ML20204H704

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Rev 3 to Emergency Operating Procedure EOP 3.1-0, Emergency Response Procedures
ML20204H704
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 02/05/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-3.1--1, EOP-3.1-0-01, NUDOCS 8810240459
Download: ML20204H704 (8)
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PROC DURE COV R hE FEB 051988 PROCEDURE NUMBER TITLE REV. NO.

EOP 3.10 Emergency Response Procedures 3 Major

WW R DATE Phil Rainha gjg gjgg DEPT.

Ops TECHNICAL REVIEW

[ OPERATIONS kka HEALTH PHYSICS

[ ENGINEERING CHEMISTRY

[ REACTOR ENGR. S%.did SECURITY -

[ MAINTENANCE STORES

[ INST. & CONTROL QA C ADMIN. RECORDS

(( ] X ( ops Verifiy ) [tbd/1

(( ] [ ]

QEPARTMENT HEAD REVIEW X YES COP.'PLETE/ B'ENNIAL REVIEW 7 NO PORC REVIEW REOUIRED? [YES]NO NWOR REVISCN? X YES NO ENVIRONNENTAL IMPACT 7 YES[NO A CH ANGE TO INTENT 7 X YES NO NA7 [YES WRITTEN SAFETY EVALUATON ATTACHED SAFETY EVALUATCN REQUIRED) X YES NO UNREVIEWED SAFETY OUESTICN? BYES [N3 r -

APPROVAL M \1 -bb FURC MEETL% NO DATE PROCEDtJRE EJHCTIVE DATI REQLl1RIS UCEASED OFE R ATOR RE\lEW '

, hI'f[ /-/' I l- [ ' YES h NO [ 8 0 87 ACP 1.2 6 5. Atta: reat 9 '

BC10240459 081007 PDR ADOCK 05000213 P PDR

EOP 3.1 0 Rev. 3 MAJOR EOP2 ENGJ Connecticut Yankee FEB 05 1 m Emergency Operating Procedure No.3.1 0 Operations Dept.

Emergency Response Procedures 1.0 DISCUSSION The Emergency Response procedures provide a network of predefined and prioritized symptom based response strategies for the management of emergency transients.

1.1 Approach

'The resultant guidance provides a systenutic approach that incorporates the following actions.

1.1.1 Evaluation of plant spnptoms

a. Formulation of an optimal recovery strategy resulting in an end state that mirumizes radiation release and equipment damage.

1.1.2 Explicit identification of the status of Critical Safety Functions independent of ev:nt scenano.

1.1.3 Restoration of Critical Safety Functions independent of event scenario.

1.2 Composition The Emergency Response Procedures art composed of three major elements.

l.2.1 Optimal Recovery Procedures 1.2.2 Critical Safety Function Status Trees 1.2.3 Function Restoration Procedures The proccdures and Status Trees that comprise the Emergency Response Procedures are provided in this volume.

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EOP 3.1 0 Rev. 3 MAJOR EOP2 ENGJ t -

FEB 0 a 1988 2.0 REVISIONS / SUMM ARY OF CHANGES ne following revisions and/or changes are incorporated as part of this procedure.

h0IE Changes and reasons for,:hange have been documented using note numbering. Following this section you will find a legend of note numbers that desenbe the change.

2.1 E 0, "Reactor Trip or Safety Injection", Rev. 2.

Step Change / Reason  ;

Back of page 2 Notes 1.5 Back of page 5 Note i Back of page 8 Note 1 I Back of page 9 Note 1 Preface (Ssmptoms) Notes 1.2 i s

2.2 ES 0.1,"Reactor Trip Response", Rev. 2.

  • Step Change / Reason Back of page 1 Notes 1.3 ,

Back of page 2 Notes 1.3  !

Back of page 4 Notes 1.9, and 10 '

Back of page 6 Note 1 2.3 ES.O.2,"Natural Circulation Cooldown" Rev. 2. l Step Change / Reason Back of page 3 Note 1 15.b.2 and note Note 11 2.4 ES 0 3."Natural Circulation Cooldown with Steam Vold in Vessel (with  !

RVLIS)", Rev. 2. j Step Change / Reason t Back of page 2 Note 1  !

