ML20081M125

Rev 17 to Procedure Dgp 03-04 Control Rod Movements

ML20081M125
Person / Time
Site:	Dresden
Issue date:	08/31/1992
From:	Feren T COMMONWEALTH EDISON CO.
To:
Shared Package
ML20081L949	List: ML20081M031 ML20081M125 ML20081M140 ML20081M161 ML20081M172 ML20081M185 ML20081M197
References
FOIA-94-285, FOIA-94-302 DGP-03-04, DGP-3-4, NUDOCS 9503310196
Download: ML20081M125 (14)

Text

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j UNIT 2 (3)

DGP 03 04 REVISION 17 CONTROL ROD MOVEMENTS

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E Requirements:

4 NONE.

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Special Controls /Raviews:

1.

Revisions to this procedure must be reviewed and approved by a Qualified Nuclear Engineer (QNE) and the Reactor Engineer in accordance with the requirements of DAP 07-29, Reactivity Management Centrol.

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= CEDDMDA

%ittw!R bud G w ad CmW T. Feren originator B. Sampson Independent Reviewer / Verifier (If Applicable)

T. Cole Department Procedure Writer N/A Department Supervisor APPROVED 4/ AUG 31 *92 EXH! BIT __

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g DGP 03-04 REVISION 17 (5 CO - . RCD -

-A. PURPOSE:

'2his procedure provides general instructions for movement of control rods on Units 2 and 3.

5. USER

REFERENCES:

1. Technical Specifications:

a.. 'Section 3.3.5./4.3.8., control Rods.

b. Table 4.s.l., Radioactive Gaseous Waste Sampling and Analysis Progreat.

2. Procedures:

, s. Current Unit CRSP (Control Pod Sequence Package) book.

b. DAP 07-29, Reactivity Management Control,

c. DAP 14-14, Control Rod Sequences.

d. DGP 03-01, Routine Power Changes.

(.. .*

e. DIP 0700-02, Neut;ron Monitoring Shorting Link Installation and Removal.

f. DGA-07, Unpredicted Reactivity Addition.

g. DOA 0300 05, Inoperable or Failed Control Rod Drives.

h. DOA 0300-12, Mispositioned Control Rod.

i. DOA 0500-01, Inadvertent Entry Into the Unstable Power / Flow Region.

j. DOP 0400-01, Reactor Manual Control System Operation.

k. DOP 0400-02, Rod Worth Minimiser.

1. DOP 5670-01, Economic Generation Control (EGC) Operation.

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m. DOP 9900-76, Flow Control Line and Average Thermal Power '

(OD-76).

n. DOS 0300-01, Daily / Weekly Control Rod Drive Exercise. I

o. DOS 0300-06, Weekly Control Rod Drive Abnormality Record,

p. DOS 0500-18, Operator's Flow Control Line Surveillance.

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DGP 03-04 REVISION 17 r

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q. DOS 5600-05, Economie Generation Control Operating i surveillances and High/ Low Limits Determination.

r. DTS 0400-01, Initializing and w d4== Sequences into the Rod Worth Minimiser.

s. DTS 8143, Core Performance (Missed Core).

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t. DTS 8271, Guidelines for Control Rod Sequence Development.  !

u. DTS 8273, Reactor Criticals.

. v. DTS 8474, Core VerificatiJa.

C. SUPPImdENTS:

NOME.

D. PREREQUISITES: f t

1. Prior to m. y control' rod sovement, the Nuclear Station Operator '

(NSO) shall notify Operations Shift Supervisor.

2. 'Itae NSO (Nuclear Station Operator) will verify the Unit is in r- Manual Flow Control. If necessary, the Unit shall be removed from EGC per DOP 5670-01. .

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l Startup of the reactor is not permitted if the RWM fails before the {

j first 12 rods are fully withdrawn.

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3. 'Any control rod movement with fuel in the core must be performed ,

with RNM control rod block function enabled. IE RNM is not i available or its control rod block function is disabled, 2EIg a Second verifier is required for all control rod movement.* (W-9)

4. Review the contents of the Control Rod Sequence Package (CRSP) and the control Rod Maneuver Request Form, if provided.

5. Chemistry Department must be notified to take samples per i Technical Specifications Table 4.8.1, Radioactive Gaseous Waste Sampling and Analysis Program (DCP 1600-21) for any of the '

following:

1

a. Unit startup,

b. Unit shutdown,

c. Unit' scram, i 3 of 14

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UNIT 2 (3)

DGP 03-04' REVISION 17 D. 5. d. A power change of more than 500 MWth '.a a one hour time '

period.

