ML20081M031
| ML20081M031 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/15/1991 |
| From: | Laflin F, Lizalek J, Regis A COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20081L949 | List: |
| References | |
| FOIA-94-285, FOIA-94-302 DOA-0300-12, DOA-300-12, NUDOCS 9503310148 | |
| Download: ML20081M031 (6) | |
Text
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UNIT 2(3)
DOA 0300-12 REVISION 02 November 1991 cMISPOSITIONED CONTROL RODo(W-2, W 3)
Requirements:
NONE.
Special Controls / Reviews:
1.
Revisions to this procedure must be reviewed and approved by a Ouulified Nuclear Engineer (ONE) and the Reactor Engineer in accordance with the requirements of DAP 07-29, Reactivity Management Control.
1 1
F. Laflin Originator J. Lizalek Independent Reviewer / Verifier (If Applicable)
A. Reais Department Procedure Writer k) lj T. Mohr Department Supervisor NOV 1L E91 EXHIBIT 8
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9503310148 941028 PDR FOIA TROY 94-205 PDR d,.l.,
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UNIT 2(3) a
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00A 0300-12 REVISION 02 3
eMISPOSITIONED CONTROL R000(W-2) z A.
SYMPTOMS:
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~
1.
Al' arms:
s.
Panel 902(3)-5 A-3, R00 DRIFT.
b.
Panel 902(3)-5 8-3, ROD WORTH MIN BLOCK.
- c.. Panel 902(3)-5 C-3, R0D OUT 8 LOCK.
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The following may occur if the consequences of 'a mispositioned I
l Control Rod are severe enough.
l t
f d.
Panel 902(3)-3 C 2, OFF GAS RAD HI HI.
e.
Panel 902(3)-3 D 2, OFF GAS RAD HI.
k f.
Panel 902(3)-5 D-7, LPRM HI.
2.
Parameter changes: Sudden rise in off gas radiation monitor indication.
_i 3.
Rod pattern anomalies: Rod position (s) differs from that specified
'i by the Control Rod sequence.
i B.
AUTOMATIC ACTIONS:
I NONE.
C.
IMMEDIATE OPERATOR ACTIONS:
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For the purposes of this procedure, during Control Rod drive 1
l exercising, a rod inserted one even notch beyond the insert limit j
j I
given on the Unit Status Sheet will be considered to be one even notch j
out of sequence.
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.'1 1.
E a Control Rod is found or moved one even notch from its
~
t insequence position,.THgH return the Control Rod to its insequence j
position. No further action is required, t
i 2.
E a Control. Rod is found or moved greater than one even no e
't its insequence position, THEN discontinue all Control Rod a j n i and recirculation flow increases.
EXHIBIT R
NOV 151991 PAGE d OFIO gg){
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I1 UNIT 2(3)
.g DOA 0300-12 REVISION 02 I.
M 1.
The size of the load reduction may be modified by the Operations Shift Supervisor in proportion to the severity of the event.
l i
2.
At reactor power levels above 50 percent of rated, subsequent actions must be performed quickly (typically less than i
10 minutes).
(
0.
SUBSEQUENT OPERATOR ACTIONS:
1.
E Reactor Power is less than or equal to 20% Rated Core Thermal Power, 3 3:
E nine (9) or more Control Rods are found inserted 3 a.
withdrawn greater than one even notch from their insequence positions. EB manually SCRAM the Reactor, b.
E a single Control Rod is inserted E found inserted greater than one even notch from its insequence position, 3 3 i
continuously insert the mispositioned Control Rod to position 00.
(-
l E a single Control Rod is withdrawn E found withdrawn gr' ester l
c.
than one even notch from its insequence position, 3 3 i
continuously insert the mispositioned Control Rod to.its insequence position.
d.
GO TO Step D.3.
2.
E Reactor Power is greater than or equal to 20% Rated Core Thermal Power, 2 3:
E the Control Rod mispositioning occurred within the past ten a.
minutes, 3 R :
(1)
E a single Control Rod is inserted greater than one even notch from its insequence position, E g continuously insert the mispositioned Control Rod to position 00.
(2)
E a single Control Rod is withdrawn greater than one even notch from its insequence position, Effi continuously insert the mispositioned Control Rod to its insequence position.
i EXHIBIT g PPaI-r-(3)
GO TO Step D.3.
t PAGE,h OF.[p_ NYill(Sd991 i
3 of 6 1
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UNIT 2(3)
[
g DOA 0300-12 REVISION 02
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The size of any required load reduction may be modified by the j'
i l
Operations Shift Supervisor in proportion to the severity of the 1
I event.
7 I
1 f
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D.
2.
b.
E the Control Rod mispositioning occurred more than 10 minutes I
ago E the time is unknown, Egg-CAUTION DO NOT drop core flow below 46 Mf/hr if flow control line is greater than or equal to 80%.
