ML18026A225

Forwards Draft Revised Emergency Operating Procedures Incorporating NRC Comments Generated During 810506-07 Simulator walk-throughs.Submittal of Procedures Will Allow NRC to Close SER Items 69,73 & 78.Draft Procedures Encl

ML18026A225
Person / Time
Site:	Susquehanna
Issue date:	05/15/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
PLA-791, NUDOCS 8105190178
Download: ML18026A225 (84)

Text

REGULAT~ INFORMATION DISTRIBUTION~STEM (RIDS) t "i.

ACCESSION NBR ~ 8105190178 DOC ~ DATE 81/05/15 NOTARIZED NO D

FACIL'.50 387 Susquehanna Steam Electric Stationi Unit ii Pennsyl va 00 387 50 388 Susquehanna Steam Electric Stationi Unit 2i Pennsylva 050 8

AUTH ~ NAME 'UTHOR AFFILIATION CURTISi No@ ~

Pennsylvania Power L Light Co.

RECIP,NAMEt RECIPIENT AFFILIATION YOUNGBLOODrB.J.

Licensing Branch 1

S UBJECT: Forwards draft-revised emergency operating procedures incorporating NRC comments generated during 810506>>07 simulator walk through'ubmittal of procedures will allow N4C to close

$ ER Items 69i73 L 78'raft procedures encl'ISTRIBUTION CODE:

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TITLE': PSAH/FSAR AMDTS*and Related Cor respondence NOTES:Send I8E 3 copies FSAR 8 all amends

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amends,i cy'.BNR LRG PM(L ~ RIB) 05000387 05000388 RECIPIENT ID CODE/NAME, ACTION:

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PP@,IL TWO NORTH NINTH STREET, ALLENTOWN, PA.

18101 PHONE:

(215) 821-5151 NORMAN W. CURTIS Vice President. Engineering & Construction 821-5381 May 15, 1981

-'gtjip>,

t'yy u,,

8 t98I 8 ta CIEArt rtr o44lissI0~NTORII Mr. B. J. Youngblood, Chief Licensing Branch No.

1 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ITEMS NO. 69, 73 AND 78 ER 100450 FILE 841-2,-12 PLA-791

Dear Mr. Youngblood:

Attached are revised Emergency Operating Procedures.

These procedures have been revised to incorporate NRC comments generated during the Simulator walk-throughs on May 6 and 7.

The submittal of these procedures completes our action and will allow NRC to close SER open items 69, 73 and 78.

Very truly yours N.

W. Curtis Vice President-Engineering 8 Construction-Nuclear DPM/mks cc:

R.

M. Stark goo

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5 i(i 8X05X80 (78 PENNSYLVANIA POWER LIGHT COMPANY

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PENNS.

ANIA POWER

& LIGHT COMPANY SUSQUEHANNA SES UNITS 1

& 2 PROCEDURE APPROVAL FORM Effective Date TITLE:

EO-00-014 REVISION 0

ANTICIPATED TRANSIENT WITH FAILURE TO SCRAM (ATWS)

PAGE 1

OF 4

PORC REVIEW REQUIRED:

YES

(

)

NO (

)

Meeting Number ORIGINATOR:

Dave Smith APPROVALS:

SECT DATE RINTENDENT OF PL&MT DATE 1.0 SY".PTOMS AND OBSERVATIONS A.

A valid scram signal is present and not all control rods insert as indicated on the full core display, RSCS rods "full-in indication",

display of OD-7(NSS-3) "Present Control Rod Positions" and the Four Rod display.

B.

Neutron flux does not decrease rapidly as in a normal scram.

C.

Reactor pressure vessel pressure

'may increase causing safety relief valves to operate.

2.0 AUTOMATIC ACTIONS A.

Recirculation pumps trip on ATWS signals of:

l.

-38" RPV level 2.

1135 psig RPV pressure FORM AD-00-001-2, Rev.

1 Page 1 of 1

EO-00"014 Revision 0

Page 2 of 4 B.

Safety Relief valves may operate.

C.

Scram Condition Alarms 1)

RX AUTO SCRAM CHANNEL Al/A2 2)

RX AUTO SCRAM CHANNEL Bl/B2 3)

Valid channel A and channel B scram alarm 3.0 IMMEDIATE OPERATOR ACTIONS A.

Manually trip recirculation pumps A and B.

B.

Manually scram the Reactor as follows:

1)

ARM and depress the manual scram pushbuttons.

2)

Place the mode switch in SHUTDOWN.

3)

If the reactor

scrams, perform EO-00-001 and do not continue this procedure.

C ~

If the reactor is not SCRAtkiED by the above actions, perform the following steps, in order, until the reactor is subcritical.

1.

Start the 2nd CRD pump a)

Place the CRD flow controller in manual and fully open the flow control valve (l(2)-46-FV-1F002A(B))

b)

Fully open the CRD drive water pressure control valve (1(2)-

46-PV-1F003).

2.

Open REACTOR PROT SYS TRIP SYS A supply breaker (BKR/j

) on panel Y201A and open REACTOR PROT SYS TRIP SYS B supply breaker (BKR/3

) on panel Y201B.

3.

Isolate and bleed air from the scram air header by closing valve 1(2)-47-1F095 and opening valve 1(2)-47-007.

4.

Individually scram the control rods at the HCU by placing the test switches (2 at each HCU) in test.

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EO-00-014 Revision 0

Page 3 of 4 5.

Inject SBLC per ON-53-001 if either of the following conditions exist:

a) 5 adjacent control rods and/or 30 control rods total are notch 06 following a reactor scram AND one or both of the following exist:

1) reactor water level cannot be maintained OR b) 2)

suppression pool water temperature reaches 110 F The Control Rod Drive system is incapable of shutting down the Reactor AND one or more of the following exist:

1)

Reactor power starts to increase as indicated by both nuclear instrumentation and steam flow OR 2)

Calculations indicate that criticality will be reached in the next hour OR 3)

In the judgement of shift supervision, a hazard exists to the environs, personnel or the plant.

4.0 SUBSE UENT OPERATOR ACTION A.

If the reactor was SCRAHMED by the immediate actions, refer to EO 001 (Reactor Scram) and discontinue this procedure.

B.

If reactor pressure is causing the safety relief valves (SRV's to cycle:

o Manually open enough SRV's to reduce reactor pressure to less than 920 psig.

o For subsequent SRV operation, the valves should be cycled in order to minimize local heat loading of the suppression pool.

o If the HPCI system is not in service, it may be placed in full flow test to minimize SRV cycling.

Place the RHR system in the suppression pool cooling mode.

(Refer to EO-00-023, Containment, Control and OP-49-001, RHR System).

EO-00-014 Revision 0

Page 4 of 4 5.0 DISCUSSION An "anticipated transient without SCRAM" (ATWS) is a

SCRAM condition existing with either no control rods being inserted or not enough control rods being inserted to prevent a restart.

While an ASS is extremely unlikely, if it did occur, prompt operator action would be required to mitigate the consequences.

Major operator concerns are as follows:

1.

Verify the recirculation pumps trip 2.

Shutdown of the reactor 3.

Limit RPV peak pressure 4;

Maintain the core cover 5.

Limit the temperature of the suppression pool/chamber 6.

