ML20098D945

Rev 0 to Off-Normal (on) Procedure ON-123, Mispositioned Control Rod

ML20098D945
Person / Time
Site:	Limerick
Issue date:	05/18/1992
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
References
ON-123, NUDOCS 9206010130
Download: ML20098D945 (7)

Text

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So-352 153

'DATE 05/20/92 13:01 NRMS RECEIPT ACKNOWLEDGEMENT SEQUENCE #' 392/>038000-A LGS PROCEOURES - APPROVED ORIGINALS DISTRCbOE ON-01 TO: NRC L.: SITE PROCEDNO NOT-A P ?'lI C a Gt-E OrJ-/t3 REVISION 000 DATE 05/18/92

! I HAVE RECEIVED THE SU3 JECT MATERIAL SIGNATURE:

__ __ __________.._________________ DATE:

'PLEASE RETURN THIS FORM PROMPTLY TO LGS ADMIN. SERVICES (LGS-340

)

WITHIN 15 DAYS OF THE ABOVE PAINT-DATE.

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03TE 05'/20/92 13: 01 NRMS DOCUMENT-CONTROL FORM SEQUENCE.# 3924038000 L K" PR'OCFOURIS - APPROVED ORIGINALS

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DCC/ WALK 01 I**PLANTLOP. SUD. FAC.-

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• CONST BLOG LIB DCC/ WALK 01 I** SHIFT MGR OFFICE' DCC/ WALK 01 I*

• CONTROL RM CART-LGS DCC/ WALK

02 I**SUPPT-BLOG LIB #1 OCC/ WALK-01 I*

rEMER3. OP. FAC. LSS _DCC/ WALK 01 C**SUPPT BLOG LIS #2 DCC/ WALK 01 I*

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-REQUESTS FOR CHANGES TO THIS DISTRIEUTION LIST MUST BE ADDRESSED TO THE

. ORGANIZATION RESPONSISLE FOR ORIGINATING THE ATTACHED DOCUMENT (SEE NUCLEAR RELATED DOCUMENT REGISTER (NRDR) FOR RESP. ORG.).-THE RESP. ORG. WILL-AUTH3RIZE THE LOCAL DCC SUPERVISOR TO MAKE THE NECESSARY CHANGES.

ATTACHED IS A COPY OF:

PROCEDNO fiO T iP 'L : 0,, L c CM. Q REVISION 000 DATE 05/18/92 UDN NTROLLED: LIBRARY, INPO, NUNEZ U

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ON-123, Rev.

0-Page 1 of 5 3924038000 CMM:l$m

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PHILADELPHIA ELECTRIC COMPANY r

LIMERICK GENERATING STATION ON-123 MISPOSITIONED CONTROL ROD l.0 SYMPTOMS 1.1 A control rod not at its desired position.

2.0 OPERATOR ACTIONS 2.1 Stop all control rod motion AND power changes.

2.2 Notify Shift Supervision.

2.3 IF control rod is drifting, THEN enter ON-104.

24 IF control rod -is raispositioned by 1 notch position, THEN reposition control rod to correct position AND exit this procedure, OTHERWISE, continue in this procedure AND contact Reactor Engineering.

2.5 IP reactor power is < RWM LPSP,.

THEN go to step 2.9.

2.6 IP any of the following conditions exist, TEEN immediately full.y inser: the mispositioned control rod:

a.

MFLPD from last P-1 is > 0.9 with no qualified Reactor Engineer present, b.

Reactor power'is OR was > 100% RTP due-t'o control rod cotion, as evaluated by a new OD3-2, c.

Mispositioned control rod is positioned at the same notch position as another control rod within a 5 x 5 array centered on the mispositioned control rod, d.

"LPRM UPSCALE" annunciator alarms, OTHERWISE, go to step 2.8.

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c ON-123, Rev. 0-Page:2 of S-CMM:ljm

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2.7 Fully insert the control rods necessary to achieve

symmetry, AND demand a P-1:

a.

IP all thermal limits are < 0.95, THEN contact Reactor Engineering for reactor power.

,recovery, AND exit this procedure.

b.

IP any thermal limit > 0.95, THEN reduce reactor power in accordance with the Reactor Maneuvering Shutdown Instructions until a P-1 indicates that all Thermal Limits < 0.95.

c.

Contact Reactor Engineering-for recovery, AND exit this procedure.

