Text

Temporary Change Notice 6-36 to Rev 6 to Operating Instruction SO23-5-1.7, Power Operations
	ML20112C182
Person / Time
Site:	San Onofre
Issue date:	10/16/1995
From:	Grovich F; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20112C180	List: ML20112C178; ML20112C182;
References
	SO23-5-1.7, NUDOCS 9605240254
	Download: ML20112C182 (103)
	v • d • e

_ . ~ .

M ##/885 Submittil No. 6/ apphcable)

REFERENCE. SOtP3-VM.0.1 TEMPORARY CHANGE NOTICE eage i oi 2 95/0000 M7 NOTES: 1) Te if the Docuenent le QA Program AMecetng, then a Technical Spoolfication Violation will occur if CFDM final approval not obtained wtthin 14 days from TCN dsTe'of leeuance.

2) Lf only Editorial Corrections are required,1_ hen form PF(123) 111 should be used (refer to SOf 23-VI 1.0.1).

e un ce D e Single Use TCN Concels *Yk

/ TCN No. , 1t t

. V8 8 # "'

Copy forwarded to the Nuclear Safety Group. PERFORMED BY:

7hA-M Date Part 8 Single use TCN. Yes O No17 Revision No. 6

1. Document No. S023-5-1.7 Docum.m Tme POWER OPERATIONS Document Author / Originator Frank Grovich 87387~ ~ ~ 9/05/95 OPG 2/3 O.% AN44 t ivN WWr 04 TYPE NAME PAA DATE

2. If required, TCN Desation Approval APPROVED BY: -

SamATURE iIF BY TELEcch PHNT NAME AND SO STARE DATE/T6ME CFCM for doengnee)

3. Check oppropriate box: Entire Docurnent Attached C Affected pakg Supersededlincorpotated TCN(s)!EC(e) 6-35 DM (Not applicable for Sing l0 Use TCNs)

NUMBER QF NONE. SO

4. Th ange cannot wait until the next revision of the Document and is re ]g To implement f acility design change (DCP, MMP, TFM, etc.) 95 a.

Facility design change identifier DCP Nd Silf r,, t 2&3-6851.00SJ mwea e<0icATE DCP, MMP, PFC. TFM, ETH (,(,jn %NnFIER has been determine Yes I No O frnplementation of the facihty deai n encimy chan on change has been imps menied I d.

at he, men a TcN cannot be approved umn

b. IOther (e.g., CAR. NRC Comm/tments) Specific Reason: OPERATIONAL NECESSITY RECDUrn enn

- wm Desenption of Change (s) (Use Reverse S/de if Required) SEE PAGE 2 0F 3 UCTJgtone l CITI nn,, .

' H.C QJf y Yee O No I l

5. Could irnplementation of this change pose adverse environmental effects of any type directly or Indirectly?

pr ves, men e TCN le not eueiorised untH a renew from Enverunmental Proinction is obtained. Refer e sot 23-W t.31 Yes O No 7

6. Review requested from other organtratice,s/ disciplines 7 sf ve.PFnzai1toA. or equarawne docwnenanon. ==v me anner.d >

Part C Yes 6 No O l

7. Is the document being TCN'd QA Program Affecting or Level 1 QA Program Affecting? l Ane-w No wur a document is ciasemed as hot CA P,ogram Aposeng The (See a

t.mecated en ew ion for namei Tanw or cemene page # e. see.mont.N time pennits occain iemas and snel apprl approvst r Yes complete tNe section; tien proceed to Part D. # he. men peaceed to Part D.

le the document to be changed an Emergency operating instruction?

YesO No I

a. YesO No 7

b. Is the intent of the original document n'tered?

(if the answer to a or b le Yes, then a TCH le not authorized. A rev6elon la required; ese SO123-Vl-0.9 and SO123-VI 1.)

10 CFR 50.59 Coneideration: 4

c. Has the proposed change already been evaluated for 50.59 consideration or a 7 question Safer / Evaluation prepared us<r's an appj proceas? (Esampise er approved processes we DCP/MMP/rFM/NCRTectwcal Specmcation chanoe assocated procedure Safety Evaluation p )

No 7 Attach PF(123) 109-1 or 50.59 Safety Evaluation (7 questions).

Yes Y Enter Identifier and associated no.

