ML20077A719

Noncontrolled Version of Rev 3 to Emergency Operating Procedure EOP-10, Malfunction of Control Rod Sys

ML20077A719
Person / Time
Site:	Summer
Issue date:	12/29/1982
From:	Thibau H, Woodward K SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20077A625	List: ML20077A623 ML20077A632 ML20077A641 ML20077A719
References
EOP-10, NUDOCS 8307220413
Download: ML20077A719 (17)

Text

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I SOUTH CAROLI!!A ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION

• NUCLEAR OPERATIONS g. . , .

6 d' h ? 11 ]

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. EMERGENCY OPERATING PROCEDURE E0P-10 MALFUNCTION OF CONTROL ROD SYSTEM REVISION 3 DECEMBER 20, 1982 bo SAFETY RELATED Reviewed by:

ud 1l )

" /2-8"8A O IGIITA'A R (of this evision) Date

/ M_ . / l DISCIPLINE SUPERVISOR ' Db.t e Appe ved:

pg l' }

,. , - - E y -

' Date Issued: JAN10 2 O

O B307220413 830712 PDR ADOCK 05000395 P PDR

E0P-10

- . PAGE i I

• REVISION 3

, 12/20/82 MALFUNCTION OF ROD CONTROL SYSTEM PAGE SECTION 1

I. PURPOSE

-- 1 II. CONDITIONS 1

A. CONTINUOUS CONTROL ROD MOTION 1

1.0 SYMPTOMS 1

2.0 AUTOMATIC ACTIONS 2'

30 IMMEDIATE CORRECTIVE ACTIONS 3

4.0 FOLLOW UP ACTIONS 3

50 FINAL CONDITION 4

4 B. CONTROL RODS FAIL TO MOVE 4

1.0 SYMPTOMS 4

2.0 AUTOMATIC ACTIONS 4

30 IMMEDIATE CORRECTIVE ACTIONS 4

4.0 FOLLOW UP ACTIONS l 5 50 FINAL CONDITIONS 6

C. STUCK OR MISALIGNED CONTROL ROD 6

1.0 SYMPTOMS 6

- 2.0 AUTOMATIC ACTIONS 6

, c 30 IMMEUSAT' CORRECTIVE ACTIONS 7

N 4.0 17J '.Q , ! ACTIONS i

' 10

! 50 FINAL CONDITIONS

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E0P-10

, , PAGE 11 REVISION 3 12/20/82 MALFUNCTION OF ROD CONTROL SYSTEM PAGE SECTION 11 D. DROPPED CONTROL ROD ._

11 1.0 SYMPTOMS 11 2.0 AUTOMATIC ACTIONS 11 3.0 IMMEDIATE CORRECTIVE ACTIONS 12 4.0 FOLLOW UP ACTIONS 14 50 FINAL CONDITION 15 VI. REFERENCES

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EOP-10 REVISION 3 12/20/82 I. PURPOSE This Emergency Operating Procedure outlines the actions required in the event of a malfunction of the Rod Control System, in order to return the Reactor to a long term safe operating condition.

II. CONDITIONS A. CONTINUOUS CONTROL ROD MOTION 1.0 SYMPTOMS 1.1 Unwarranted Control Rod motion as indicated by Step Counters and Lisital Rod Pccition Indication.

1.2 RCS TAVG-TREF DEV HI/LO annunciator alarms.

13 RCS T AVG DEV HI/LO annunciator alarms.

1.4 CRB INSRT LMT LO annunciator alarms.

15 CRB INSRT LMT LO-LO annunciator alarms .

1.6 Incre.asing Reactor, power without an accompanying Turbine load increase.

1.7 'CMPTR ' FLUX LMT EXCEEDS annunciator alarms.

1.8 RCS LOOP A, B, or C HIGH TAVG annunciator alarms.

2.0 AUTOMATIC ACTIONS 2.1 Continuous uncontrolled rod motion may result in a Reactor Trip due to one of the following:

a. High Flux Reactor Trip for control rod withdrawl.

b. Low Pressure Reactor Trip for control rod insertion.

2.2 Continuous control rod withdrawal actuates the following:

a.

Intermediate Range High Neutron Flux Rod Stop, if not blocked.

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• b. PowenrRange High/ Flux Rod Stop, if above 25% reactor -

power.

PAGE 1 0F 15

EOP-10 REVISION 3 12/20/82

c. Overtemperature AT Auto Turbine Runback / Block Rod Withdrawal.

d. Overpower AT Auto Turbine Runback / Block Rod Withdrawal.

