ML20065T148: Difference between revisions

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| number = ML20065T148
| number = ML20065T148
| issue date = 12/18/1990
| issue date = 12/18/1990
| title = Rev 6 to Emergency Operating Procedure EOP-12.0, Monitoring of Critical Safety Functions.
| title = Rev 6 to Emergency Operating Procedure EOP-12.0, Monitoring of Critical Safety Functions
| author name = Karbach R, Naylor G
| author name = Karbach R, Naylor G
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.

Latest revision as of 02:46, 6 January 2021

Rev 6 to Emergency Operating Procedure EOP-12.0, Monitoring of Critical Safety Functions
ML20065T148
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/18/1990
From: Karbach R, Naylor G
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20065T147 List:
References
EOP-12.0, NUDOCS 9012270285
Download: ML20065T148 (13)


Text

_ _ _ _ _ _ _ . _ _ - _ . . - _ . _ . - _ . __ . . _ __ _ . . _ _ . _.

SOUTH CAROLI!1A ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS EMERGE!1CY OPERATING PROCEDURE

' EOP-12.0 MONITORING OF CRITICAL SAFETY FUNCTIONS REVISION 6 SAFETY RELATED k ( c_. - T-/ - Yo DISCIPLINE SUPERVISOR DATE wJ ,WlHCQTY 1PPROVAL nkn F-s)-re DATE i

RECORD OT, CHANGES CHANGE TYPE EFFECTIVE DATE CHANGE TYPE EFFECTIVE DATE L DATE CANCELLED NO. CHANGE DATE CANCELLED NO. CHANGE l

9012270285 901218 PDR ADOCK 05000395 l

- P PDR Next Two Year Review required no later than b'b' b .

l (Date)

. i '

SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS EMERGENCY OPERATING PROCEDURE EOP-12.0 MONITORING OF CRITICAL SAFETY FUNCTIONS REVISION 6 SAFETY RELATED

- n

i 4 t t 4 c. 9 Yo DISCIPLINE SUPERVISOR DATE W/ q h-* k- [F DATE APPROVA) #UTHC$TY RECORD OF CHANGES CHANGE TYPE EFFECTIVE DATE CHANGE TYPE EFFECTIVE DATE NO. CHANGE DATE CANCELLED NO. CHANGE DATE CANCELLED 9012270285 901218 PDR ADOCK 05000395 P PDR Next Two Year Review required no later than ~ b'b b .

(Date)

. i .

E0P-12.0 REVISION 6 MONITORING OF CRITICAL SAFETY FUNCTIONS

_ TABLE OF CONTENTS SECTION f.$5.

PURPOSE 1 ENTRY CONDITIONS 1 OPERATOR ACTIONS 2 ATTACHMENTS Attachment 1 - Subcriticality 5 Attachment 2 - Core Cooling 6 Attachment 3 - Heat Sink 7 Attachment 4 - Integrity 8 Attachment 5 - Containment 10 Attachment 6 - Inventory 11 Attachment 7 - Critical Safety Function Status 12 l

l PAGE i

E0P-12.0 REVISION 6 I MONITORING OF CRITICAL SAFETY FUNCTIONS I

ten This procedure provides instructions for monitoring Critical Safety Functions during an emergency situation. By continuously maintaining the Critical Safety Functions satisfied, the integrity of the fuel matrix, the fLei clad, the RCS pressure boundary and the Containment is assured, thus minimizing the possibility of radiation releases.

This procedure also provides a direct interface between monitoring of conditions within the station and the emergency classification of the event which is accomplished in EPP-001, ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN.

Instructions are given for monitoring Critical Safety functions using the Status Trees attached to this procedure with the Integrated Plant Computer i System or with Main Control Board indications. JE the monitoring process

! indicates that a Critical Safety Function is NOT satisfied,.THf,!! the appropriate procedure is referenced from the Status Tree.

! The Critical Safety Function Status Trees in order of priority are:

SUBCRITICALITY CORE COOLING HEAT SINK INTEGRITY CONTAINMENT l

! INVENTORY l ENTRY CONDITIONS l 1. This procedure is monitored for information only during the performance of E0P-6.0, LOSS OF ALL ESF AC POWER.