Long term cooldown The operator must insert enough negative reactivity into the core so that an uncontrolled restart will not occur, this by the most readily available means.

The consequences of this accident to the containment and environment must be evaluated, and if it is deemed necessary, the Susquehanna SES Emergency Plan should be initiated.

6.0 REFERENCES

A.

EO-00-001 Reactor Scram B.

EO-00-023 Containment Control C.

OP-49-001 RHR System D.

ON-53-001 SLBC Initiation

PENNS ANIA POWER

& LIGHT CONPANY SUSQUEHANNA SES UNITS 1

& 2 PROCEDURE APPROVAL FOR~i Effective Date TITLE:

EO-00-021 LEVEL CONTROL REV IS ION 0

PAGE l OF 6

PORC REVIEW REQUIRED:

YES

(

)

NO (

)

tieeting Number ORIGINATOR:

P.

E. Taylor

, APPROVAKS:

SECTS DATE RINTENDENT OF PLANT DATE 1.

ENTRY CONDITIONS The entry conditions for this procedure

~an of the following:

a.

RPV water level less than +13".

b.

Drywell pressure greater than 1.69 psig.

c.

An isolation condition exists which requires or initiates reactor scram (refer to section 3/4~ 3.2 of Technical Specifications for isolations).

2.

OPERATOR ACTIONS 2.a.

CONFIRM initiation OR initiate the following:

Reactor scram.

Perform EO-00-001 (Reactor Scram) concurrently with this procedure.

2)

System isolations consistent with plant parameters.

3)

ECCS and SGTS operation consistent with plant parameters.

Diesel Generators operating consistent with plant parameters.

PORN AD-00"001-1, Rev. l Page

3. of l

EO-00-021 Revision 0

Page 2 of 6 CAUTION AVOID RPV HIGH WATER IEVEL TRIP (+54") of F.W.

PUMPS, RCIC, AND HPCI.

CAUTION DO NOT SECURE OR PLACE AN ECCS IN MANUAL MODE UNLESS)

BY AT LEAST TWO INDEPENDENT INDICATIONS)

(1)

MISOPERATIONS IN AUTOMATIC IS CONFIRMED OR (2)

ADEQUATE CORE COOLING IS ASSURED.

IF AN ECCS IS PLACED IN MANUAL, IT WILL NOT INITIATE AUTOMATICALLY.

MAKE FREQUENT CHECKS OR THE INITIATINGOR CONTROLLING PARAtKTER.

WHEN MANUAL OPERATION IS NO IONGER REQUIRED, RESTORE THE SYSTEM TO AUTOMATIC/STANDBY MODE IF POSSIBLE, 2.b.

RESTORE AND MAINTAINRPV water level between

+13" and +54" with one or more of the following systems.

The choice of using the following systems vary with plant conditions.

It is preferred that the minimum of systems be used to accomplish the water level restoration.

EO-00-021 Revision 0

Page 3 of 6 2.b.

(cont)

SYSTEM Cond/FW OP OP-44-001 FLOWRATE 30,000 gpm PRESS RNG 1076psig -

Opsig OP-55-001 400 gpm 1076psig -

Opsig RCIC OP-50"001 600 gpm 1076psig -

60psig HPCI OP-52-001 5,000 gpm 1076psig - 110psig CS Loop ASB I

OP"51-001 6,350 gpm/loop 455psig -

Opsig LPCI Loop ASB OP-49-001 21,300 gpm/loop 455psig -

Opsig I

1)

IF RPV water level can be restored and maintained above +13", then enter appropriate G.O.

as determined by Shift Supervision.

2.c. IF RPV water level CANNOT be restored and maintained above +13",

PERFORM the following then:

1)

IF level is below +13" BUT above TAF, then MAINTAINRPV water level above TAF AND evacuate unnecessary personnel from the Reactor Building.

NOTE IF IT IS APPARENT THAT INJECTION SYSTEMS ARE NOT READILY AVAILABLE, LINEUP ALTERNATE INJECTION SYSTEMS PER EO-00-024 (I.evel Restoration)

IN CONJUNCTION WITH PERFORMING THIS PROCEDURE.

2)

IF level is below TAF OR CANNOT be determined, then ENTER EO-00" 024 (Level Restoration).

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Page 4 of 6 CAUTION MANUAL CYCLING OF SRV's IS TO BE DONE IN ALPHABETICAL ORDER TO PREVENT EXCESSIVE LOCAL HEAT IOADING OF THE SUPPRESSION POOL.

2.d. IF SRV's are cycling, then manually open one SRV and reduce RPV pressure to between 700 psig and 920 psig AND start HPCI and/or RCIC to minimize SRV cycling.

2.e.

WHEN RPV water level has stabilized, enter EO-00-022 (Cooldown) 3.

DISCUSSION A.

This procedure provides the direction necessary to restore and stabilize RPV water level.

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EO-00-021 Revision 0

Page 5 of,6 B.

SRV's discharged to the Suppression Pool by the following drawing:

SRV Settin s

> o B

L 0

G Qie E0 H0 Qry OOOO MAIN STEAM LINES S

F 0,

0 0

0 0

~ REACTOR 0

Relief 1086

)076 1086 D

1086 1076 1096 1116 1086 1106 1116 1106 1116 1106 1096 1096 1096 Safet 1175 1146 1175 1175 1146 1185 1205 1175 1195 1205 1195 1205 1195 1185 1185 1185 C.

All levels are from instrument zero unless otherwise noted.

TAF is "0" on the fuel zone indicator.

4.

REFERENCES a.

EO-00-001 Reactor Scram b.

EO-00-022 Cooldown c.

EO-00-024 Level RestOration d.

EO-00-025 RPV Flooding

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EO-00-021 Revision 0

Page 6 of 6 e.

OP-44-001 Condensate and Feedwater System f.

OP-49-001 RHR System g.

OP-50-001 Reactor Core Isolation Cooling System h.

OP-51-001 Core Spray System i.

OP-52-001 High Pressure Coolant Injection System j.

OP-55-001 CRD Hydraulic System OP-55-001 Control Rod Drive Hydraulic System l~

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~I PENNSY AifIA POWER

& LIGHT COMPANY SUSQUEHAifNA SES UNITS 1

& 2 PROCEDURE APPROVAL FORM Effective Date TITLE:

EO-00-022 COOLDONN REVISION 0

PAGE 1 OF 7

PORC REVIEW REQUIRED:

YES (

)

NO (

)

A~feeting Number ORIGINATOR:

P.

E. Taylor APP ROVALS:

SE'CTIO DATE NDENT OF PLAiNT DATE l.

ENTRY CONDITIONS This procedure is entered from E0-00-021, (Level Control), after the RPV water level has been stabilized.

2.

OPERATOR ACTIONS CAUTION DO NOT SECURE OR PLACE AN ECCS IN MANUAL MODE UNLESS, BY AT LEAST TWO INDEPENDENT'NDICATIONS, (l) MISOPERATION IN AUTOMATIC IS CONFIRMED, OR (2)

ADEQUATE CORE COOLING IS ASSURED.

IF AN ECCS IS PLACED IN MANUAL, IT MILL NOT INITIATE AUTOlfATICALLY. MAKE FREQUENT CHECKS OF THE INITIATING OR CONTROLLING PARAMETER.