30 IMMEDIATE CORRECTIVE ACTIONS ACTIONS ALTERNATIVE ACTIONS 31 If a reactor trip has occurred, proceed to EOP-5 Verify that a turbine 32 If a turbine load 32 load rejection is not in rejection or runback has occurred, refer to progress. GOP-4, Attachment III Rotate ROD CNTRL SEL 33 If uncontrolled control 33 switch to MAN position. rod motion continues in MANUAL mode,

a. Trip Reactor.

b. Proceed to E0P-5 3.4 Stop any turbine load changes in progress.

35 Return Tavg to within

+ 1.5 F of Tref.

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E0P-10 REVISION 3 12/20/82 II. A Continued:

4.0 FOLLOW UP ACTIONS NOTE 4.0 Initial each step whsn it is completed.

ACTIONS ALTERNATIVE ACTIONS 4.1 If control rods movement stopped when control was shifted to MANUAL,

a. Continue operation in manual rod control.

b. Determine cause of malfunction and initiate repairs.

50 FINAL CONDITIONS 51 Plant is in a stable operating condition except the reactor is being c'ontrolled with the Rod Control System in MANUAL.

52 continued plant operation is being conducted by the applicable GOP.

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1 PAGE 3 0F 15

1 E0P-10

. . REVISION 3 12/20/82

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B. CONTROL RODS FAIL TO MOVE 1.0 SYMPTOMS 1.1 Control rods fail to move in Automatic during Turbine load or Reactor Coolant System temperature changes.

1.2 RCS TAVG-TREF DEV HI/LO annunciator alarms.

1.3 RCS TAVG DEV HI/LO annunciator alarms.

1.4 ROD CNTRL SYS FAIL URGENT annunciator alarms.

2.0 AUTOMATIC ACTIONS None.

3.0 IMMEDIATE CORRECTIVE ACTIONS ALTERNATIVE ACTIONS ACTIONS 31 Rotate ROD CNTRL SEL switch to MAN-position. ,

32 Stop any Turbine load changes in progress.

Position Control Rods to 33 If Control Rods fail to 33 move in MANUAL, adjust return Tavg to within I

+ 1.5 F of Tref. Turbine load to return

- Tavg within + 1 5'F of Tref.

4.0 FOLLOWUP ACTIONS _

NOTE 4.0 Initial each step when it is completed.

e

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l EOP-10

.. . REVISION 3 12/20/82 II B Continued:

ALTERNATIVE ACTIONS ACTIONS 4.1- If Control Rods move in MANUAL control, proceed as follows: ..

a. Continue plant operation in MANUAL Rod Control.

b. Determine cause of malfunctions and initiate repairs.

- NOTE 4.2 If Control Rods are inoperable, the plant must be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4.2 Manually trip the 4.2 If Control Rods fail Reactor and proceed to move in Automatic or to EOP-5.

Manual rod control, proceed as follows:

a. Borate the Reictor Coolant System per SOP-106 at a rate which will allow for Turbine unloading.

b. Ramp Turbine to minimum load (50MW), maintaining Tref within + 3 to 5*F of Tavg.

c. Manually trip the Reactor and proceed j

' to EOP-5 5.0 FINAL CONDITIONS l

51 Plant is in a stable operating condition except the l

Reactor is being controlled with the Rod Control System

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Manual.

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52 Plant is in the Hot Standby mode with all Shutdown and Control Rods inserted into the core.

PAGE 5 OF 15

E0P-10 REVISION 3 12/20/82

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C. STUCK OR MISALIGNED CONTROL ROD 1.0 SYMPTOMS 1.1 One or more Control Rod (s) are inoperable or misaligned '

from the Group Step Counter demand position by more than 1 12 steps.

1.2 Disagreement between Group Step Counters for the same bank.

1.3 Digital Rod Position Indicater System indicates one or more Control Rods misa11gned from the Rod Bank position by more than i 12 steps.

1.4 CMPTR ROD DEV/ SEQ NIS PR TILTS annunciator alarms.

1.5 PR UP DET FLUX HI DEV AUTO DEFEAT annunciator alarms.

1.6 PR CHAN DEV annunciator alarms.

1.7 Core thermocouples and/or in-core nuclear flux map indicates a flux tilt.

2.0 AUTOMATIC ACTIONS 2.1 None 30 IMMEDIATE CORRECTIVE ACTI'ONS ALTERNATIVE ACTIONS ACTIONS i 31 Stop any Turbine load changes in progress.

