10

,to'20 percent.

Raise the EHC pressure setpoint to 600 psig.

This setpoint ensures that a RFP will be operating

' r prior to reactor pressure 6

. ext:eeding the condensate

/

' pump deliveredy capability.

Initial UEEe 3.3.13' Continue rod withdrawal i

maintaining less than a 100

[

f degrees F/hr heatup

/

. f rate.

Initial Date s\\

c3.3.14 Place isolated phase bus t

w heater in service per procedure S34.1.A and continue preparing s

the turbine generator

/

for operation.

Initial Dafd s.

l j 450 psig

/

, ^'

b.

/

I.

'3.3.15 Start a second condensate 3

pump per procedure

/

,' v.

S05.1.B.

Initial Date

.- /

3.3.16 Start the first RFP in

_ p accordance with procedure 806.1.A and commence feeding

/

1

_the reactor vessel.

Initial Date ENSURE THE FEEDWATER STARTUP -FLUSH VALVES HV-41-lO9A' (.209A) and 109B ( 209B) ARE CLOSED WHENEVER REACTOR PRESSURE IS ABOVE 600 PSIG.

l-(

Reference:

Memorandum entitled " LGS Open Items -

Feedwater Isolation Valves", ' D.

R.' Helwi g, 7/18/83, 3

4

! File:

NUCL 9-6-B).

.3.3.17 ' Start a second RFP per

' procedure SO6.1.A, and place it in " standby"

/

per SO6.1.C.

Initial Date FOLLOW S06.1. A CONCURRENTLY WITH GP-2 FOR GUIDANCE ON n

METHODS OF REACTOR VESSEL LEVEL CONTROL,

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383b200880 GP-2 Rev. 0 Paga 21 of 29 GJM/sm 600 psig 3.3.18 Carefully observe the arri val at.600 psig by an increase in turbine

/

bypass valve opening.

Initial Date

3. h 19 Raise the EHC steam

. pressure setpoint to

/

920-psig.

Initial Date s

3.3.20 Slowly start withdrawing control rods'to increase reactor pressure f rom 600 psig to 920 psig in about

/

one hour..

. Initial UEEE 3.3.21 Verify that the main steam line low pressure annunciators clear

/

at a nominal 831 psig.

Initial Date 920 psig

- 3.3.22 Observe arrival at 920 psig by turbine bypass valve opening increasing.

(

When the bypass valve L

is open 30 to 40 percent, l

set the bypass valve

/

l jack back to zero.

Initial.UKEE 3.3.23 Contirui control rod withdrawal-toward achieving two

/

L bypass valves full open.

Initial DIEE 1 BPV Open 3.3.24 Close the appropriate RFP

/

turbine drains as required.

Initial Date l-g L-L i

i

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

GP-2 Rsv. O Pog2 22 of 29 GJM/cm ingen one and.one-half 3.3.25 turbine bypass valves are open, adjust each APRM channel's indicated power to be ecual to the percent thermal power as cal-culated by 2.8% times the number of bypass valves (e.g. with one open.

and one-half BPVs open:

% Power = 2.8% x 1.5 = 4.2%).

At this time, also veriYy~

that the APRM downscale alarms are clearing

/

and the IRM's read about Initial Date 10% on range 10.

When all APRM downscale 3.3.26 alarm lights have cleared, place the reactor mode switch to "RUN" prior to exceeding the scram setpoints of 15 percent APRM power in "STARTUP" or 120 percent IRM scale.

Ensure reactor pressure is maintained above a nominal

_/

831 psig to prevent Initial Date MSIV isolation.

At the APRM recorders 3.3.27 on panel 10c603 (20c603),

verify "RUN" mode by check-ing the APRM scram / rod block

/

setpoint has changed to Initial Bate the flow biased value. -

2 BPV's Open Pully withdraw the IRM's

/

3.3.28 and secure IRM and SRM Initial DatE detectcr drive power.

m

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.3830200880 GP-2'Rav. O Paga 23.of 29 GJM/ sm 3.3.29 If LV-C-06-138A( 238A), the "A"

RFP Discharge Bypass Valve, is being used to control RPV level, put the " stand-by" RFP in service and place the 1A(2A) RFP in " stand-by" per pro-

/

cedure S06.1.A.