2. This procedure is enterea from:

!

  • E0P-6.1, LOSS OF ALL ESF AC POWER RECOVERY WITHOUT SI REQUIRED.
  • E0P-6.2, LOSS OF ALL ESF AC POWER RECOVERY WITH SI REQUIRED.
  • Any time a transition is made from E0P-1,0. REACTOR TRIP / SAFETY INJECTION ACTUATION to any other E0P.

PAGE 1 0F 12

> i

  • E0P-12.0 REVISION 6 HONITORING OF CRITICAL SAFETY FUNCTIONS ACTION / EXPECTED RESPONSE ALTERNATIVE ACTION I

OPERATOR ACTIONS EQlE

  • The monitoring of Critical Safety Functions begins after any transition from E0P-1.0, REACTOR TRIP / SAFETY INJECTION ACTUATION, to any other Emergency Operating Procedure.
  • The results of Critical Safety Function monitoring will be circled on Attachment 7 and given to the Control Room Supervisor.

NOTE - Steo 1 Critical Safety Function Attachments are arranged in order of priority.

1 Determine the status of the Critical Safety Functions:

a. Press F1 on the Integrated C a. Monitor Critical Safety 0 Plant Computer System to Functions using Main Control display Critical Safety Board indications. REFER TO Functions. Attachments 1 through 6.

GO TO Step 1.'.:. O

b. Press the appropriate Function O Key to display the page for any Critical Safety Function which is not GREEN.
c. Progress through the Status 0 Tree until a branch end is reached.

(Step 1 continued on next page) (Step 1 continued on next page)

PAGE 2 0F 12

, i ,

j ,

i bN6 MONITORING OF CRITICAL SAFETY FUNCTIONS ACTION / EXPECTED RESPONSE ALTERNATIVE ACT10l4 (Step 1 continued) (Step 1 continued) d Examine the branch path:

1) A RED path signifies the Critical Safety function is extremely challenged:

a) Verify a RED path exists. O a) GO TO Step 1.d.2). O b) Notify the Control Room O Supervisor to GO T0 the Procedure referenced at the end of the highest priority RED path, c) REFER TO EPP-001, O ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN, to classify the event, d) Inform the Shift O Supervisor of any RED path indications.

2) An ORANGE path signifies the Critical Safety Function is severely challenged:

a) Complete monitoring of C the remaining Status Trees to identify any RED paths.

b) Verify nq RED paths O b) RETURN TO Step 1.d.1). O exist, c) Verify an ORANGE path 0 c) GO TO Step 1.d.3). O exists.

d) Notify the Control Room C Supervisor to GO T0 the Procedure referenced at the end of the highest priority ORANGE path.

(Step 1 continued on next page) (Step 1 continued on next page)

PAGE 3 0F 12

, 's .

E0P-12.0 REVISION 6 MONITORING OF CRITICAL SAFETY FUNCTIONS ACTION / EXPECTED RESPONSE ALTERNATIVE ACTION (Step 1 continued) (Step 1 continued)

3) A YELLOW path signifies the Critical Safety Function is NOT satisfied:

a) Verify a YELLOW path O a) GO TO Step 2. Observe C exists. the NOTE prior to Step 2.

b) Notify the Control Room O Supervisor to GO T0 the Procedure referenced at the end of the highest priority YELLOW path at his discretion.

NOTE - Sten 2 Critical Safety Function monitoring should continue if either the Reactor Protection System M the Engineered Safeguards System is inoperable.

2 Continue monitoring the Critical O Safety Functions until normal conditions are restored M the plant is in Cold Shutdown.


l End of E0P-12.0 1-----------

PAGE 4 0F 12

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. E0P-12.0 l

- REVISION 6 ATTACHMENT 4 PAGE 2 0F 2 4

INTEGRITY PLANT OPERATIONAL LIMITS CURVE RCS PRESSURE (PSIG) 3000 2560 PSIG (PZR SAFETY VALVES ASSUMED FULL OPEN)

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2500 220'F ~~~~~~

2000 - 2050 PSIG f REGION OF

[ ACCEPTABLE OPERATION 1500-f . . . . . LIMIT T2 275'F 1000 l

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_. _ -_ -_