7.b.2 and note Note 11  !

i 2.5 ES 0.4 "Natural Circulation Cooldown with Steam Vold in Vessel I (without RVLIS)", Rev. 2.

Step Change / Reason

[ Note on page 7 l Note i1 l l

?

f 2 of7 -

EOP 3,1 0 Rev. 3 MAJOR EOP2 ENG.i FEB 05 1 %-

2.6 E.1,"Loss of Reactor or Secondary Coolant", Rev. 2.

Step Change / Reason Back of page 2 Note i Back of page 4 Notes 1.4 Back of page 5 Note 1,4 2.7 ES.I.1,"S1 Termination", Rev.1.

Step Change / Reason Back of page 1 Notes 1,4 Back of page 3 Notes 1.9. and 10 Back of page 4 Note i Back of page 7 Note 1 2.8 ES.I.2 "Post LOCA Cooldown and Depressurization", Rev.1.

Step Change / Reason Back of page 1 Notes 1,4 -

Back of page 2 Note 1 Back of page 3 Note i Back of page 9 Note 1 Back of page 10 Notes 1.8 2.9 ES I.3, Transfer to RilR Recirculation", Rev. 3.

Step Change / Reason lVanous tMajor Rensioni l Notes 1.4. and 13 l 2.10 ES.I.4,"Transfer to Two Path Recirculation", Rev. 3.

Step Change / Reason QniousMajor Rewsion) l Note 13 l 2.11 E.2,"Faulted Steam Generator Isolation", Rev.1.

Step Change / Reason lBack of page 1 l Note 1 l 2.12 E 3."Steam Generator Tube Rupture" Rev. 2.

Step Change / Reason Back of pages 3.4,5.9.10 Note i

11. and 14 Back of page 13 Notes 1,4 Back of page 15 Notes 1,9. and 10 Back of page 17 Notes 1,8 Back of page 23 Notet 1,4 3 of 7

EOP 3.1 0 Rev. 3 MAJOR EOP2 ENG.J FEB 0 5198E 2.13 ES 3.1,"Post SGTR Cooldown Using Backfill", Rev. 2.

Step Chante/ Reason Back of page 1 Note t Back of page 4 Note 1 10.b.2 and note Note 11 2.14 ES.3.2 "Post SGTR Cooldown Using Blowdown", Rev. 2.

Step Change / Reason l8.b.2 and note l Note 11 l 2.15 ES.3.3 "Post SGTR Cooldown Using Steam Dump", Rev. 2.

Step Change / Reason Back of page i Note i ~' ~

Back of page 6 Note 1 8.b.2 and note Note 11 ,

2.16 ECA.O.0,"Station Blackout" Rev.1.

Step Change / Reason Back of page 2 Notes 1.6 Back of page 5 Note 1 Ta'ck of page 7 Note 1 Tlack of page 9 Notes 1.4 i Back of page 10 Notes 1.5 2.17 ECA.O.1,"Station Blackout Recovery Without SI Required". Rev.1.

Step Change / Reason Back of page 1 Notes 1.4 Back of page 4 Note 1 Back of page 6 Notes 1.9.10 Back of page 7 Note 1 Back of ptge 9 Notes 1.6 2.18 ECA.O.2,"Station Blackout Recovery With SI Required" Rev. 2.

Step Change / Reason Back of page 1 _ Notes 1.6 Back of page 3 Note 1 2.19 ECA.I.1,"Loss of Emergency Coolant Recirculation", Rev. 2.

Step Change / Reason lBack of page 2 l Notes 1,4 I F

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EOP 3.1 0

$[)"P2 @ @ 1986 ENG J 2.20 ECA 2.1,"Uncontrolled Depressurization of ALL Steam Generators",

Rev. 2.

Ste3 Change / Reason

35. ).2 and note Note 11 Back of pages 3 and 4 Nottes 1,4 Back of page 5 Note 1 Eack of page 6 Notes 1,9. and 10 Back of page 8 Notes 1. 6 Back of page 9 Notes 1,8

~

2,21 ECA 3,1,"SGTR With Loss of Reactor Coolant Subcooled Recovery Desired" Rev.1.

Step Change / Reason Back of gages 1 and 17 Notes 1,4 Back of pages 3 and 4 Note 1 Back of page 13 Notes 1,8 2.22 ECA.3.2,"SGTR With Loss of Reactor Coolant, Saturated Recovery Desired" Rev.1.