MHEN MANUAL OPERATION IS NO LONGER REQUIRED, RESTORE THE SYSTEM TO AUTO~AfATIC/STANDBY MODE IF POSSIBLE.

FORM AD-00-001-1, Rev 1

Page l of 1

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~'O-00-022 Revision 0

Page 2 of 7

CAUTION IF A DRYWELL PRESSURE ECCS INITIATIONSIGNAL (1. 69 psig)

OCCURRS OR EXISTS WHILE DEPRE S SURIZING, PREVENT INJECTION FROM THOSE CS AND LPCI PR1PS NOT REQUIRED TO ASSURE ADEQUATE CORE COOLING PRIOR TO REDUCING RPV PRESSURE TO THEIR MAXIMUM INJECTION PRESSURES WHEN THE HIGH DRYWELL PRESSURE ECCS INITIATIONSIGNAL CLEARS, RESTORE CS AND LPCI TO AUTOMATIC/STANDBYMODE.

2. a MAINTAIN RPV water leve 1 between

+54" and TAF with one or more of the following systems The choice of using the following systems vary with plant conditions. It is preferred that the minimum of systems be used to accomplish the level restoration.

SYSTEM Cond/FW OP OP-44-00 1 FLOWRATE 30, 000 gpm PRESS RNG 1076psig,-

Opsig CRD (Both Pum s)

RCIC OP-55-001 OP-50-001 400 gpm 600 gpm 1076psig - Opsig 1076psig - 60psig HPCI OP-52-00 1 5, 000 gpm 1076psig -

1 1. Opsig CS Loop OP-5 1 -001 6, 350 gpm/loop 455psig " Opsig LPCI I,oop tlAII g IIBII OP-49-00 1 2 1, 300 gpm/1 oop 455psig - Opsig

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CONFIRM AUTOMATIC TRANSFER OF HPCI AND MANUALLYTRANSFER RCIC SUCTION FROM THE CONDENSATE STORAGE TANK TO THE SUPPRESSION POOL BY OPENING HV-1F042 (HPCI PP SUCT FRM SUPP POOL)

AND SHUTTING HV-1F004 (HPCI PP SCT VLV FROM CST)

FOR HPCI AND BY OPENING HV-1F031 (RCIC PP SUCT FRM SUPP POOL)

AND SHUTTING HV-1F010 (RCIC PP SUCT VLV FRM CST)

FOR RCIC.

l 1g 2.b. IF RPV water level CANNOT be determined or maintained above

TAF, then enter EO-00-024 (Level Restoration).

CAUTION I

MANUAL CYCLING OF SRV's IS TO BE DONE IN ALPHABETICAL ORDER TO PREVENT EXCEEDING LOCAL HEAT LOADING OF THE SUPPRESSION POOL.

I 2.c. IF SRV's are cycling, then manually open one SRV and reduce RPV pressure to between 700 psig and 920 psig and start HPCI and/or RCIC to minimize SRV cycling.

CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAINRPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

2.d.

DEPRESSURIZE and COOLDOWN the RPV at less than 100 F/hr per GO 004 (Reactor Shutdown from Minimum Power Operations to Cold Shutdown Condition) concurrently with this procedure.

1)

Pressure reduction may be augmented in accordance with EO 026 (RPV Pressure Reduction - Preferred Method).

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i EO-00-022 Revision 0

Page 4 of 7 2.d.

(cont) 2)

WHEN the RHR shutdown cooling interlocks clear as indicated by RPV pressure indicating less than 109 psig.

INITIATE the shutdown cooling mode of RHR per OP-49-001 (RHR System).

1)

IF the RHR shutdown cooling mode CANNOT be established AND further cooldown is required, then CONTINUE to cooldown using one or more of the sytems used for depressurization.

2.e.

IF RPV cooldown is required BUT CANNOT be accomplished, then perform Alternate Shutdown Cooling as follows:

Initiate suppression pool cooling mode of RHR per OP-49-001 (RHR System).

2)

CLOSE the following valves:

a)

RPV Head Vents:

HV"41-F001 b)

All MSIV's:

HV-41-F002 HV-41-F005 HV-41-F022A HV-41-F022B HV-41-F022C HV-41-F022D HV-41-F028A HV-41-F028B HV-41-F028C HV-41-F028D c)

MSL Drain Lines:

HV-41-F016 HV-41-F019 HV-41-F020 d)

RHR Steam Condensing Valves:

HV-51-F051A HV-51-F051B HV-51-F052A HV-51-F052B 3)

Position SRV's so that only one SRV is open.

4)

Maintain RPV water level less than 54" until RPV pressure is less than 455 psig by use of HPCI and RCIC.

5)

WHEN RPV water level exceeds 54":

a)

CLOSE the following HPCI isolation valves:

HV-55-F002 HV-55-F100 HV-55-F003

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~'O-00-022 Revision 0

Page 5 of 7 2.e.

(cont) b)

CLOSE the following RCIC isolation valves:

HV-49-F007 HV-49-F088 HV-49-F008 6) 7)

8)

Start one CS or LPCI pump with suction from the suppression pools Slowly raise RPV water level to 131", while maintaining less thana 100~F/hr cooldown rate, to establish a flow path through the open SRV back to the suppression pool.

Slowly increase LPCI flow to establish a

100 F/hr cooldown rate.

a)

IF necessary, increase LPCI flow to the maximum single pump flow for the pressure at which RPV pressure stabilizes.

If LPCI is unavailable, use CS.

b)

IF RPV pressure does not stabilize ABOVE 122 psig, start another pump.

c)

IF RPV pressure does not stabilize BELOW 280 psig, open additional SRV's located symetrically about the suppression pool.

CAUTION CONTROL SUPPRESSION POOL TEMPERATURE TO MAINTAINRPV WATER TEMPERATURE ABOVE 70 F PER OP-49-001.

9)

WHEN RPV cooldown is under control and plant conditions are

stable, proceed to cold shutdown in accordance with G0-00-004 (Reactor Shutdown from Minimum Power Operations to Cold Shutdown Conditions).

3.

DISCUSSION This procedure provides the direction necessary to depressurize and cooldown the RPV to cold shutdown conditions while maintaining RPV water level within a satisfactory range.

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EO-00-022 Revision 0

Page 6 of 7 B.

All levels are from instrument zero unless otherwise noted.

TAF is 0" on the fuel zone indicator.

C.

SRV's discharge to the suppression pool by the following drawing:

SRV Settin s

Relief Safet 0

g Q

0 0 REACTOR A

(

1086 B

<i1076 C

1086 1175 1146 1175 1096 1185 1116 1205 1086 1175 1086

!I 1175 1076 '146 0

Qj 0

1106 1116 1106 1116 1106 1096 1096 1096 1195 1205 1195 1205 1195 1185 1185 1185 D.

The 280 psig in step 2.f.7.b) is to assure sufficient alternate shutdown cooling flow.

4.

REFERENCES a.

EO-00-021 I.evel Control b.

EO-00-024 I,evel Restoration c.

EO-00-025 RPV Pressure Reduction (preferred methods) d.

G0-00-004 Reactor Shutdown from Minimum Power Operations to Cold Shutdown Conditions e.

OP-44-001 Condensate and Feedwater System f.

OP-49-001 RHR System-g.

OP-50-001 Reactor Core Isolation Cooling System

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EO-00-022 Revision 0

Page 7 of 7 h.