E. PRECMFFIfBIS:

1.

In general, control rod sequences are designed to comply with a Low Power Setpoint Sequence (LPSS), fuel . vendor preconditioning guidelines and Technical Specification 'lineraal Limits. In the event of a mispositioned control rod, time is usually of the '

essence. In order to recover from a mispositioned control rod, refer to DQA 300-12, Mispositioned Control Rod.  !

2.

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Control rod motion described in this procedure is to be performed

' using standard reactor manual oontrol (DOP 0400-01). *This

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procedure prohibits use of scram timing equipment,for control rod insertion, except for testing purposes or emergency use.* (W-4) '

3.

• Control rod motion has a direct and dramatic effect on core l reactivity. Like all core reactivity changes, it must be performed in a conservative manner in strict compliance with written procedures.* (W-4)

4.  !

' Control rod movement without approval from a Qtet (Qualified

, ,- Muclear Engineer) or explicit procedural guidance may lead to fuel l' over (W-s) powering, Technical Specification violation or core damage.'

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5.

• When possible, avoid withdrawing control rods to a high reactor t power level which could lead to solid APRM High alarms.* (W-8)

F.

LNTTATIONS AND ACTIONS:

1.

It is always the option of responsible licensed personnel to  !

decline to perform any control rod movement which in their ,

judgement, compromises plant safety or endangers plant equipment. _

2.

• When performing control rod movements per Control Rod Sequence (DAP 14-14), steps may EE be skipped without approval of a QNE.* ,

(W-4) l i

3.

Power operation with both Flow Control Line greater than 80% and core flow less than 45% is prohibited due to potential reactor

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core instabilities. II this region is inadvertently or enintentionally entered, 2]EE refer.to DOA 0500-01 for corrective l actions.

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In order to keep CRDs in good operating condition, it is important to record all CRD anomalies per DOS 0300-06. I i

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UNIT 2 (3) ,

4 DGP 03-04 REVISION 17

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• MIgE a Second Verifier is required for control rod movement, M i the Second verifier will have no other duties during control rod ,

[ movement and will monitor control rod movement closely enough to '

i ensure control rod movement is within limits of station procedures.' '(w-9) Se second verifier shall be a licensed operator or a qualified technical person.

G. PROCEDORE:

s 1.

BISO (31uclear Station Operator) and Operations shift Supervisor '

observe the following general instructions :

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• When fuel is in the' reactor core, all control rod movement shall be made in accordance with this procedure, the CRSP or l ,

j appropriate station procedures.* (w-4) l

2. 4

'A W may be present at times during control rod movement to  !

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, act as an advisor to the EISO and Operations shift Supervisor, '

j to provide technical guidance, and approve any unplanned deviations from the sequence.* (w-2)

a. Using DGP 03-01 Attachment A, Min 4== Requirements for QttE

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coverage During Power Changes, determine QNE coverage requirenants for the p1 maned evolution.  !

b.

ZZ a control rod drop or any other unpredicted reactivity

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addition is suspected, 22lEE refer to DGA-07, Unpredicted  ;

Reactivity nddition.

c.

When withdrawing control rods, observe the expected response of the nuclear instrumentation to verify the control rod is -

following its drive. For previously uncoupled control roda (DOS 0300-06) that exhibit no discernable response on the nuclear instrumentation, response verification must be '

repeated at a power level above 20 percent Core neraal Power (CTP) . * ,

d.

Any time a control rod is withdrawn to notch posicion 48, maintain a withdrawal signal for a few additional seconds.

Acti'vation of the Rod Overtravel Alarm indicates an uncoupled control rod (DOA 0300-05). '

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, DGP 03-04 REVISION 17 +

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i G. 1. e. 'R a Second verifer is required for. control rod movement,  ;

2EEE perform the verification as follows: -

4 (1) MSO &E2 Second verifer compare current control rod  !

pattern based on Panel 902(3)-5 indications (or equivalent) to the espected control rod pattern' based  ;

on the last step cospleted in the control Rod Sequence

• Instructions or Surveillance.

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MSO ACTIONS SSCtMD VSRIFIER ACTIONS (2) Road aloud Verbally acknowledge verification of from the the correct step to be performed.

Control Rod Sequence  !

Instructions  :

or Surveillance the step to be performed.

(3) Select the verbally acknowledge verification control rod that the correct control rod has to be moved. been selected. '

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(4) State the Verbally acknowledge' verification control rod that the NSO has correctly stated '

to be moved the move.

and its final I

position.

(5) Perform the Observe the control movement and f indicated IMIEDIATELY notity the NSO of any control rod errors. ,

movement.