2.8 Evaluate whether mispositioned control rod may be returned to its desired position:

2.8.1 Demand an OD7-2.

IP control rod was.mispositioned by being withdrawn a.

past its desired' position, THEN go to step 2.8.3.

2.P.2 IF the control rod was mispositioned by beino Inserted past its desired position, AND:

The mispositioned control rod must pass through the a.

notch position of any control rod in a 5 x 5-array centered on the mispositioned_ control rod in order to be returned to1.ts desired position, THEN fully insert the 'misposiioned control rod

-unless directed otherwise by a-qualified on-shift Reactor Engineer, AND go to step 2.7.-

ON-123, Rev 0

Page 3 of 5 CMM:ljm O

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NOTE: Reactor axial relative power is indicated in the top center of the P-1 edit.

Location 1 is at core bottom, and lo;ation 12 is at core top.

One location increment is equivalent to 2 even Control Rod notch posi.tions.

Example:

Rod Position 46 42 38' 34 30 26 22 18 14 10 06 02 LOCATION 1

2 3

4 5

6 7

8 9

10 11 12 AXIAL RCL PWR 0.48 0.79 0.89 0.39 1.03 1.15 1.17

1. 2'O 1.20 1.01 1.11 0.74 REGION REL PWR 0.87 1.08 0.37 1.07 1.33 1.07 0.87 1.08 0.86 RING REL PUR 1.05 1.37 1.32 1.30 1.25 1.21 0.92 0.48 APRM GAF 1.00 1.00 0.99 1.00 0.99 1.01 b.

The mispositioned control rod must pass from a location ci lower axial relative power to a

[~D location of higher axial relative power as kt/

indicated by the last P-1, THEN fully insert the mispo itioned control rod unless directed otherwise by a qualiried on-shift Reactor Engineer, AND go to step 2.7.

CAUTION X X X X X X X X X X X X X X XX X X X XX X X X X-X X X X X X X X o

To preclude violation of Thermal Limits AND rated power all control rod withdrawals greattr than a. total of four notch positions shall-be-performed with a qualified on-shift Reactor Engineer present'exceot for' execution of the Reactor Maneuvering Shutdown Instructions, including the l

Shutdown RWM.

X X X X X X X X X X X X X X X X X X X X X~ X XX X. X-X X X X XX X c.

IF'the control rod was mispositioned by more than a total of 4 notch positions, l

THEN fully insert the mispositioned control rod l

unless directed otherwise by a qualified.on-shift-l_ _

Reactor Engineer,.

AND go to steo 2.7.

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OTHERWISE return the mispositionedLcontrol rod to.

its desired position using_ single notch withdraw commands:-

^

IF the RBM does not permit withdrawal of the' mispositioned control' rod to~its desired position.

THEN fully insert the mispositioned control rod unless' directed:otherwise by a qualified on-shift Reactor Engineer, AND go;to_ step 2.7.

2.

Demand a P-1 once the mispositioned control ~ rod has been returned to its desired. position.

3.

IP any_ Thermal Limit > 0.98, OR any new; Base Crit Codes appear THEN fullyfinsert the-mispositioned control-rod unless directed otherwise_by a~ qualified on-shift Reactor Engineer, AND-go to step 12.7.

-OTHERWISE exit this orocedure.-

2.8.3 IF the control rod.was mispositioned-by being withdrawn pact'its desired position, THEN:

I a.

Reduce power 100 MWe_using cora flow, BUT not to less than 45 mlb/hr core flow.

b.

IF the mispositioned control: rod will not pass tErough-the notch position of any_controf rod in a 3

5 x-5. array. centered on the_mispositionedicontrol rod in order to rbe returned to :its proper position, THEN return:the mispositioned control rod!to its propor-position

~

AND:

1. - Demand-a P-1.

2...Go to step-2.7.a'.-

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.c.

OTHERWISE, reduce power to < 80% RTP using core flow.-

d..

Return-the mispositioned control? rod to-'its proper i

. position-AND:

1.

Damand a P-1.

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2.

Go to ctep 2.7.a.

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ON-123, Rev. 0 Page 5 of 5 CMr.:ljm 2.9 g reactor power $ RWM LPSP, AND > 10% RTP, THEN contact Reactor Engineering for recovery.

2.10 E reactor power 5 10% RTP, AND the control rod pattern is not latched into-the RWM, L

THEN:'

l a.

SCRAM l

b.

Enter T-100 I

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