Step Change / Reason Back of pages 2,3 and 5 Note i Eack of page 16 Notes 1,4 2.23 ECA 3.3,"SGTR Without Pressurizer Pressure Control". Eev. 2.

Step Change / Reason Back of pages 2,6,8 and 12 Note 1 Back of page 4 Notes 1,4 Back of page 5 Notes I,9. and 10 2.24 FR.0.4,"RCS Integrity Status Tree", Rev. 2.

Step Change / Reason IBottom of logic block l Note i1 l 2.25 FR.C.1,"Response to Inadequate Core Cooling". Rev.1.

Step Change / Reason IBack of page 2 l Note 1 l 5 of7

EOP 3.1 0 Rev. 3 MAJOR EOP2

\

ENG.J FEB 0 6 1985 2.26 FR.C.2,"Response to Degraded Core Cooling", Rev.1.

Step Chanre/ Reason lBack of page 3 l Note l l

2.27 FR.H.1,"Response to Loss of Secondary Heat Sink", Rev. 2.

Step Change / Reason Back of page 3 Note 1 Back of page 8 Notes 1.4 Attachment A, Step 8 Note 7 2.28 FR ll.3,"Response to Steam Generator High Level", Rev. 2.

Step Change / Reason lBack of page 1 l Note 1 l 2.29 FR ll.5,"Response to Steam Generator Low Level", Rev.1.

  • Step Change / Reason lBack of page 1 l Note 1 l 2.30 FR.P.1,"Response to Imminent Pretsurized Thermal Shock Condition",

Rev. 2.

Step Change / Reason Back of page 3 Notes 1.4 Back of page 6 Note 1 Back of page 7 Notes 1.9 and 10 2.31 FR.Z.1,"Response to liigh Containment Pressure" Rev.1.

Step Change / Reason lBack of page 1 l Notes 1.5 l 2.32 FR.I.1,"Response to liigh Pressurizer Level", Rev. 2.

Step Change / Reason IBack of page 2 l Notes 1.9. and 10 l 2.33 FR.I.3 "Response to Volds in Reactor Yessel" Rev. 2.

Step Change / Reason IBack of page 2 l Notes 1.9, and 10 l 6 of 7

EOP 3.1 0 ,

Rev. 3 MAJOR i EOP2 '

ENG J FEB 0 5 1986 2.34 Attachment A to EOPs, Rev. 2 L Step Chante/ Reason  !

Vanous Note 2 l Page 3. Last paragraph Note 14 i Reason Codes

1. Format changes and clarification in tesponse to NRC and INPO EOP review comments. I
2. Relocrted note on PASS valves, removed reference to man"al trip buttons, and l

i changed the logic for VLirr (PDCR.861). -

3. Removed reference to checking pressuitzer pressive (confusing and not necessary) L l

4 Added guidance to rtalign htCB operated containment isolation valves. [

. F

5. Added note regarding PASS valves per amendment 72.  !
6. Rearranged order of steps and and added guidance to check trip signal removed pnor i to resetung undervoltage lockout relays.

l

7. Incorporate addition of ACP override switch on LD TV 230(PDCR 878) l
8. Added guidance to ensure SI WLs are reset prior to resetting the EDG lockout relayt,  !

l

9. Included new valve LD TV 230 (PDCR 878).
10. Changed to conform with WOG ERG's regarding establishment of letdown w hen centamment pressure is greater than five psig.

f

11. Changed to reflect the ttvised temperature requirement for LTOPs (340 F to 315 F)
12. hiinor changes to increase clarity of statements.

I

13. ES 1.3, and ES 1.4 were revised (major revision) to meet the following requirements:. i
a. Westinghouse me norandum 87 255, dated hiay 29,1987,concerning recirculation switchover rime.
b. Proside guidance in the event of a clogged RHR sump suction (CR 871063) ,
c. NRC and INPO EOP resiew comments on EOP formatting and guidance i provided to operators.

i

d. Added direction to operate CH V 286 and CH V 2868 if CH htOV 2928 and i CH htOV 292C do not go fully closed. '
e. Incorporated changes to htCB switch operation resulting from PDCR 861 [
14. Added statement regarding use of correlation between RHR flow and RHR amps.  !

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