OP-51-001 Core Spray System i.

OP-52-001 High Pressure Coolant Injection System j.

OP-55-001 Control Rod Drive Hydraulic System

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PENN ANIA POWER

& LIGHT COMPANY SUSQUEHANNA SES UNITS 1

& 2 PROCEDURE APPROVAL FOR 1

TITLE:

EO-00-023 CONTAINMENT CONTROL Effective Date REVISION 0

PAGE 1

OF 11 PORC REVIEW REQUIRED:

YES

(

)

NO (

)

Meeting Number ORIGINATOR:

P.

E. Taylor APPROVALS:

SECTI DATE NTENDENT OF PLMT DATE 1.

ENTRY CONDITIONS The entry conditions for this procedure are

~an of the following:

a

~

b.

C ~

d.

e.

Suppression Pool Water Temperature above 90~F.

Drywell Atmosphere Temperature above 135~F.

Drywell Pressure above 1.69 psig.

Suppression Pool Water Level above 24'uppression Pool water level less than 22'.

2.

OPERATOR ACTIONS NOTE REGARDLESS OF THE ENTRY CONDITION, ENTER THIS PROCEDURE AT STEPS 2.a, 2.b, 2.c, AND 2.d AND PERFORM THESE STEPS CONCURRENTLY WITH ONE ANOTHER.

FORM AD-00-001-1, Rev.

1 Page 1 of 1

2.a.

SUPPRESSION POOL TEMPERATURE EO-00-023 Revision 0

Page 2 of ll 1)

SHUT any SRV that is open as indicated by "PRESSURE RELIEF ADS OR SAFETY VLV LEAKING" alarm on ECCS benchboard and a

STM FLOW/FEED FLOW mismatch of about 800,000 ibm/hr.

CAUTION IF CONTINUOUS LPCI OPERATION IS REQUIRED TO ASSURE ADEQUATE CORE

COOLING, DO NOT DIVERT RHR PUMPS FROM THE LPCI MODE.

2) 3)

WHEN suppression pool temperature exceeds 90~F, operate available RHR Loop A and/or B in the suppression pool cooliong mode per OP-49-001.

IF suppression pool temperature reaches 110 F, then SCRAM the reactor per EO-00-001 (Reactor Scram).

CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAINRPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

CAUTION COOLDOWN RATES ABOVE 100 F/HR MAY BE REQUIRED TO ACCOMPLISH THIS STEP.

CAUTION MAINTAIN SUPPRESSION POOL WATER LEVEL ABOVE (later)

FEET TO ENSURE NPSH REQUIREMENTS FOR PUMPS TAKING SUCTION FROM SUPPRESSION POOL ARE MET.

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EO-00-023 Revision 0

Page 3 of ll 2.a.

(cont) 4)

IF suppression pool water temperature cannot be maintained below the Heat Capacity Temperature Limit, Figure E0-00-023-1, then maintain RPV PRESSURE below that limit per EO-00-026 (RPV Pressure.

Reduction - Preferred Hethod).

5)

IF suppression pool water temperature AND RPV pressure CANNOT be maintained below the Heat Capacity Temperature Limit, Figure EO" 00-032-1 then:

a)

RAPIDLY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure,

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2.b.

DRYWELL TEMPERATURE EO-00-023 Revision 0

Page 4 of 11 1)

IF drywell temperature exceeds 135~F, then operate ALL AVAILABLEdrywell coolers per OP-60-001(Drywell Ventilation System)

CAUTION WHENEVER DRYWELL TEMPERATURE EXCEEDS THE TEMPERATURE IN THE TABLE) THE ACTUAL RPV WATER LEVEL MAY BE ANYWHERE BELOW THE ELEVATION OF THE LOWER INSTRUMENT TAP WHEN THE INSTRUMENT READS BELOW THE INDICATED IEVEL IN THE TABLE.

AT THIS POINT, DISREGARD THE INSTRUMENT FOR FURTHER RELIABILITY.

C Drywell Tem eratue Indicated I.evel Instrument Inst.

No.

(later)

(later Shutdown Range (0 to +400 in.)

(later)

(later)

(later Upset range (0 to +180 in.)

(later (later)

(later)

Wide range

(-150 to +60 in.)

(later)

(later)

(later)

Narrow range (0 to +60 in.)

later (later)

(later)

Fuel zone

(-150 to +50 in.)

(later)

CAUTION DO NOT DIVERT RHR PUMPS FROM THE LPCI MODE IF CONTINUOUS LPCI OPERATION IS REQUIRED TO ASSURE ADEQUATE CORE COOLING.

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2.b.

(cont) 2)

E0-00-023 Revision 0

Page 5 of ll BEFORE drywell temperature reaches 340~F, but after drywell temperature reaches 320~F STOP the recirculation pumps and drywell cooling fans AND INITIATE drywell sprays.

IF drywell temperature near the RPV level instruments reaches the saturation limit, Figure E0-00-023-2, then rapidly depressurize the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110, PSIG UNLESS MOTOR DRIVEN PR1PS SUFFICIENT TO MAINTAINRPV WATER LEVEL ARE RUNNING AND AVAILABIEFOR INJECTION.

CAUTION COOLDOWN RATES ABOVE 100 F/HR MAY BE REQUIRED TO ACCOMPLISH THIS STEP.

4)

IF drywell temperature CANNOT be maintained BELOW 340~F, then a)

RAPIDIY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

~

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2. c.

PRIMARY CONTAIRKNT PRESSURE EO-00-023 Revision 0

Page 6 of 11 CAUTION

'2 CONCENTRATIONS MAY DEVELOP IN THE PRIMARY CONTAIRKNT.

1)

BEFORE H2 concentration reaches 3.3% by volume:

a)

Start the hydrogen recombiner system per OP-73-001 (Containment Atmosphere Control System)tr CAUTION ELEVATED SUPPRESSION CHAMBER PRESSURE MAY TRIP THE RCIC OR HPCI TURBINES ON HIGH EXHAUST PRESSURE.

NOTE ENSURE CHEMISTRY DEPARTMENT SAMPIES AND ANALYSES THE SPACE TO BE VENTED PR10R TO VENTING.

2)

VENT the primary containment through the SGTS ONLY vhen space to be vented is BELOW 212~F.

CAUTION DO NOT DIVERT RHR PUMPS FROM THE LPCI MODE IF CONTINUOUS LPCI OPERATION IS REQUIRED TO ASSURE ADEQUATE CORE COOLING.

3)

IF suppression pool chamber pressure APPROACHES the Suppression Pool Spray Limit, Figure EO-00-023-3 then:

a)

INITIATE suppression pool sprays

2.c.

(cont)

EO-00-023 Revision 0

Page 7 of ll CAUTION DO NOT OPERATE THE REACTOR RECIRCULATION PUMPS OR PRIMARY CONTAIRIENT VENTIIATION FANS WHEN SPRAYING THE DRYWELL.

4)

IF suppression chamber pressure APPROACHES the Pressure Suppression Limit, Figure EO-00-023-4 then:

a)

SHUTDOWN the recirculation pumps and drywell cooling fans AND INITIATE drywell sprays.

5)

IF suppression chamber pressure CANNOT be maintained below the Pressure Suppression Limit, Figure EO-00-023-4 then:

a)

RAPIDLY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this p'cedure.