(6) State the Verbally acknowledge verification  !

control rod that the control rod has been and its correctly positioned.

current  !

i position.

I (7) R arrays are being used, 2EEE NSO &lg2 Second Verifier '

repeat Steps G.1.e. (3) through Step G.1.e. (6) for the remaining control rods on the designated Array Card.

(8) Second verifier will review the current control rod pattern with the expected pattern at a frequency designated by the Operations Shift Supervisor.

(Consult with a QNE if needed.)

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UNIT 2 (3) i- DGP 03-04 REVISION 17 t

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G. 1. e. (9)

MSO Agt Second Verifier repeat Steps G.1.e. (2) through Step G.1.e. (4) for i -4=4ag steps to be performed C from the Control Rod Sequence Instructions or -

Surveillance.' (W-9)

f. MHgg control zod sequence checkpoint step is reached during ,

either startup or shutdown, IEEE perform the following.

Verify control rod pattern is consistent with sequence

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(1)

'=- ;-:'=t pattern.

(2) IE control rod pattern does E match, IEEE stop i

, control rod movement, notify operations Shift Swervisor, AEt refer to Dok 0300-12, asispositioned Control mod. ,

e operations Shift Supervisor will notify a QME IE control pattern does E match the check point pattern.

j (3) Enter initials, date and time in the appropriate space on the CRSP sequence. i

g. MEEE the Low Power Setpoint Sequence (LPSS) break point is  !

reached during either startup or shutdown, 2EEE perform the

(. .,

fo11owing:

(1) Verify control rod pattern is consistent with LPSS break point pattern Agt obtain the fraction of rated

} Core ' thermal Power (CTP) .

l (2) Verify CTP (Core ' thermal- Power) is greater than 20% l rated power &lEl record this fraction of CTP in the j appropriate space on the CRSP sequence. -

(3) IE control rod pattern does E match, or IE LPSS l break point is reached and CTP is less than 20%, THEN l stop control rod movement, notify Operations Shift  !

Supervisor, 852 refer to DQk 0300-12 if appropriate. I e operations Shift Supervisor will notify a QNE IE control rod pattern does E match, or IE LPSS break point is reached and CTP is less than 20%. l (4) Enter initials, date and time in the appropriate space on the CRSP sequence.

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UNIT 2 (3)

DGP 03-04 REVISION 17

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' I t l Notify Operations Shift Supervisor prior to any use of the CRSP book l l

A for control rod amovenant. l A 3 G. 1. h. For normal in-sequence control rod movements, the control rod sequence section of'the CRSP will be utilised. Any ,

deviations to control rod sequence must be entered on the Change Log with appropriate approvals.

i (1) As each step of control rod sequence is completed, a

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log entry will be made as called for on control rod y sequence check sheet. 'nais entry implies the following:

e Step has been cospleted. '

e Eso has observed expected response of the nuclear instruenntation to verify each control rod is following its drive.

• Control rods that were withdrawn to position 48, an overtravel check was successfully performed. l

( '

(2) VERIFY box is to be completed for all control rod movement:

e II RW (Rod Worth Minimf ser) is operable, 2EEE enter RWM in VERIFY box.

i ee II R W is inoperable, 2EEE,a second sequence verifier saast be used per Step G.I.e. ,

f \ ,

e After each step has been completed and verified,

' second verifier shall initial the VERIFY box for the appropriate step.e (W-1 and W-9)

(3) QNE HOLD POINT, this means control rod withdrawal beyond this point in the control rod sequence will not be permitted without consent of a QNE. This consent may be written or verbal and shall be neted in space provided.

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tatIT 2(3) a DGP 03-04

. REVISION 17 O

G. 1. 1. *H need arises'to sodify order in which steps are completed in the CRSP sequence or Special CRSP sequence, 'DEE these changes will be entered on Change Log and approved by a gus. -

(1) H' necessary,. RESE rod' blocks to full power must be disabled.

e

'Ibe second verifier for control rod movements shall be a licensed operator or'a

• qualified individual" who is familiar with the Reactor sanual a control System, and is familiar with DAP 07-27.

i (2) Upon completion of the control rod moves, if  ;

w y m d ate, RIGE rod blocka to full power must be i enabled.* (W-4)  ;

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Operations shift Supervisor has the following duties: l 1

(1) Have a basic unders*==M ag of maneuver /and or control' rod motion to take place.