32 Place Rod CNTRL BINK SEL l in MAN.

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E0P-10

.. .- REVISION 3 12/20/82 II. C Continued:

4.0 FOLLOWUP ACTION ACTI ~ ALTERNATIVE ACTION NOTE 4.0

a. If rods cannot be placed in proper alignment, l

the plant must be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. Refer to Technical Specification 3 1.3.1.

NOTE 4.0 Initial each step when it is completed.

4 .1 Monitor the Digital Rod Position Indicator and Step . connectors to determine the following:

a. Which rod (s) are misaligned.

b. Which Rod Control Bank is affected.

c. The direction of the misalignment, either high or low.

4.2 Recocd all Control Rod positions and Step 09unter positions.

4.3 Rotate ROD CNTRL SEL switch to the affected bank position.

4.4 Drive the Control Rod Bank in 6 steps while

-

• monitoring rod positica -

indications, then out to the original position.

P AGE 7 0F 15

E0P-10

.. . REVISION 3 12/20/82 II. C Continued:

ALTERNATIVE ACTIONS ACTIONS 4.5 If misaligned Control 4.5 If misaligned control Rod (s) failed to move, Rod (s) moved, proceed as proceed as follows:

follows: ,_

Place all Lift Coil c. Determine if the

a. Control Rod (s)

Disconnect Switches for failed to move the affected Bank, except for the misaligned as a result of Control Rods, to the mechanical Disconnect position. interference or a Rod Control system (located in Control Rod malfunction.

Disconnect Switch Box, inside Main Control Board).

Note b.

Note b.

ROD CNTRL SYS FAIL If Control Rods are immovable the Shutdown margin must be UdGENT annunciator determined within one hour will alarn. and the plant being in HOT

+- STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

i

b. If failure to move

b. Drive the Control is due to mechanical Rod Bank in the interference proceed direction opposite of the direction of as follows:

misalignment.

1) Within one hour complete STP. 134.001,

c. Verify that only the Shutdown Margin misaligned Control Calculation.

Rod (s) moved.

Maintain Tavg within 2) Borate the Reactor

d. coolant System per iby 3 one F to of 5 the P offollowing:

Trer SOP-106 at a rate' which will allow for Turbine unloading.

1) Adjust Turbine Load.

3) Ramp Turbine to

2) Borate or Dilute per minimum load (50mw),

SOP-106. maintaining Tref l within i 3 to 5 F of Tavg.

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E0?-10

. . . . REVISION 3 12/20/82 II. C Continued:

ALTERNATIVE ACTIONS ACTIONS (4 5 6 Continued)

4) Manually trip the

e. Continue Control Rod Reactor and proceed to movement until the E0P-5 misaligned Control Rod (s~T are re-aligned with the Control Rod Bank. c. If failure to move is Reset the Control Bank due to a Rod Control f.

Group Step Counters to System malfunction, indicate the perviously proceed as follows:

recorded positions.

- 1) Rotate ROD CNTRL Place all Lift Coil SEL switch to the

g. affected Bank Disconnect Switches to the position.

Connected position (located in Control Rod Disconnect 2) Drive the Control Switch Box, inside Main Bank as necessary to Control Board). achieve alignment with the misaligned

h. Initiate applicable sections Control Rod (s).

of STP-106.001 to verify cod operability.

3) Maintain Tavs within

1. Rotate ROD CNTRL SEL switch

+ 3 to 5 F of Trer one of the following:

to MAN position.

a) Adjust Turbine load

j. Depress ROD CNTRL ALARM RESET. b) Borate or Dilute per Proceed to applicable SOP-106.

k.

procedures for normal plant 4) Rotate ROD CNTRL SEL operations. Switch to MAN.

5) Refer to Technical Specification 3 1.3 1 for ACTION requirements.

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I E0P-10

. . . - . REVISION 3 12/20/82 II C Continued:

50 FINAL CONDITION 51 Stuck or misaligned control rods have been restored to operable status and plant has been returned has to normal, been at power, operating conditions and STP-106.001 satisfactorily completed.

or 5.2 The Control Rod Bank has been realigned with the misaligned Control Rods and the applicable Actions statement of Technical Specification 3 1.3.1 implemented.

or 53 The Reactor is in a HOT STANDBY mode with all Shutdown and Control Rods inserted into the core.

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E0P-10 r,o ,

REVISION 3 12/20/82 D. DROPPED CONTROL ROD 1.0 SYMPTOMS 1.1 ONE ROD ON BOTTOM annunciator alarms.