NOTE- W YES, the proposed change meet be addreened in ihe so.se documentaeon ausady genereind Wer to SOMW W NOTE: Both YES and NO may be checked, if applicable.

DCP 2&3-6851.00SJ mR ff/00006 iiioiCAYoCP, MMP. Tm NGM.rECH: SPEC, PROCEDUAE ann NO.

Part 0-JNTTIAL APPHOV -AEVIEWED and APPAOVED SY: ** QW rw\ 'l <N $ , Y? ,3 k-

1. it

" O No cou .T a eh.nge to e Yes*" O No I id m TCN a d m a change b. e 5 pi pians operanon m progreesY eof m

/d49f 1639 3 6 cars Tws

(

sawuTs au q-A g oArE 1w EE. oar i g , ~

V Part E - H b \

5. 0- D and APPROYED / BY:"Y/Y6. QUAUTY ASST.#MN;E- UNITS i. 2 ANO 3 OAfc j

/ OATE COGNGANT FUNC1',04Ac Division MANAGER

N Wel t GA Program Apoctmg & Not QA Pacgrom AMoong. then octam approvai from ew Cogatrant Suponemorp) on the aPeced Unm) [siges on SHO/CFM been paor to submatal to COM QA approveJ may be sequired lor lavel 1 QA Program AFocting TCNa For TCh acproval members of the

. N QA Program, Arlecting. then appsovel shall be by one membat or the Platit Managerment Staft, and one change }

.. m ves then ww satsi supe,me.~.ce": rift a% a enaH provide the esquood SROfCFM approvat The entro document was reviewed in conjur'cti n wttn this TCN and found to be acceptable as written. This constitutes an Part F -(Optrona/) annual /b6ennial review dispositSn of Acce .

Written-Extend (Sot 23-Vk1.0.2).

REVIEWED and APPROVED BY; DATE COGNIZANT FUNCTICNAs OlVISION MANAGER Jt LEStGNEE Part O -For NPG Une Ordy*

ls CA/QC Aaview/ Approval Required 7 wors; use ine computer evowm or cA/oC Rev.= Not Roeweed Report fmmw tht) to respond

c}) Yes O No*

l j

I

W he, emar N/A on the Ousmy Amewance Rowww/Approvapy E.

a sw es th Fn2atoot so se sarcy E,amanon to Yes O No Has a 50 59 Safety Evaluation (7 questio bestuasttehedViiy e

weien ucenses se apphcan6e IFis*w to 80123- W p } Q l b 4 W ,p PERFORMED BY: 310 nm _l /. mA

/ /oAre-3ccr<n2= ita nEv s m s meLEAn paocEq6souppi i

9605240254 960520 PDR ADOCK 05000361 G PDR j

TCN b d6 Site Document No. SO23-5-1.7 Revision No. 6 Page 1 of 1 l 1) Modified procedure to allow throttling open S2(3 maximize Unit Megawatt Output, per SO23-9-1. )1301MU120, First Point Heaters Bypass to

2) Deleted reference to use of Shift Superintendent's PC for Reactivity Calculations due to the program being available on other Control Room computers.

3) Added Secondary Plant Guidelines to Section for Guidelines for Steady State Power Operation.

4) Deleted Note instructing SRO Ops. Su i or all comments have been resolved. pv. to ensure system is in the correct configuration, Action is covered in SO123-0-20.

5) Deleted Note to consider removing Unit 3 V& LPM Recorder from service if many spurious alarms are expected, since this is no longer a problem with new V& LPM system installed per DCP 2&3-6851.00SJ

6) . Corrected called out VCT pressure band to be consistent with current operating philosophy.

7) Changed the called out BSCAL value to CV9005 AVG, which is an average value and the only ABB/CE approved BSCAL value.