(2) Notify the Load Dispatcher when a maneuver is going to i i

ehange unit load an appreciable ascunt. I i

2. t Edo and Operations Shift Supervisor observe the following 1

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instructions foy Refueling:

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a. Prior to any control rod movement, the core or control cell \

containing the control rod to be moved must be preliminarily verified per DTS 8474, Core verification. l

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WhenR108isoperable,inserviceandloadedwithanall-rods-inl  !

l sequence, control rod withdrawal function is considered l blocked. j

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2. .

The following requir===nts need not be adhered to for control i

f j rod movement required to d==an=trate operability of refueling f interlocks. i 1

l j b.

H there is fuel in the Reactor Vessel M the Peactor Vessel Head is de-tensioned QB removed, 2]EE one of the following must be met to assure adequate shutdown capability:

1 (1) All control rods are fully inserted M the control rod withdrawal function is blocked or disabled.

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• tarIT 2 (3)

-. DGP 03-04 REVISION 17

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G. 2. b. (2) Se QNE has determined the neutron monitoring systent shorting link configuration requirements to be established by the Instrument Maintenance Department (DIP 0700-02) per the followiig criteria:

• EIEE less than four Snus or Fuel w d4=g rh==h=rs (FICs) are operable, 2EEE remove all four shorting links.

• EEEE four Snus are operable and monitoring the fueled region, 2EEE remove two Sam shorting links to place SEK Scrast logic.in coincident mode.

3. N80 and Operations Shift Supervisor observe the following instruccices for Reactor Startup:  ;

l l EDIE I l l j

1. To minimise the occurrence of short periods during startups, l )

g two methods for dete =4a4=a the proper time to initiate notch j g override restrictions have been developed. The two methods are g l based upon SRM count rates and sequence step. The g I

implementation of notch override restrictions is to occur i l whenever either of the two following conditions axiots. l l I

C. ,g I

2. These restrictions shall be clearly noted in the check sheet I i

g l section of the control rod sequence.

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a. Do EZE use Notch Override Switch between positions 00 and 24 '

after SRMs have experienced a 3-fold increase in count rate (8 times the initial count rate) until'the Unit is in a .

steaming condition (one bypass valve partially OPEN or the l Iktit on-line) . The QNE will record the SRM count rates 1 during startup and will inform the NSO when the notch override restrictions are to be implemented per DTS 8273,  !

Reactor Criticals, QB  !

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b. After pulling the first two LPSS (Low Power Setpoint i Sequence) groups (groups 1 and 2) to position 48, do EQI use l Notch Override Switch between positions 00 and 24 until the  !

Unit is in a stemming condition. his restriction may be i altered by a QNE, Operating Order or sequence note.

4. NSC and Operations Shift Supervisor observe the following instructions for Reactor Shutdown:

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g IntIT 2 (3)

DGP 03-04 REVISIOst 17

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I Inserting control rods in reverse order of sequence is reserved for l '

! Unit shutdown only. Jlppropriate unit shutdown procedures address l j

. I techniques used and prerequisites needed for inserting control rods l in reverse order of sequence.

c-a.

'At no time should inserting control rods in reverse order of sequence be assumed to be conservative. Inserting ocotrol rods in reverse order of sequence while at core flows greater than 47% of rated may lead to fuel over powering, Technical specification violations or core damage.* (w-s)

E2EE Flow may be reduced to =4n4== pump speed upon achieving a Core

'fhermal Power other than 40% of rated at de discretion of a Qats.

G. 4. a. EHER at apprawi==tely 47% of rated core flow, 2]lEE insert control rods in reverse order of sequence until Core Thermal Power is reduced to 40% rated as follows:

(1) Insert control rod (s) to designated target position.

(2) Do E2I plaos control rod (s) at intermediate position without getE approval. L b.

Reduce recirculation pumps to minimus speed (approximately 28%).

c.

Continue control rod insertion in reverse order of sequence.

5.

NSO and Operations Shift Supervitor observe the following instructions for Emergency Load Reduction (CRAM Arrays):

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Eas;gency load drops are defined as any load drop that must be taken quickly in order to avoid equipment damage or a reactor scram. 'Ihe preferred method to acccuplish a load drop is to reduce recirculation I flow. If reduction of recirculation flow is insufficient, not practical or not possible, CRAM Array insertica may be used to drop ,

load. CRAM Arrays may also be used to increase margin to the APRM l.

scram line in emergency situations. I

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IntIT 2(3)

DGP 03-04 REVISION 17 l  ;

2 G. 5. ' a. If CRAM Array insertion is not directed by station procedure l

or does not meet the above criterion, QNE spproval is

, required prior to use of the CRAM Arrays. i I

b. Consult' CRSP book CRAtt Arrays section which provides

} guidance on which arrays'can be inserted. ';

c. I Enable the Power Reduction Function of the R388.