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2.d.

SUPPRESSION POOL WATER LEVEL EO-00-023 Revision 0

Page 8 of ll 1.

Ensure Chemistry Department samples and analyzes suppression pool water prior to discharging.

2.

Maintain suppression pool water level between 22'nd 24'.

CAUTION lg I

DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAIN RPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

J CAUTION COOLDOWN RATES ABOVE 100 F/HR MAY BE REQUIRED TO ACCOMPLISH THIS STEP.

1)

Suppression Pool water level less than 22')

IF level CAN be maintained above the Heat Capacity Level Limit, figure E0-00-023-5, then:

(1)

INITIATE suppression pool make-up per OP-59-001 (Suppression Pool Cleanup) and maintain suppression pool level between 22'nd 24'.

b)

IF level CANNOT be maintained above the Heat Capacity Level Limit E0-00-023-5, then:

(1)

Rapidly depressurize the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

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2.d.

(cont)

EO-00-023 Revision 0

Page 9 of ll CAUTION IF SIGNALS OF HIGH SUPPRESSION POOL WATER LEVEL (23'2")

OR LOW CONDENSATE STORAGE TANK WATER LEVEL (3'9") OCCUR, CONFIRM AUTOMATIC TRANSFER OF HPCI AND MANUAILYTRANSFER RCIC SUCTION FROM THE CONDENSATE STORAGE TANK TO THE SUPPRESSION POOL BY OPENING HV-1F042 (HPCI PP SUCT FRM SUPP POOL)

AND SHUTTING HV"1F004 (HPCI PP SUCT FRM CST)

FOR HPCI AND BY OPENING HV-1F031 (RCIC PP SUCT FRM SUPP POOL)

AND SHUTTING HV-1F010 (HPCI PP SUCT VLV FRM CST)

FOR RCIC.

2)

Suppression pool water level cannot be maintained below 24')

IF ADEQUATE core cooling is assured then:

1)

TERMINATE injection into the RPV from sources external to the primary containment.

b)

IF su ression ool water level CANNOT be maintained below the Suppression Pool Load Limit, Figure EO-00-023-6 then:

(Reactor Pressure Reduction - Preferred Method) 3.

DISCUSSION restored or maintained below the Suppression Pool Load Limit, Figure E0-00-023-5, then:

1)

RAPIDLY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

2)

IF primary containment water level reaches 122.4'hen:

a)

TERMINATE injection into the RPV from sources external to the primary containment.

A.

This procedure provides the direction necessary to control primary containment temperatures, pressure and level.

~

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~ q EO-00-023 Revision 0

Page 10 of 11 B.

The Heat Capacity Temperature Limit, Figure E0-00-023-1, is the limit which may result in insufficinet heat capacity of the suppression pool to assure stable condensation of steam discharged through the SRV's during a full ADS.

C.

The RPV Saturation Limit, Figure E0-00-023-2, is the limit for the reference leg vertical runs boiling off.

Loss of inventory from the reference leg results in an increase of indicated level and the operator ran no longer rely on RPV water level indication for verification of adequate core cooling.

D.

Suppression Pool Spray Limit, Figure E0-00-023-3, is the limit that requires spray to be initiated to condense steam in the suppression pool and terminate any further suppression chamber increase prior to reaching containment design pressure.

E.

Pressure Suppression Limit, Figure E0-00-023-4, is the limit that indicates the containment's pressure suppression function is not performing as designed.

F.

The Heat Capacity Level Limit, Figure E0-00-023-5, is the limit which may result in insufficient heat capacity of the suppression pool to assure stable condensation of ste-discharged through the SRV's during a full ADS.

G.

Suppression Pool Load Limit, Figure E0-00-023-5, defines the limiting conditions for which a rapid RPV depressurization using the ADS is always safely possible.

'H.

The 122.4'imit in step 2.d.3) is based on a possible breach of the primary containment boundary due to increased loading from the added water and flooding above the highest containment vent elevation precludes future venting of the containment which eliminates the ability to take action to prevent possible containment overpressurization.

l.

Adequate core cooling is assured by any of the following:

1.

The active fuel is covered with liquid or a two phase mizture.

2.

ECCS flow is cooling each fuel assembly in sufficient quanity to remove all heat generated in the assembly.

3.

Steam flow is cooling each fuel assembly in sufficient quality to remove all heat generated in the assembly.

4.

REFERENCES a.

EO-00-001 Reactor Scram b.

EO-00-025 RPV Flooding c.

EO-00-026 RPV Pressure Reduction - (Preferred Methods)

EO-00-023 Revision 0

Page ll of ll d.

EO-00-027 Rapid Depressurization e.

OP-70-001 Standby Gas Treatment System

1 FI GURE EO.=

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PV, Pressure (psig) g i

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PRESSURE SUPPRESSION LIHIT 50 C

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PENNSY~NIA POWER

& LIGHT COMPANY SUS~HANNA SES UNITS 1

& 2 PROCEDURE APPROVAL FOR f Effective Date TITLE EO-00-024 LEVEL RESTORATION REVISION 0

PAGE l OF 9

PORC REVIEW REQUIRED:

YES

(

)

NO (

)

Meeting Number ORIGINATOR:

P.

E. Taylor APP ROVALS:

SECTION DATE c INTENDENT OF PLANT DATE 1.

ENTRY CONDITIONS This procedure is entered from EO-00-021 (Level Control) or EO-00-022 (Cooldown) when RPV level cannot be maintained above TAF or cannot be determined.

2.

OPERATOR ACTIONS 2.a.

LINE UP for injection and START pumps in two or more of the following normal injection systems to commence injection.

The choices of using the following systems vary with exact plant conditions.

It is preferred that the minimum of systems be used to accomplish the level restoration.

S stem Condensate IlAII CS Loo "B"

LPCI Loo "A"

LPCI Loo "B"

OP OP-44-001 OP-53.-001 OP-53.-001 OP-49-001 OP-49-001 Flowrate 30 000 m

6 350 m

6,350 gpm 21 300 m

21 300 m

Pressure Rn 650 si 0 si 455 si 0 si

. 455psig

-. Opsig 455 si 0 si 455 si 0 si FOEf AD-00-001-1, Rev. l Page 1 of 1

2. a.

(cont)

EO-00-024 Revision 0

'Page 2 of 9 1)

IF less than two of the above sytems can be lined up, then COGENCE lining up as many of the following alternate systems as

possible, but DO NOT inject with the alternate systems at this time.

S stem

'I RHR Service Water across tie by assuring the RHR Service Water System is in operation and then opening HV12F073(ARB)

(RHR/RHRSW Crosstie Vlv and HV12F075 (AGB)

(RHR/RHRSW Crosstie Vlv) when in'ection is called for.

Flowrate 6,000 gpm Pressure Rn 120 psig -

0 psig SBLC Boron Tank to reactor per OP-55-001 SBLC S stem 45 gpm 1076 psig -

0 psig.

ECCS Keep Full System, by confirming the Keep-Full System is lin'ed up and assuring the Condensate Transfer Header is pressurized per OP-37-001, Condensate and Refueling Water Transfer S stem.

