ML20205A700

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Change 1 to Rev 2 to Emergency Operating Procedure EOP 2540E, Functional Recovery of Containment Integrity
ML20205A700
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 01/28/1987
From: Mroczka
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-2540E-01, EOP-2540E-1, NUDOCS 8810260073
Download: ML20205A700 (9)
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Docket No. 50-423 A07413 Attachment 4 Hillstone (Nelear Power Station, Unit No. 3 Emergency Operating Procedures October 1988

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3500 UNIT 3 EMERGENCY OPERATING PROCEDURES INDEX NUMBER TITLE REV. 2FF. DATE AOP 3550 Turbine / Generator Trip 0 11/16/85 AOP 3551 DC Bus Ground 0 10/30/86 AOP 3552 Malfunction Of The Red Drive System 0 12/02/85 A0P 3553 High Reactor Coolant System Activity 1 11/06/85 AOP 3554 RCP Trip or Seal Failure 1 12/17/85 AOP 3555 Reactor Coolant Leak 0 12/10/85 AOP 3556 Steam Generator Tube Leak 0 11/09/85 A0P 3557 Secondary Chemistry 1 11/06/85 AOP 3558 Condenser Tube Leak 0 11/21/85 AOP 3559 Loss of Condenser Vacuum 0 11/21/85 A0P 3560 Loss of Service Water 0 11/21/85 A0P 3561 Loss of Reactor Plant Component 1 10/21/86 Cooling Water A0P 3562 Loss of Instrument Air 0 10/25/85 AOP 3563 Loss of a DC Bus 0 12/30/85 A0P 3564 Loss of One Protective System Channel 1 11/06/85 AOP 3565 Loss of Containment Vacuum / Integrity 0 12/05/85 AOP 3566 Immediate Boration 1 12/26/85 AOP 3567 Operation With A Feedwater Heater 0 12/05/85 String Isolated AOP 3568 Emergency Breaking of Containment Vacuum 0 03/23/87 AOP 3569 Severe Weather Conditions 2 05/21/87 AOP 3570 Earthquake 1 12/14/87 AOP 3571 Instrument Failure Response 1 12/01/87 AOP 3572 Failure of Refueling Cavity Seal 1 10/28/87 AOP 3573 Radiation Monitor Alarm Response 1 05/26/87 PORC APPROVAL REQUIRED Rev. 44 06/16/88 Page 1 of 4

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UNIT 3 EMERGENCY OPERATING PROCEDURES INDEX ,

j 3 NUMBER TITLE REV. EFF. DATE :

E0P 3502 Fuel Handling Accident. 0 09/14/84 -

! E0P 3503 Shutdown Outside Control Room 4 01/24/87 i E0P 3504 Cooldown Outside Control Room 2 11/05/85  !

! l E0P 3505 Loss of 3hutdown Cooling (RHR) 1 11/05/87 l

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] E0P 3506 Loss of All Charging Pumps 0 10/09/85 i E0P 3509 Fire Emergency 5 06/15/88  !

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! E0P 35 E-0 Reactor Trip er Safety Injection 2 06/15/88 l i  ;

E0P 35 E-1 Loss of Reactor or Secondary Coolant 2 06/15/88 j j E0P 35 E-2 Faulted Steam Generator Isolation 2 06/15/88 l E0P 35 E-3 Steam Generator Tube Rupture 2 06/15/88 l E0P 35 ES-0.0 Rediagnosis 1 12/13/85  !

E0P 35 ES-0.1 Reactor Trip Response 3 06/15/88 l {

l E0P 35 ES-0.2 Natural Circulation Cooldown 2 06/15/88  !

E0P 35 ES-0.3 Natural Circulation Cooldown With 1 12/13/85

, Steam Void In Vessel (With RVLMS)

E0P 35 ES-0.4 Natural Circulation Cooldown With 2 06/15/88 l Steam Void In Vessel (Without RVLMS) (

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! E0P 35 ES-1.1 SI Termination 4 06/15/88 l I l

! E0P 35 ES-1.2 Post LOCA Cooldown and Depressurization 2 06/15/88 j i i I E0P 35 ES-1,3 Transfer to Cold Leg Recirculation 2 06/15/88 f

' i E0P 35 ES-1.4 Transfer to Hot Leg Recirculation 2 06/15/88 l

} E0P 35 ES-3.1 Post-SGTR Cooldown Using Backfill 2 06/15/88 {

E0P 35 ES-3.2 Post-SGTR Cooldown Using Blowdown 2 06/15/63 i

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i E0P 35 ES-3.3 Post-SGTR Cooldown Using Steam Dump 2 06/15/88 i i t

) E0P 35 ECA 0.0 Loss of All AC Power 3 06/15/88 1-i E0P 35 ECA-0.1 Loss of A11 AC Power Recovery Without 2 06/15/88 l SI Required a