- d. vexity CRAM Arrays listed on RsRE screen are identical to those listed in the CRSP book CRAlf Array section.

e.

• ZE RESE and CRSP are M in agreement M time permits, 23F" l contact a Qus for instructions, 13

• ZE time does M permit contacting a'QHR, M bypass the RISE , and

• provide second verifier per DOP 0400-02* (W-9) . ,

CatrrImt 1.

Canat Array control rod movement must occur in a continous fashion to prevent fuel failures, t

2.

In most cases, insertion of CRAM array rods results in control

( , rod positions that deviate from the approved control rod ,

pequence. ZE core thermal power is reduced to less than 20% of '

rated prior to ree - iaa control rods to the approved control rod sequence Position, IEEE the control rod positioining may be in violation of LPSS/BPWS rules. ,

f.

IE RISt and CRSP book are in agreement, or the RMM IS BYPASSED, 2EEE continously insert control rod (s) until desired load drop is accomplished:

e Cont 4===ly insert control rod (s) to designated target position, e

. Do E2r place control rod (s) at intermediate positions.  ;

g.

Upon full or partial coupletion of 'a CRAM Array insertion l step, Unit RSO shall record Cram Array number and individual -

rods inserted in space provided on CRAM Array sheet then sign-date-time step completion.

h.

IE a resumption of CRAtt Array insertion is required following the partial completion of a CRAM Array step, 2 Egg insertion shall b gin with the remaining control rods in partially inserted CRAM Array before proceeding to next CRAM l

Array.

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tNtIT 2 (3)

DGP 03-04 REVISION 17

/*s G. 5. i.

Notify a QME at earliest possible time following CRAM Array insertion to perform a review of Unit status and provide re h tions for CRAM Array withdrawal when the emergency-4 situation has been rectified.

6.-

mso and Operations shift supervisor observe the following instructions for Routine Load Reductions using PCL Control Rods:

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• FCL Instructions should be used to elir'uce or minimise  !'

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l intermittent rod blocks prior to surveillances involving routine  !

[ control rod movement.* ' (W-10) j

a. 2 FCL increases to a point where APRM High alarms are nearly solid (the auto reset APRK High lights are not periodically resetting or bouncing), or the FCL Limit is being exceeded, 2EEE perform the following:

(1)

Consult the CRsP book FCL Instruction section for guidsace on which arrays or control rods may be inserted to safely and promptly reduce FCL.

(2) Insert control rod (s) until desired load drop is accesplished: ,

e Insert control rod (s) to designated target position.

e Do E2I place control rod (s) at intermediate positions without QUE approval. .

(3) Following completion of the FCL insertions, the NSO should sign, date and time the FCL instruction sheet.

b.

H no explicit instructions exist or the instructions provided are inadequate, 233E contact a QNE for directions.

H. DISCUSSION:

1. I

'Inforsation dealing with the CRSP book (e.g. distribution, use and control) was removed from this procedure and placed in DAP 14-14 to improve sequencing practice. In addition, guidelines  ;

have been added to this procedure to clarify the following: '

a. Conditions under which the control rod sequence may be used in reverse order.

b. Proper use of FCL Instructions. i 1

c. Actions to be taken to address APRM High alarms.* (W-8) 1 13 of 14 1

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DEIT 2 (3)

DGP 03-04 ,

nEVISION 17 j ..

t w. wnITunes anFanancm8:

1. Inspection Reports, 50-10/85-009, 50-237/85-023, 50-249/85-019. .

2 Action Itest 12-77-223.

3. Investigative Commtittee - Final Report, Dresden 2 Out-of- Sequence Shutdown, January 9,1984.

4. SOER 44-02, Control Rod Mispositioning.

5. W. F. Naughton Letter to R. L. Bax etal, 'IMPO SOER 88-02 Revised Re h tions", date May 10, 1989.

6. NFSR-0075, Rev. O, Control Rod Seg-a 4ner . Simplification, December 1989.

7 Current letter to the Station Manager from the Nuclear Fuel Services Department regarding the qualification status of Station Nuclear Engineers.

4.

Investigation Report, Inappropriate Use of Control Rod Sequence Due to Operations mindset, August 19, 1991.

9.

Investigation Report, Control Rod Mispositioning during Stall Flow N

Testing, May 1, 1991.

10. W.F.Naughton letter to E.D. Eenigenburg, Nuclear Fuel Services and Nuclear Operations Recommendation on Control Rod Surveillances with Intermittent Rod Blocks, dated October 24, 1991.

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