100 gpm 120 psig - 0 psig 2)

IF at any time RPV water level cannot be determined and at least one injection system (normal or alternate) is lined up for injection with at least one pump running, then RAPIDLY DEPRESSURIZE per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

3)

IF at any time RPV water level cannot be determined and no injection systems (normal or alternate) are lined up for injection with at least one pump running, then go to step 2.e.4 of this procedure (Core Cooling Without Injection).

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4

EO-00-024 Revision 0

Page 3 of 9 2.b. Monitor RPV water level and pressure 1)

Refer to Table EO-00-024-1 to determine the step to proceed to.

IF AT ANY TIME RPV PRESSURE OR WATER LEVEL TREND REVERSES OR RPV PRESSURE CHANGES REGIONS, RETURN TO TABLE E0-00-024-1.

K Table EO-00-024-1 RPV PRESSURE REGION RPV Level Inc RPV Level Dec Hi h 455 si go to Step 2.b of EO-00-021 Level Contro I Intermediate 455 si

- 110 si 2.c Low 2.d 2.f 110 si

EO-00-024 Revision 0

Page 4 of 9 2.c.

RPV level INCREASING and RPV pressure INTERMEDIATE (above

110psig, below 455psig)

IF HPCI and RCIC are not ready for operation AND RPV pressure is INCREASING then:

a)

RAPIDLY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

2)

IF HPCI and RCIC are not ready for operation AND RPV pressure is NOT increasing then:

a)

Enter EO-00-021 (Level Control) at step 2.b.

3)

MKN RPV water level at step 2.b.

reaches

+13", enter EO-00-021 (Level Control)

EO-00-024 Revision 0

Page 5 of 9 2.d.

RPV level INCREASING and RPV pressure LOW (below 110psig) 1)

IF RPV. pressure is INCREASING then:

a)

RAPIDLY.DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

2)

MiEN RPV level is above TAF a)

ENTER EO-00-021 (Level Control) at step 2.b.

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EO-00"024 Revision 0

Page 6 of 9 2.e.

RPV level DECREASING and RPV pressure above 110psig 1)

IF HPCI and/or RCIC are not operating then:

a)

START HPCI per OP-52-001 and/or START RCIC per OP-50-001.

2)

IF CRD is not operating AND at least two normal injection systems are lined up for injection with pumps running (as per step 2.a) then:

3) a)

RAPIDLY DEPRESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

IF CRD is not operating AND no normal injection system is lined up for injection with at least one pump running:

C a)

START pumps in all alternate injection systems that are lined up for injection per step 2.a.

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EO-00-024 Revision 0

Page 7 of 9 2.e.

(cont) 4)

WHEN RPV water level drops to TAF:

a) b)

IF CRD is operating then RAPIDLY DEPRESSURIZE the RPV per EO 027 (Rapid Depressurization) concurrently with this procedure.

IF CRD is not operating AND no normal injection or alternate injection system is lined up for injection with at least one pump

running, then perform Core Cooling Without Injection as follows:

1)

WHEN RPV water level drops to core midplane (-75" on the Fuel Zone Indicator) or if RPV water level CANNOT be determined, open one SRV.

2)

)

AS RPV pressure decreases, open additional SRV's in alphabetical order as required by Table E0-00-024-2.

Table EO-00-024-2 RPV Pressure (PSIG)

Above 800 Total No. of SRV's 0 en Between 800 and 500 Between 500 and 350 Between 350 and 250 Between 250 and 175 Between 175 and 125 Below 125 3)

WHEN a normal injection or alternate injection system is lined up for injection with at least one pump running:

a)

RAPIDLY DEPBESSURIZE the RPV per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

EO-00-024 Revision 0

Page 8 of 9 2.f.

RPV water level DECREASING AND RPV pressure is LOW (below 110 psig)

IF no normal injection system is lined up for injection with at least one pump running (per step 2.a) then:

a)

START pumps in alternate injection systems that are lined up for injection (per step 2.a).

2)

IF RPV pressure is increasing then:

a)

RAPIDLY DEPRESSURIZE per EO-00-027 (Rapid Depressurization) concurrently with this procedure.

3)

WHEN RPV water level drops to TAF, perform Core Cooling Without Level Restoration as follows:

/

a)

OPEN all ADS valves 1)

IF all ADS valves cannot be opened, open other SRV's until a total of 6 valves are open b)

Operate CS with a suction from the suppression pool (per OP-51-001, Core Spray).

c)

WHEN either CS Loop "A" or "B" is operating with suction from the suppression pool AND RPV pressure is below 105 psig, TEE'JINATE injection into the RPV from sources external to the primary containment.

d)

IF RPV water level is resto'red to TAF, enter EO-00-021 (I,evel Control) at step 2.b.

s l.

EO-00-024 Revision 0

Page 9 of 9 3.

DISCUSSION B.

This procedure provides the direction necessary to restore the RPV water level to above the top of active fuel while maintaining an increasing or stable trend.

All levels are from instrument zero unless otherwise noted.

TAF is "0" on the fuel zone indicator.

C.

With RPV water level at core midplane, one SRV is opened to promote boil-off.

Steam at the two phase level in the RPV is saturated and becomes superheated as it rises up through the core.

Although steam cooling will not assure adequate core cooling indefinately, this procedure will provide the operator with the maximum amount of time possible to get an injection system operable.

lg D.

The pressure ranges of EO-00-024-1 (RPV Pressure Regions) are based on the following:

o HIGH - only High Pressure Injection Systems available o

INTEEKDIATE - both High and Low Pressure Injection Systems available o

LOW - only Low Pressure Injection Systems available REFERENCES a.

EO-00-021 Level Control b.

EO-00-022 Cooldown c.

EO-00-025 RPV Flooding d.

EO-00-027 RPV Pressure Reduction - (Preferred Method) e.

OP-37-001 Condensate and Refueling Water Transfer f.

OP-44-001 Condensate and Feedwater System g.

OP-49-001 RHR System h.

OP-50-001 Reactor Core Isolation Cooling System i.

OP-51-001 Core Spray System j.

OP-52-001 High Pressure Coolant Injection System k.

OP-53-001 Standby Liquid Control System

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PENNS~DiiIA POWER

& LIGHT COMPANY SUS~EHANViA SES UNITS 1

& 2 I

PROCEDURE APPROVAL FORM Effective Date TITLE'O-00-025 RPV FLOODING REVISION 0

PAGE 1 OF 6

PORC REVIEW REQUIRED:

YES (

)

NO (

)

Meeting Number ORIGINATOR:

P.

E. Taylor APP ROVALS:

".~j4 ERINTENDENT OF PLANT DATE DATE 1.

ENTRY CONDITIONS This procedure is entered from EO-00-023 (Containment Control) or EO-00-027 (Rapid Depressurization}

when:

a ~

I b.

C ~

RPV water level cannot be determined Drywell temperature near the RPV level instrument reference leg vertical runs (per Table EO-00-023-2) reaches the RPV Saturation Limit.

Suppression chamber pressure CANNOT be maintained below the Pressure

~ Suppression Limit (per Figure EO-00-023-4 or Figure EO-00-027-1)

FORM AD-00-001-1, Rev.

1 Page 1 of 1

2.