4 PORC APPROVAL REQUIRED Rev, 44 Ob/16/88 1 Page 2 of 4 l

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3500 UNIT 3 EMERGENCY OPERATING PROCEDURES INDEX NUMBER TITLE REY. EFF. DATE E0P 35 ECA-0.2 Loss of All AC Power Recovery With SI 2 06/15/88 Required EOF 35 ECA-1.1 Loss cf Emergency Coolant Recirculation 2 06/15/88 E0P 35 ECA-1.2 LOCA Outside Containment 1 12/13/85 E0P 35 ECA-2.1 Uncontrolled Depressurization of All 2 06/15/88 Steam Generators E0P 35 ECA-3.1 SGTR With Loss of Reacter Coolant - i 06/15/88 Subcooled Recovery Desired E0P 35 ECA-3.2 SGTR With Loss of Reactor Coolant 2 06/15/88 Saturated Recoviry Desi ed E0P 35 ECA-3.3 SGTR Wiihout Pressurizer Pressure 2 06/15/88 Control E0P 35 FR-C.1 Response to Inadequate Core Cooling 2 06/1 '88 E0P 35 FR-C.2 Response to Degraded Core Cooling 2 06/15/88 E0P 35 FR-C.3 Response to Saturated Core Conditions 1 12/13/85 E0P 35 FR-H.1 Response to Loss of Secondary Heat Sink 1 12/13/85 E0P 35 FR-H.2 Response to Steam Generator Overpressure 1 12/13/85 E0P 35 FR-H.3 Respt.,se to Steam Generator High Level 1 12/13/85 E0P 35 FR-H.4 Response to loss Of Normal Steam 1 12/13/85 Release Capabilities E0P 35 FR-H.5 Response to Steam Generator Low Level 1 12/13/85 E0P 35 FR-I.1 Response to High Pressurizer Level 1 12/13/85 E0P 35 FR-I.2 Response to Low Pressurizer Level 1 12/13/85 E0P 35 FR-I.3 Response to Voids In Reactor Vessel 2 06/15/88 E0P 35 FR-P.1 Response to Imminent Pressurized 2 06/15/88 Thermal Sheck Condition E0P 35 FR-P.2 Response to Anticipated Pressurized 2 06/15/88 Thermal Shock Condition E0P 35 FR-S.1 Response to Nuclear Power Generation /ATWS 2 06/15/88 E0P 35 FR-5.2 Response to Loss of Core Shutdown 2 06/15/88 PORC APPROVAL REQUIRED Rev. 44 06/16/88 Page 3 of 4

. 3500 UNIT 3 EMERGENCY OPERATING PROCEDURES INDEX

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NUMBER TITLE REV. EFF. DATE E0P 35 FR-Z.1 Response to High Containment Pressure 2 06/15/88 E0P 35 FR-Z.2 Response to Containment Flooding 1 12/13/85 E0P 35 FR-Z.3 Response to High Containment 1 12/13/85 Radiation Level f

n PORC APPROVAL REQUIRED Rev, 44 06/16/88 Page 4 of 4

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3500 UNIT 3 EMERGENLY OPERATING FORMS INDEX OPS FORM NUMBER TITLE REV. EFF. DATE E0P 3505-1 Decay Heat Flow Rate Versus Time After Trip 0 11/05/87 (100% Power History)

EUP 3505-2 NPSH vs RHR Flow 0 11/05/87 (with level of center line of hot leg)

E0P 35 ECA-1.1-1 Minumum SI Flow Rate Versus Time After Trip 0 06/15/88 E0P 35 ECA-3.1-1 RWST Level Versus Containment Sump Level 0 06/15/88 E0P 35 F-0.3 Subcriticality 0 01/10/86 l

E0P 35 F-0.2 Core Cooling 0 01/10/86 EUP 35 F-0.3 Heat Sink 0 01/10/86 E0P 35 F-0.4 Integrity 0 01/10/86 E0P 35 F-0.5 Containment 0 01/10/86 E0P SS F-0.6 Inventory 0 01/10/86 E0P 35 FR-I.3-1 Hydrogen Flow Rate Versus RCS Pressure 0 06/15/88 E0P 35 FR ?.1-1 Post Soak Cooldown Limit Normal Errors 0 06/15/88 E0P 35 FR-P.1-2 fost Soak Cooldown Limit Adverse Errors 0 06/15/88 E0P 35 FR-P.2-1 Cooldown Limit Normal Errors 0 06/15/88 E0P 25 FR-P.2-2 Cooldown Limit Adverse Errors 0 06/15/88 PORC APPROVAL REQUIRED Rev. 2 06/09/88 Page 1 of 1

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