Initial Date 3.4 STARTUP AND SYNCHRONIZATION OF THE MAIN UNIT Plant'is n'ow in "RUN" mode, IRM's withdrawn,-two turbine bypass valves open, two condensate pumps running, two reactor feed pumps running, turbine chest warm, recombiner in service, and drywell inerting is in process.

3.4.1 Notify the Load Dispatcher of expected synchronization and request permission to open both the 535 (235) and 635 (335) breakers

-and close the 11 '(21)

/

-disconnect.

Initial Data 3.4.2 Roll the main turbine and bring it to '1800 rpm

/

per procedure S01.1.A.

Initial FiTE AT NO TIME DURING OPERATION SHOULD FIRST STAGE BOWL DIFFERENTIAL (INNER-OUTER) TEMPERATURE EXCEED 75 DEGREES F.

INNER FIRST STAGE BOWL TEMPERATURE. RISE IS ALSO LIMITED TO A MAXIMJM OF 150 DEGREES PER i

HOUR.

3.4.3 continue to raise reactor power by control rod with-drawal using the "RW

/

Rod Sequence" for startup.

Initial Date 3.4.4 Dispatch an operator to 220KV (500KV) substation to clear the permit on

/

generator disconnects.

Initial Date i

L I

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t

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...m..

38302bO880 GP-2 Rsv. O Page 24 of 29 GJM/sm

~

3.4.5 Open both generator output

' breakers, 535 (235) and 635 (335).

Then clear the permit on the generator disconnect,

/

-11 ( 21), and clos e it.

Initial Date 3.4.6 Synchronize'the main generator to the grid per procedure

'S32.1.A.

Pick up load until all the turbine

/

bypass valves close.

Initial ITafs 3.4.7 When tha generator load reaches'a nominal 100 MW, transf er house loads to the unit auxiliary transformer per procedure

/

S91.6.B.

Initial Date 3.4.8 Run load set up to 105

/____

per cent.

Initial Date 3.4.9 Maintain close surveillance of generator cold gas temperature (nominal 40 to 46 degrees C), and turbine expansion as

/

the machine is loaded.

Initial Date 3.5 INCREASING POWER TO RATED Plant is now at nominal 10% power with the generator synchronized.

Rod withdrawal is continuing with the reactor recirculation pumps at minimum speed.

Two condensate pumps are-running.

Two reactor f eed pumps are running, but only one is l

delivering water to the vessel.

l 3.5.1 Open the sixth feedwater l

heater motor operated extraction steam isolation valve. HV-02-119A ( 219A),

for the heater associated with the operating RFP

/

per procedure 802.1.A.

Initial Date d

5

/

m,na, -..-:-

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38302 0880

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GP-2 Rev. O Paga 25 of 29 GJM/sm 3.5.2 Open all fif th feedwater heater extraction steam isola-tion valves HV-02-118A, B,C (218A,B,C) per procedure

/

S02.1.A.

Initial Date

'50 - 100 MWe 10 Percent Power 3.5.3 Continue control rod withdrawal using the "RWM

/

Rod Sequence".for startup.

Initial Date 3.5.4 Close the Main Turbine Control Valve Above Seat Drain Valve HV-Ol-102 (202),

and Below Seat Drain valves HV-01-105A,B (205A,B) and HV-01-lO6A,B (206A,B).

Close the Main Steam Line Startup Drain Valve HV-01-104 (204) and Main Stop Valve Above Seat Drain Valves

-HV-01-101A,B,C,D

/

(201A,B,C,D).

Initial UEEe

~

3.5.5 Close the Main Steam Line Drain Valves HV-41-lF016 ( 2F016),

1F019 (2F019) and

/

1F021 ( 2F021).

Initial DaEE 3.5.6 Ensure that sufficient condensate domineralizers are available for the system

/

flow.

Initial Date 3.5.7 Transfer reactor vessel level i

control to the three-element mode at approx-imately 20 percent

/

l power.

Initial UEEE l

5 1

/

i l

I

~

3830200880

~.

GP-2 Rav. O Paga 26 of 29 GJM/sm 150 - 200 MNe 2'0-Percent Power 7,,

2.5.8 Open all fourth FW heater extraction steam isolation valves MV-02-112 A, B,C

( 212A, B,C) per

/

procedure SO2.1.A.

Initial ITsEe l

THIS PROCEDURE ASSUMES THAT THE BULK OF THE FUEL PRECONDITIONING HAS BEEN DONE.

FUEL i

PRECONDITIONING IS HANDLED IN OTHER PROCEDURES.