I l j

Referm ce: 50123-VI-1.3 Pago 3 of 3 UNREVIEWED SAFETY OUESTION (10 CFR 50.59) SCREENING CRITERIA DOCUMENT No. $023-5-1.7 '

REV. NO. 6 TCN.NO.h~

PART I)

(if applicable) 10 CFR 50.59 REVIEW (Refer to 50123-VI-1.3)

1. Does this new procedure / procedure change alter system / component performance

) or the design configuration of a system important to safety? Yes No x

2. Does this new procedure / procedure change alter the calibration of a system important to safety? Yes No x

3. Does this new procedure / procedure change alter the required actions as a result of not meeting the acceptance criteria or alter Technical Specification numerical dita of a system important to safety? Yes__ No_L

! 4. Does this new procedure / procedure change reduce the level of approval

! required for a plant activity? Yes Nc X S. Does this new procedure / procedure change alter processes for handling, processing, monitoring, or releasing licensed radioactive material M contained in plant systems? Yes No X j 6. Does this new procedure / procedure change violate the provisions of the Technical Specifications? Yes No X l Remarks:

l l

(If required, use reverse side or attach additional sheets.)

PREPARED BY: DATEM/8/f5"

/ Cognizant Indi dual APTROYED BY:

sem Bogni ant Supervi~sor DATE 7' M f Jff, "Yes" is the answeryto any question in Par I),thenSTOPdocumentprocessing. Coordinate Part II) completion with Cognizant Supervisor, or contact Nuclear Procedures Group (NPG) to coordinate Part II) completion with Supervisor. Technical Support, or contact Supervisor, l Technical Support directly; during off-hours contact the on-duty Station Technical Adviser l (STA).

PART II) 50.59 SAFETY EVALUATION DETERMINATION (Required when YES checked in PART !)

Area / Individual Assigned: DATE l (Please Print) i Is a 50.59 Safety Evaluation required based on the new l procedure change? (Refer to $0123-VI-1.3, Attachment 1) procedure / Yes*_ No**

l If YES, complete 50.59 Safety Evaluation per established procedures and attach. STOP document processing if YES_

l answer indicated on 50.59 Safety Evaluation.

If NO, provide justiff catf or (Indicate resources consulted, as applicable):

t I (If required, use reverse side or attach additional sheets.)

PREPARED BYt DATE Cognizant Individual /STA APPROVED BY: DATE CFDM or Designee

! NPG: 1) IfYESinPartII),lht3 notify NPG supervision; forward a copy of this form and associated 50.59 Safety Evaluation (7 questions) to Nuclear Licensing.

2) 11 YES answer is indicated on 50.59 Safety Evaluation (7 questions), M stor document processing and notify NPG supervision; forward a copy of this form, 50.59 Safety Evaluation, and document to huclear Licensing and

, Nuclear Safety Group.

1 3G Pf(123) 109-1. Rev. I 2/95

NUCLEAR ORGANIZATION UNITS 2 AND 3 OPERATING INSTRUCT 10N S023-5-1.7 REVISION 6 PAGE 1 0F 100 l COMPLETE REVISION , TCN _

c EFFECTIVE DATE JUNE 15. 1988 I

POWER OPERATIONS TARLE OF CONTENTS SECTION l

PAGE l 1.0 OBJECTIVE . . . . . . . . . . .,. . . . . . . . . . . . . . . . . . . . 3 l

2.0 REFERENCES

..............,,,,,,,,,,,,,,,, 3 l 3.0 i

PREREQUISITES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.0 PRECAUTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.0 CHECKLIST (S) 1

............................. 9 I 6.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6.1 10 l Preparations for Power Ascension . . . . . . . . . . . . . . . 10 i

6.2 Guidelines During Power Ascension . . . . . . . . . . . . . . . 12 6.3 Power Ascension . . . . . . . . . . . . . . . . . . . . . . . . 18 6.4 Guidelines for Steady State Power Operation . . . . . . . . . . 24 6.5 Preparations for Power Descension . . . . . . . . . . . . . . . 31 l 6.6 Guidelines During Power Descension . . . . . . . . . . . . . . 34 6.7 Power Descension . . . . . . . . . . . . . . . . . . . . . . . 41 6.8 Guidelines for Rapid Downpower Transients . . . . . . . . . . . 44 6.9 Guidelines for Accelerated Downpower Transients . . . . . . . . 46 6.10 E0C Shutdown - Turbine and Reactor Trip from 35% Reactor Power . 46 7.0 RECORDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 ATTACHMENT 1

Maximum Core Power Escalation Rate ..............49 1 2 Turbine Run-up and Loading Rates with Reheat Temperature Control 50 3 Recommended Maximum Rates for Increasin Machine . . . . . . . . . . . . . . . .g Load.on a Heatsoaked