OPERATOR ACTIONS EO-00-025 Revision 0

Page 2 of 6 CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PM1PS SUFFICIENT TO MAINTAINRPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

CAUTION COOLDOWN RATES ABOVE 100~F/HR MAY BE REQUIRED TO CONSERVE RPV WATER INVENTORY, PROTECT PRIMARY CONTAIRKNT INTEGRITY) OR LIMIT RADIOACTIVE RELEASE TO THE ENVIRONMENT.

2.a.

IF LESS THAN three SRV's can be opened then proceed to step 2.c. of this procedure.

2.b. IF AT LEAST three SRV's are open, then shut:

All MSIV's:

HV-41-F022A HV"41-F022B HV-41-F022C HV-41-F022D HV-41-F028A HV-41-F028B HV-41-F028C HV-41-F028D 2.

MSL Drain Lines:

HV-41-F016 HV-41"F019 HV-41-F020 3.

4.

HPCI Isolation Valves:

HV-55-F002 RCIC Isolation Valves:

HV-55-F100 HV-55-F003 5.

HV-49-F007 HV-49-F088 HV-49-F008 RHR Steam Condensing Isolation Valves:

HV"51-F051A HV-51-F051B HV-51-F052A HV-51-F052B

2.b.

(cont) 6.

RWCU Isolation Valves

'V-44-F001 HV-44-F004 EO-00-025 Revision 0

Page 3 of 6 2.c.

INJECT water into the RPV with ALL of the following:

SYSTEM COND I

OP OP-44-001 FLOWRATE 30,000 gpm PRESS RNG 650 psig - 0 psig CRD (both pumps)

OP-55-001 400 gpm 1076 psig - 0 psig CS Loop A OP-51-001 6,350 gpm 455 psig - 0 psig CS Ioop B

OP-51-001 6,350 gpm 455 psig - 0 psig LPCI Loop A OP-49-001 21,300 gpm 455 psig - 0 psig IPCI Loop B

OP-49-001 21,300 gpm 455 psig - 0 psig 2.d. IF RPV water level is rising, then continue this proceduxe at step 2.f.

2.e When RPV pressure is stable, cycle one SRV closed for about 3 minutes and then open to determine the single SRV pressure rise.

1)

IF the single SRV pressure rise exceeds the Minimum Single SRV Pressure Rise per Figure E0-00-025-1, then continue this procedure at step 2.f.

2)

IF the Single SRV Pressure Rise does not exceed the Minimum Single SRV Pressure Rise per Figure EO-00-025-1 then:

a)

Inject water into the RPV with ALL of the following:

ss s

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EO-00-025 Revision 0

Page 4 of 6 S stem Flow Rate Pressure Ran e

RHR Service Water cross tie by assuring the RHR Service Water System is in operation and then opening HV12F073(ASB)

(RHR/MiRSW Crosstie Vlv) and HV12F075(ASB)

(RHR/RHRSW Crosstie Vlv) when in'ection is called for.

6,000 gpm 120 psig - o psig SBLC Boron Tank to reactor per OP-55-001 SBLC S stem 45 gpm 1076 psig - 0 psig ECCS Keep-Full System, by confirming the Keep-Full System is lined up and assuring the Condensate Transfer Header is pressurized per OF-37-001, Condensate and Refueling Water Transfer S stem 100 gpm 120 psig - 0 psig

2. f. IF suppression chamber pressure approaches within 5 psig of the Primary Containment Pressure Limit, figure EO-00-025-1 then VENT the primary containment per OP-73-001 (Containment Atmosphere Control System) to reduce pressure 10 psig below that limit.

2 ~ g ~ IF suppression chamber pressure cannot be maintained below the Primary Containment Pressure Limit per Figure E0-00-025-2, then initiate the following regardless of whether or not adequate core cooling is assured:

1)

Drywell sprays per OP-'49-001(MK System) 2)

Suppression pool sprays per OP-49-001(RHR System) only if suppression pool level is below 49 feet.

2.h. Fill all RPV level instrument reference legs per (later).

2.i. Continue injecting water into the RPV until drywell temperature near the RPV level instrument reference legs (vertical runs) is below 212~F AND RPV water level instrumentation is available.

1)

IF RPV is determined to be filled, then continue this procedure at step 2.k.

7

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EO-00-025 Revision 0

Page 5 of 6 2.j.

CYCLE one SRV closed for above 3 minutes and then open to determine the single SRV pressure rise.

2)

IF the single SRV pressure rise exceeds the Minimum Single SRV Pressure Rise per Figure E0-00-025-1, then continue this procedure at step 2.k.

IF the single SRV pressure rise DOES NOT exceed the Minimum Single SRV Pressure Rise per Figure E0-00-025-1, then return to step 2.i.

above.

CAUTION I

REFER TO FIGURE EO-00-025-3 FOR HAXIMUM ACCEPTABLE CORE UNCOVERY TIME PRIOR TO PERFORMANCE OF STEP 2.k.

2.k. IF single SRV pressure rise exceeds the Minimum Single SRV Pressure Rise OR it can be determined that the RPV is filled then:

1)

TERMINATE ALL injection into the RPV (Injection sources are listed in 2.cd and 2.e. of this procedure).

2)

REDUCE RPV water level until RPV water level indication is restored.

a) b)

IF RPV water level indication is NOT restored within the Maximum Acceptable Core Uncovery Time per Figure EO-00-025-3 after termination of injection into the RPV, then RETURN to step 2.c. of this procedure.

IF RPV water level is restored within the Maximum Acceptable Core Uncovery Time per Figure EO-00-025-3 after termination of injection into the RPV, then enter EO-00-021 (Level Control) at step 2.b.

3.

DISCUSSION A.

This procedure provides the direction necessary to assure adequate core cooling and containment integrity by "flooding the RPV.

B.

SRV's open insures the ability to flood the RPV with low pressure systems.

C.

Closing isolation valves of steam lines directly attached to the RPV or to the Main Steam lines minimizes the amount of piping exposed to a

water hammer that may occur as these lines are flooded.

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EO-00-025 Revision 0

Page 6 of 6 D.

Venting the primary co'ntainment at the Suppression Chamber Pressure Limit is performed to prevent failure of the containment.

E.

RPV can be determined filled by the following methods:

1.

Water level indication 2.

If a source external to the containment is being injected into the

RPV, a stable RPV pressure coincident with an increasing suppression pool level will indicate the RPV is filled.

3.

If no external source is being injected, a stable RPV pressure coincident with a stable suppression pool level will indicate the RPV is filled.

REFERENCES a.

EO-00-021 Level Control b.

EO-00-023 Containment Control c.

EO-00-024 I,evel Restoration d.

EO-00-027 Rapid Depressurization e.

OP-37-001 Condensate and Refueling Water Transfer f.

OP-49-001 RHR System g.

OF-51-001 Core Spray System h.

OP-53-001 Standby Liquid Control System i.

OP-55-001 Control Rod Drive Hydraulic j.

OP-73-001 Containment Atmosphere Control System

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FIGURE EO 00 025 PRIMARY CONTAINMENT PRESSURE LDfIT,

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i 9 ft PENNS AiNIA POWER

& LIGHT COiMPANY SUSQUEHANNA SES UNITS 1 6 2

PROCEDURE APPROVAL FORM Effective Date TITLE:

EO-00-026 RPV PRESSURE REDUCTION (PREFERRED METHOD)

REVISION 0

PAGE 1 OF 3

PORC REVIEW REQUIRED:

YES (

)

NO (

)

Meeting Number ORIGINATOR:

P.