FUEL PRECONDITIONING IS AN ATTEMPT TO PREVENT FUEL CLAD FAILURES BY "LOOKING AT" EACH 6 INCH SECIMENT OF EVERY FUEL BUNDLE IN THE CORE AND INCREASING ITS POWER PRODUCTION ABOVE SKW/FT AT A RATE OF 0.11 KW/FT PER HOUR.

COMPUTER PROGRAM OD-ll DEALS WITH -

PRECONDITIONING.

Nominal 25 Percent Power 3.5.9 Check that the process computer program OD-3 (Core Thermal Power) is operable.

The Reactor Engineer, or alternate, will give direction f a

/

~

further power ascension.

Initial DaEe 3.5.10 Place the standby reactor feed pump in service.

It is already running on the MGU at a discharge pressure of about 100 psig less than the other RFP, with its discharge valve open.

Slowly increase its speed via the MGU until it begins to deliver water to the reactor.

When'the individual controller deviation meter. reaches zero, place its MGU in " AUTO".

Open the sixth FW heater extraction steam isolation

/

i valve for this RFP.

Initial Date 4

L

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3830200880 GP-2 Rev. O Page'27 of 29 GJM/ sm 3.5.11 Open all third FW heater extraction steam isolation valves HV-02-108A, B,C (208A,B,C) per procedure

/

S02.1.A.

Initial Date

-3.5.12 continue rod withdrawal toward the 1001 power rod. configuration as directed by-the Reactor

/

Engineer or alternate.

Initial Date 3.5.13 Continue to increase power within PCIOMR limitations by increasing reactor recirc-culation flow as directed by the Reactor Engineer

/

or alternate.

Initial Date 3.5.14 Use the various process computer programs to ensure satisf actory operation of.the-core.

P-1 Periodic Log OD-3 Core Thermal Power and APRM Calibration l

OD-7 Control Rod Positions i

i L

OD-8 LPRM Console Readings j

l OD-6, Option 3 Critical Power Ratio 1

j OD-6, Option 1,2 Thermal Data in Puel Assembly OD-6, Option 4 LHGR OD-ll, Option 00,3 Preconditioned Data OD-ll, Option 6 Core Analysis Log (Control Rod Withdrawal vs.

Precondi tioned

/

Envelope).

Initial Date 1

l 9

w w

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TW w

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3830200880 GP-2 Rav. 0 Pags 28 of-29 GJM/sm 3.5.15 start the' third condensate

/

pump per procedure S05.1.B.

Initial Date

-3.5.16 Warm up thu third reactor-feed pump and place it in standby per

/

i procedure S06.1.A.

. Initial Date i

'3.5.17. Check to ensure sufficient l

condensate demineralizers are

/

operable.and in service.

Initial UEEE T

3.5.18 Place the third reactor feedpump in service at approximately 60 percent

/

power.

Initial Date

- 3.5.19 Continue to increase power

/

to rated conditions.

Initial Date t

l-3.5.20 continue to monitor core performance via the-various

/

process computer programs.

Initial DaEE l

Full Load MWe 3.5.21 After 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the "RUN" mode, close 'the feedwater heater startup vent valves per procedure

/

SO2.1.A.

Initial 5IEI REVIEWED BY:

DATE (Shif t Supervision) 9 r

++uF

.3830200880 GP-2 Rav. O Paga 29 of 29 GJM/sm 4.0 REFE RENCES 4.1 Technical. Specifications 4.2 Final Safety Analysis' Report (FSAR) 4.3 G..E. Service Infermation Letters (SIL.)

4.4 G.E. - Turbine Information Letters (TIL) 4.5 NRC IE Bulletin 80-25 4.6 Memorandits entitled "Deaerating Assist Steam Spargers",

D. A. DiPaolo, 7/4/83; File:

EQUIP l-12-5 4.7 Memorandum entitled " LGS Open Items - Feedwater Isolation. Valves", D.

R. Helwig, 7/16/83; File:

NUCL 9-6-B 4.8 Bechtel Memorandum' entitled " LGS Feedwater System Startup Revi ew", D.

L. Damon, 5/24/83; File EQUIP 1-26 J

G w

....._,,_...,__r....

.--

ML20096F714: Difference between revisions

Latest revision as of 07:52, 13 December 2024

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References:

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ML20096F714: Difference between revisions

Latest revision as of 07:52, 13 December 2024

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References:

Reference:

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