. . . . . . . . . . . 51 4 Recommended Maximum Rates for Increasing Load on a Machine Not Heatsoaked . . . . . . . . . . . . . . . . . . . . . . . . . . 52 l 5 Recommended Maximum Rates for Decreasing Load . . . . . . . . . 53 i 6 Recommended Power Plateaus . . . . . . . . . . . . . . . . . . 54 7 Reactor Power vs. Megawatts . . . . . . . . . . . . . . . . . . . 57 8

Tcol d vs. Reactor Power . . . . . . . . . . . . . . . . . . . . 58 9 Thot. Tavg and Tcold Program . . . . . . . . . . . . . . . . . 59 l 10 Guidelines for Loss of COLSS and COLSS Backup Computer ....60 11 Circulating Water Intake / Discharge Delta T . . . . . . . . . . 62 12 Axial Xenon Oscillation Dampening Example . . . . . . . . . . . 67 13 14 ASI Plot . . . . . . . . . . . . . . . . . . . . . . . . . . .

ASI Control Strategy During Steady State Operation . . . . . .

68 69 15 Power Maneuvering Boration/ Dilution Guidelines . . . . . . . . 72 16 Reactivity Calculator - Xenon Program . . . . . . . . . . . . . 89 17 Boration/ Dilution Calculation . . . . . . . . . . . . . . . . . 90 18 Boration/ Dilution Schedule . . . . . . . . . . . . . . . . . . 91 J7-6.wS1 QA PROGRAM AFFECTING 4

1 l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6- PAGE 2 0F 100

/ TCN (D'b(?_

POWER OPERATIONS TABLE OF CONTENTS (Continuedl ATTACHMENT g 19 Rapid And Accelerated Down Determination . . . . . . power Boration/CEA Insertion

. . . . . . . . . . . . . 92 20 Rapid And Accelerated Downpower Boration/CEA Insertion 21 Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . .

97 EOC Unit Shutdown Parameter Expectations Example .......98 22 Generator Capability Curve . . . . . . . . . . . . . . . . . . 99 l

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Y l

4 4

O

-)

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NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 3 0F 100 l

TCN

/

j POWER OPERATIONS

-l i

i 1.0 OBJECTIVE .

i i 1.1' This procedure is intended to provide procedural guidelines and l strategies for conducting overall plant operations above 15% power.

l

2.0 REFERENCES

l l '

2.1 Licensino Commitments 2.1.1 Technical Specifications 2.1.2 National Pollutant Discharge Elimination System (NPDES)

Permit contained in the Facility Operating License

.1 Unit 2 NPOES Pernit No. CA0108073

.2 Unit 3 NPDES Permit No. CA0108181 2.2 Procedures l 2.2.1 S0123-VI-0.9, " Documents-Author's Guide to the Preparation i of Orders, Procedures and Instructions" l

2.2.2 S0123-III-2.1.23, " Units 2/3 Steam Generator and Condensate /Feedwater Chemistry Control and Sampling l Frequencies" l

2.2.3 S023-V-13. " Modifications to the Nuclear Design Data Book (NDDB) and the Operations Physics Summary (OPS) 2.2.4 S023-V-2, " Power Ascension Testing" 2.3 Goeratinu instructions l

2.3.1 50123-0-25, " Trip / Transient Review" 2.3.2 50123-0-32, " Operations Records and Transmittal" l

2.3.3 S0123-0-42, " Cumulative Equipment Hours, Inopercbility, and Design Cycles" 2.3.4 S023-2-1, " Main Feedwater Pump and Turbine Operation" 2.3.5 S023-2-2, " Condensate Pump Operation" l

2.3.6 S023-2-3, " Heater Drain Pump Operation" l 2.3.7 5023-3-1.3.." Operation of Part-Length CEAs" a

2.3.8 5023-3-2.1, "CVCS Charging and Letdown" f

NUCLEAR ORGANIZATION OPERATING INSTRUCT 10N S023-5-1.7 UNITS ~2 AND 3 REVISION 6 4 ,24 PAGE 4 0F 100

, TCN t0 X -

l

2.0 REFERENCES

(Continued) 2.3.9 5023-3-2.2, " Makeup Operations" 2.3.10 S023-3-2.4, "RCS Purification and Deborating Ion Exchange !