E. Taylor APP ROVALS:

DATE SUPERINTENDENT OF PLAibT DATE l.

ENTRY CONDITIONS This procedure is entered from EO-00-022 or EO-00-023 when it is required to depressurize the RPV using preferred methods at a continuous rate.

2.

OPERATOR ACTIONS CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PEPS SUFFICIENT TO MAINTAIN RPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

CAUTION COOLDOWN RATES ABOVE 100 F/HR MAY BE REQUIRED TO CONSERVE WATER INVENTORY, ROTECT PRIMARY -CONTAINMENT INTEGRITYs OR LIMIT RADIOACTIVE RELEASE TO THE ENVIRONMENT.

FORM AD-00-001-3, Rev.

1 Page 1 of 1

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EO-00-026 Revision 0

Page 2 of 3 NOTE PERFORM EO-00-023 (CONTAIR1ENT CONTROL) IN CONJUNCTION WITH THIS PROCEDURE AS NECESSARY.

2.a.

Hain Condenser Available 2.)

Use bypass valves to DEPRESSURIZE and COOLDOWN the RPV, per G0 004 (Reactor Shutdown from Minimum Power Operation to Cold Shutdown Condition).

Pressure reduction may be augmented with one or more of the fol1.owing systems a.)

HPCI in Full Flow Test Mode or Injection Mode per OP-52-001 b.)

RCIC in Full Flow Test Mode or Injection Hode per OP-50-001 c.)

Other steam driven equipment (1)

Steam Jet Air Ejectors per OP-43-001 (2)

Steam to Reactor Feed Pumps per OP-45-001 (3)

Steam to Steam Seal Evaporator per OP-92-001 (4)

Hain Condenser Deaerating Steam per OP-44-001 d.)

Reactor Water Cleanup (Recirculation Mode) per OP-61-001 e.)

Hain Steam Line Drains f.)

Reactor Water Cleanup (Coolant Rejection) per OP-61-001.

ENSURE Chemistry samples and analyzes primary coolant prior to rejection.

2.b.

Main Condenser not available:

DEPRESSURIZE and COOLDOWN RPV at less than 100~F per hour using one or more of the following systems:

a.)

HPCI per OP-52-001 b.)

RCIC per OP-50-001 c.)

Reactor Water Cleanup System (Recirculation Hode) per OP 001

C EO-00-026 Revision 0

Page 3 of 3 CAUTION 1.

'PEN SRVs IN THE ALPHABETICAL SEQUENCE IF POSSIBLE.

2.

IF THE CONTINUOUS SRV PNEUMATIC SUPPLY IS OR BECOMES UNAVAILABLE, THEN DEPRESSURIZE WITH SUSTAINED SRV OPENING.

3.

DISCUSSION d.)

Pressure reduction may be augmented by:

(1)

SRV's in alphabetical sequence (2)

RWCU (Coolant Rejection) per OP-61-001 (RWCU System).

This procedure provides the direction necessary to select the proper method(s) to reduce RPV pressure at a controlled rate.

4.

REFERENCES a

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d.

e.

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EO-00-022 Cooldown EO-00-023 Containment Control OP-43-001 SJAE and Mechanical Vacuum Pump OP-44-001 Condensate and Feedwater System OP-45-001 Feedwater Turbine and Lube Oil System OP-50-001 Reactor Core Isolation Cooling System OP-52-001 High Pressure Coolant Injection System OP-61-001 Reactor Water Cleanup System OP-92-001 Steam Seal System GO-00-004 Reactor Shutdown from Minimum power Operation to Cold Shutdown Conditions

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PROCEDURE APPROVAL FORf Effective Date TITLE:

EO-00-027 RAPID DEPRESSURIZATION REVTSION 0

PAGE 1

OF 4

PORC REVIEW REQUIRED:

YES

(

) 'O

(

)

Meeting Number.

ORIGINATOR:

P.

E. Taylor APPROVALS:

DATE

'PERINTENDENT OF PLANT DATE 1.

ENTRY CONDITIONS This procedure is entered from,E0-00-023, E0-00-024, and EO-00-025 when it is required to rapidly depressurize the RPV.

2.

OPERATOR ACTIONS 2.a.

Ensure the reactor is in a shutdown condition.

FORM AD-00-001-1, Rev.

1 Page l of 1

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EO-00-027 Revision 0

Page 2 of 4 CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 110 PSIG UNLESS MOTOR DRIVEN PRiPS SUFFICIENT TO MAINTAINRPV WATER LEVEL ARE RUNNING AND AVAILABLEFOR INJECTION.

CAUTION COOLDOWN RATES ABOVE 100~F/HR MAY BE REQUIRED TO ACCOMPLISH THIS STEP.

2.b.

OPEN all ADS valves.

1)

IF all ADS valves CANNOT be opened then:

a)

OPEN other SRV's nearest the failed ADS valve until a TOTAL of six SRV's are open.

2)

IF IESS THAN three SRV's can be opened~ then AUGtiENT the pressure reduction by using the minimum number of the following systems required to depressurize the RPV.

Use in the order which minimizes radioactive release to the environment.

(a)

Main Condenser per GO-00-004 (b)

HPCI steam line per OP-52"001 (c)

RCIC steam line per OP-50-001 (d)

Other steam driven equipment:

(1)

Steam Jet Air Ejectors per OP-43-001 (2)

Steam to Reactor Feed Pumps per OP-45-001 (3)

Steam to Steam Seal Evaporator per OP-92-001 (4)

Main Condenser Deaerating Steam per OP-44-001

2.b.

(cont)

EO-00"027 Revision"0 Page 3 of 4 (e)

Reactor Water Cleanup (Coolant Rejection per OP-61-001.

ENSURE Chemistry samples and analyzes primary coolant prior to rejection.

(f)

Hain Steam Line drains (g)

RPV head vent 2.c.

IF suppression pool water level is below 22 feet, then initiate suppression pool make-up per OP-59-001 (Suppression Pool Cooling).

NOTE THIS STEP WIIL RESULT IN A LOSS OF., SPRAY TO THE DREKLL AND SUPPRESSION POOL.

2.d. IF suppxession chamber pressure CANNOT be maintained below t..

Pressure Suppression Limit of Figure E0-00-027-1, then entex EO-00-025 (RPV Flooding).

2.e.

IF RPV water level CANNOT be determined, then enter EO-00-025 (RPV Flooding).

3.

DISCUSSION A.

This procedure provides the direction necessary to rapidly reduce RPV pressure when less than 3 SRV's can be opened.

B.

Step 2.d.

takes credit fox spraying hte drywell via the break in the RPV pressure boundary.

For this reason, all injection systems are lined up to the RPV per EO-00-025 (RPV Flooding).

4.

REFERENCES a

b.

EO-00-023 Containment Control EO-00-024 Level Restoration c ~

d.

EO-00-025 RPV Flooding G0-00-004 Reactor Shutdown from Hinimum Power Operations to Cold Shutdown Conditions

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'I EO-00-027 Revision 0

Page 4 of 4 e.

f.

h.

OP-43-001 SJAE and Hechanical Vacuum Pump OP-44-001 Condensate and Feedwater System OP-45-001 Feedwater Turbine and Lube Oil System OP-92-001 Steam Seal System

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