(1)
Immediately drop reactor power by 50 MWe using recirculation flow ONLY in accordance with DGP 03-01, Routine Power Changes.
(2)
E mul.,iple Control Rods are found inserted E withdrawn greater than one even notch from their insequence positions, Egg continue to drop reactor power by another 50 MWe (total of 100 MWe) using recirculation
(,
flow ONLY in accordance with DGP 03 01, Routine Power Changet.
(3) 00 TO Step D.3.
3.
Contact a ONE (Qualified Nuclear Engineer).
4.
cIn conjunction with Step D.5, contact the Unit Operating Engineer or the Operations Duty Supervisor.o (W-2) 5.
Compare the current Off Gas radiation level to the Off Gas radiation level prior to the suspected time of the mispositioning:
{
E Off Gas radiation level has increased 6MQ a GNE is HQT a.
available, Egg insediately reduce power using recirculation flow ONLY until Off Gas radiation level has returned to its i
original pre-mispositioning value.
b.
E dropping recirculation flow does HQI return the Off Gas i
radiation level to its original pre-mispositioning value, I!![N insert ALL sispositioned Control Rods to position 00.
c.
Refer to DOP 0500-02, Evaluation of Suspected Preconditioning Overpower Conditions, and DGA-16, Coolant High Activity / Fuel Element Failure.
B APPME."
EXHIBIT 4
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UNIT 2(3) i.
DOA 0300-12 REVISION 0?
,. e7 D.
5.
d.
Record data in Unit log book including location of mispositioned rod (s), time of discovery of mispositioning, actions.taken and any other observations determined to be
- relevant, p
i g
6.
Upper. Management representative will conduct.an evaluation into
.the cause of the Control Rod mispositioning and implement immediate corrective actions prior to resuming routine Control Rod movements.o (W-2) 7.
Control Rod Drive abnormalities:
i E the CRD does not respond as expected, Egg enter and perform a.
DOA 0300-05, Inoperable or Failed Control Rod Drives.
b.
E the CRD is not failed, but exhibits ' abnormal behavior, Egt(
record as appropriate on DOS 0300-06, Weekly Control Rod Drive Abnormality Record.
E.
USER
REFERENCES:
1.
Procedures:
l a.
DOP 0500 02, Evaluation of Suspected Preconditioning Overpower 1
Conditions.
b.
DOA 0300-05, Inoperable or Failed Control Rod Drives.
c.
DOS 0300-06, Weekly Control Rod Drive Abnormality Record.
.d.
DAN 902(3)-3 C-2, Off Gas Rad Hi Hi.
I t
DAN 902(3)-3 D-2, Off Gas Rad Hi.
e.
f.
DAN 902(3)-5 A 3, Rod Drift.
g.
DAN 902(3)-5 8-3, Rod Worth Min Block.
h.
DAN 902(3)-5 C-3, Rod Out Block.
i.
DAN 902(3)-5 D-7, LPRM Hi.
J.
DGA 16, Coolant High Activity / Fuel Element Failure.
I k.
DGP 03-01, Routine Power Change.
l PAGE IOF b PAGE(S)
APPROVED NOV 151991 t
D.0.S.R.
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UNIT 2(3) i 00A 0300-12 REVISION 02 t
F.
DISCUSSION:
P When possible, Control Rod movement should be performed per the GNE recommendation to ensure Control Rod movement / power level changes adhere to preconditioning rules ~and comply with Technical Specifications and Low Power Setpoint Sequence patterns / power levels. In the event of an Out of Position Control Rod, time is usually of the essence..At high power levels (above 50 percent), inadvertent Control Rod movementes should be corrected or appropriate power reductions commenced prior to spending time on data gathering or consultation. Conservative judgement must be applied when the described actions are not appropriate.
After completing the prescribed actions to correct the eispositioned Control Rod, the independent Upper Management representative must i
conduct an investigation into the cause and contributing factors. Short term corrective actions, if appropriate, must be laplemented prior to continuing Control Rod motion. Contacting Upper Station Management should not preclude taking prompt corrective actions to prevent fuel failures.
The Rod Drop Accident analysis is associated with the Low Power Setpoint Sequence assumed a maximum of eight (8) Control Rods out of sequence at position 00.
Thus, when nine (9) or more Control Rods are out of
)
sequence when the Reactor is less than 20% Rated Core Thermal power, the unit is in an unanalyzed condition. A manual Reactor SCRAM is s
(.
warranted. All Control Rod sispositioning events aunt be reported through the deviation process *(DAP 02-08).
W.
WRITER'S
REFERENCES:
}
1.
SIL 292, Inadvertent Control Rod Withdrawal.
2.
SOER 84 2, Control Rod Mispositioning.
3.
DVR 12-2-91-29, Control Rod Mispositioning During Stall Flow-Testing Due to Personnel Error (NTS 237-200 91-02906).
4.
DAP 02 08, Deviation Reporting.
5.
DAP 07-29, Reactivity Management Control.
EXHIBIT M
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