ML20054J998
| ML20054J998 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/12/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-IV-1, 5-1-2-IV-1, NUDOCS 8206300284 | |
| Download: ML20054J998 (4) | |
Text
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PLANT OPERATIONS WdUAL 'y
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s, OFF-NORMAL EVENT PROCEDURE
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CONTROL ROD / DRIVE MALFUNCTIONS l.
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t List of Effective Pages:
Page:
l l-3 List of TCN's Incorporated:
Revision TCN No.
10 None 11 None 8206300284 820625 PDR ADOCK 05000416 p
CRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURr.
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Control Rod / Drive lNo.:
05-1-02-IV-1 lRavision:
11 lPege:
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l Malfunctions l
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1.0 PURPOSE / DISCUSSION, h
1.1 This procedure provides the Operator with instructions in the event of a Control Rod and/or Control Rod Drive System Malfunction with the system properly lined up.
li 1.2 This procedure may interface with the Emergency Plan and the Emergency Procedures.
I 1.33 Several Failure modes are addressed, and instructions for each are
!j x 3 provided in section 5.0.
Control Rod System Malfunctions can cause a temporary loss of control rod drive capability.
The system is designed such that reactor pressure and/or accumulator pressure are available to scram the reactor if required, even with no CRD pump operating. With the required S/n margin met, one control rod stuck full out will not prevent reactor shut down should it remain full out following a scram.
The Cor. ol Rod Drop accident is the result of a postulated event in which a I
high worth, fully inserted control rod becomes uncoupled from its drive mechanism. The drive is then withdrawn, but the uncoupled rod sticks full in.
Later, the rod falls free and drops out the core to the full i
_out_ position at rate limited-only by the designed veloe.ity.11 miter under s
l worst case conditions, with 50%' rod density *"an'd ' xenon free, the maximum,*
free fall velocity limits the peak fuel enthalpy to less than 280 calories per gram.
2.0 SYMPTOMS 2.1 Failure of a CRD to operate on a normal insert or withdrawal signal.
2.2 Rod position indication does not change when attempting to move the control rod (s).
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2.3 Neutron monitoring indication does not change when attempting to move the control rod (s).
2.4 For an uncoupled rod, the rod overtrahel alarm, loss of the position 48 indicators, loss of the FULL OUT lights.
2.5 For control rod drop:
2.5.1 Possible high flux scram 2.5.2 Rod block alarm I
i 2.5.3 Unexp1'ained increase in reactor power.
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G AND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Con 2rol Rod / Drive No.:
05-1-02-IV-1 Revision:
11 l
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2.6 Loes of shutdown capability with control rods:
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2.6.1 Following a plan'ned 'or unplanned shutdown,. the control rods are unable or insufficient to bring or maintain the reactor suberitical.
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3.0 AUTOMATIC ACTIONS
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3.1 No automatic action will occur.except in the case of a control rod drop.
This r.ay result in a rod block and/or reactor scram due to the rapid i !
reactivity addition.
This will depend on the control rod worth at the time of the transient.
I 4.0 IMMEDIATE OPERATOR ACTIONS i
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1 4.1 Ensure automatic action has occured, if applicable.
i 4.2 If no CRD pumps 'are operating, when the second scram accumu'lator ~
associated with a withdrawn control rod is declared Inop, place 'the Mode Switch to. SHUTDOWN per Tech Spec 3.1.3.3.
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4.3 If the reactor has scrammed, entered ONEP 05:1-02-I-1.
4.4 Determine what type of malfunction has occurred and notify the Shif t Supervisor / Superintendent and Reactor Engineer.
4.5 Refer to Section 5 of, this procedure for the response to th.e particular
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5.0 SUBSEQUENT OPERhTOR ACTI'ONS' j
5.1 Inability to drive contr_o1 rod (s):
. e 5.1.1 Verify CRD drive pressure equal to or greater than 260 psid af ter l
making necessary adjustment.
If <260 psid:
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Verify CRD ' drive fil'ter dp less than 20 psig.
1 b.
Verify 'CRD suction filter dp less than 4.75 paid, i
c.
Verify CRD Suction backwash filter dp less than 5 psid.
d.
Verify proper FCV station operation and valve lineup per SOI l
04-1-01-C11-1.
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GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE s
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Title:
Control Rod / Drive lNo.:
05-1-02-IV-1 lRavision:
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l Malfunctions l
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5.1.2 If permitted by RCIS, attempt to move the af fected rod in the opposite direction.
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CAUTION Do not exceed 350 psi drive water dif ferential pressure, as this could damage the drive mechanism.
5.1.3 Increase drive water pressure in 25 psi increments and attempt to drive the affected rod.-
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5.1.4 Check stabilizing valves and the inservice FCV for proper operation.
5.1.5 If CRD parameters are normal, and the drive water dif ferential pressure has been increase to 350 psi, and rod still will not move, verify a generic problem does not exist (ie: verify other rods will move), and refer to Tech. Spec. 3/4.1.3, control Rode.r 5.2 Uncoupled Control Rod:
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CAUTION
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Do not attempt to couple a rod by scraming the rod. This could result in rod / drive damage.
5.2.1 Refer to Tech. Specs, 3.1.3.4, and attempt to recouple the
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af fected rod by inserting the drive 1 to 2 notches.
It may be
.necessary to drive the rod FULL IN to get it recoupled. After
- - - - - ---- attempting.to recouple the drive, contact the Reactor Engineer and get permission to move the drive to the full-out position to j
determine if the drive is coupled.
If drive cannot be recoupled,
. refer to Tech Spec's 3.1.3.4 and take action as applicable.
5.3 Loss of control rod shutdown capability:
1 5.3.1 Refer directly to Emergency Procedure EP-10.
5.4 Control rod' drop:
5.4.1 If a scram did not occur, and if permitted by RPCS, fully insert the drive for the af fected rod.
N,gIE Control rod recoupling may require rod repositioning as directed by Reactor Engineer.
5.4.2 Attempt to recouple the affected rod if so directed per section 5.2 of this procedure.
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