1.2 RB indicator illuminated on Digital Rod Position indicator.

13 PR CHAN DEVIATION annunciator alarms.

1.4 CMPTR/ ROD DEV/ SEQ NIS PR TILTS annunciator alarms.

1.5 RCS TAVG-TREF DEV HI/LO annunciator alarms.

1.6 PZR PCS LO BU HTRS ON annunciator alarms.

2.0 AUTOMATIC ACTIONS 2.1 Control Rods withdraw at-maximum rate until blocked by Bank D Full Rod Withdrawal Interlock.

2.2 Possible Reactor Trip due to one of the following:

a. P.R Negative Rate Trip.

b. Low Pressurizer Pressure Trip.

30 IMMEDIATE CORRECTIVE ACTIONS ALTERNATIVE ACTIONS ACTIONS 31 If Reactor Trip has 31 Decrease Turbine load occurred, proceed to to match Tavg to within E0P-5

+ 3 to 5 F of Tref.

32 Rotate ROD CNTRL BANK SEL switch to MAN.

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E0P-10

, , , , REVISION 3 12/20/82 II D Continued:

4.0 FOLLOWUP ACTIONS Note 4.0 Initial each step when it is completed.

ALTERNATIVE ACTIONS ACTIONS 4.1 Stabilize plant such 4.1 If CMPTR ROD DEV/ SEQ that the following NIS PR TILT annunciator is alarmed, refer to conditions exist: Technical Specification /

a. Tavg is within + 3 2 for ACTION STATEMENTS power 1.5 F of Tref. restrictions.

b. Reactor power is less than 75%.

4.2 Determine the cause of the rod drop and correct.

If the Control . Rod can be 4.3 If the Control Rod can 4.3 not be withdrawn, withdrawn, proceed 'as refer to Technical follows: Specification 3 1.3 1.

l

- a. Record Step Counter l

numbers for both groups of the affected Bank and the Master Counter (located in the Rod Control Cabinets, 463 Intermediate Building).

! b. Rotate ROD CNTRL SEL to the affected Bank position.

c. Manually zero the step counters for the affected group.

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EOP-10

... . REVISION 3 12/20/82 II. D Continued:

ACTIONS ALTERNATIVE ACTIONS (4 3. continued)

-d. Place all Lif t Coil Disconnect switches for'~~

the affected Bank except for the dropped rod, in the Disconnect position (located in Control Rod Disconnect Switch Box, inside Main Control Board). ,

e. To withdraw the dropped rod from the core, proceed as follows:

Note 1.

ROD CNTRL SYS FAIL URGENT annunciator iwill alarm.

l') Drive the a'ffected Bank out.

2) Verify rod movement on the Digital Rod Position indicator.

3) Verify ONE ROD ON BOTTOM annunciator clears at 6 steps.

4) Adjust Turbine load to maintain Tavg within + 3 to 5 F of Tref.

5) continue rod motion until the rod has been realigned with the Bank as determined by:

a) Step Counter has

• • * - ,+ returned to recorded -

Bank position.

b) Digital Rod Positin indication.

PAGE 13 0F 15

E0P-10 REVISION 3 12/20/82

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(II. D Continued)

ACTIONS ALTERNATIVE ACTIONS (4.3 continued)

f. Reset the Master Counter _

to the recorded number.

g. Place all Lift Coil Disconnect Switches for the affected bank in ,

the Connect position.

h. Rotate ROD CNTRL SEL to MAN position.

1. Depress ROD CNTRL ALARM RESET.

4.4 Initiate applicable sections of STP-106.001 to verify rod operability.

45 Proceed to applicable procedures for normal plant operations.

50 FINAL CONDITIONS 51 The dropped rod has been recovered and normal plant operations resumed and STP-106.001 has been satisfactorily completed.

or 52 Plant operations are being conducted in compliance with Technical Specifications 3 1.3 1 Action requirements.

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E0P-10

.,,, REVISION 3 12/20/82 VI. REFERENCES 1.0 Virgil C. Summer Final Safety Analysis Report Volume XVI, Technical Specifications, Section 3/4.1.

Westinghouse Technical Manuals, full length rod control 2.0 system, volumes 1 thru 4, IMS-94B-023-1-0 thru 1MS-94B-023-4-0.

30 Virgil C. Summer System Operating Procedure, SOP-403 4.0 Westinghouse Abnormal Procedure A-2, Malfunction of Reactor Control System.

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