Operation" 2.3.11 S023-3-2.13, " Core Protection / Control Element Assembly Calculator Operation" !

y 2.3.12 5023-3-2.17, " Vibration and Loose Parts Monitoring System" 2.3.13 S023-3-2.21, " Core Operating Limits Supervisory System (COLSS)"

2.3.14 S023-3-3.5, "CEA Monthly Operability Test" 1 2.3.15 S023-3-3.25, "Once-A-Shi ft Surveillance (Modes 1-4)"

l 2.3.16 S023-5-1.1, " Heat Treating the Circulating Water System" 2.3.17 S023-5-1.3.1, " Plant Startup from Hot Standby to Minimum j Load" ;

i 2.3.18 S023-5-1.4, " Plant Shutdown to Hot Standby" 2.3.19 5023-9-2, " Testing Bleeder Trip Valves and Blowdown of Heater Level Alarms" 2.3.20 S023-9-4, " Steam Generator Blowdown Processing System Operation"

)

2.3.21 S023-9-9, " Condenser Overboard Operations" 2.3.22 S023-10-1, " Turbine Startup and Normal Operation" l 2.3.23 S023-10-2, " Turbine Shutdown" 2.4 Other 2.4.1 Operations Physics Summary

, 2.4.2 Letters and Memorandums

.1 CE to SCE Letter S-CE-3973, Fuel Pieconditioning Guidelines

.2 CE to SCE Letter S-CE-8250, Core Operating Guidelines for

, SONGS 2 and 3

.3 Letter from W. Marsh to J. D. Dyer, dated August 14, 1983; j

Subject:

San Onofre Unit Load Limitations (AC-056)

I l-

NUCLEAR ORGANIZATION S023-5-1.7 OPERATING INSTRUCTION UNITS 2 AND 3 REVISION 6 PAGE 5 0F 100

, TCN &

2.0 REFERENCES

(Continued) 2.4.2.4 Letter from J. F. Hirsch to V. B. Fisher, dated January 7, 1988;

Subject:

MSR Live Steam Venting, Unit 2 (MT-173)

.5 Letter from R. Waldo to W. Marsh, dated June 16, 1985;

Subject:

Unit 2 ASI Control (RP-046)

.6 CE to SCE Letter S-CE-9113, CPC Thermal Power Decalibration ' Unit 2

.7 Memorandum for File from R. Waldo, dated July 25, 1985;

Subject:

CPC Responses to SONGS 2 Power Reduction on July 23, 1985 (PPS-044)

.8 Letter from J. T. Reilly to R. W. Krieger, dated September 13, 1985;

Subject:

Full Flow Condensate Polisher Demineralizer (FFCPD) Technical Guidance.

(COND-119)

.9 letter to J. T. Reilly from I. C. Rickard (C-E), dated December 6, 1985;

Subject:

Overlap of CEA Banks for SONGS 2/3 Operation (RP-052)

.10 Memorandum to File from W. G. Zint1, dated December 11, 1985;

Subject:

Regulating CEA Insertion Limits Clarification (RP-052)

.11 Letter from P. H. Penseyres to V. B. Fisher, dated July 23, 1986;

Subject:

Temperature Effects on Purification Ion Exchanger Resin (CVCS-121)

.12 Letter from M. McDevitt to W. Zintl, dated l September 18, 1986;

Subject:

ASI Control Using CEA Group 5 (101-095)

.13 Memorandum For File from N. J. Quigley, dated August 18, 1986;

Subject:

MSRReliefValves(101-094)

.14 Letter from J. A. Mundis to W. C. Marsh, dated December 17, 1986;

Subject:

Circulating Water Delta T (101-111)

.15 Memo from D. Niebrugge to D. Lokker, dated 04/30/87;

Subject:

Recommended Power Levels When Operating With 3 Circulating Water Pumps (101-128) l

.16 Letter from J. F. Hirsch to W. C. Marsh, dated 7 May 1987;

Subject:

Operation of Narrow Range Governor During Load Reduction (MT-156)

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 7 PAGE 6 0F 100

, TCN(O'a/ v-

2.0 REFERENCES

(Continued) 2.4.2.17 Letter from R. W. Waldo to W. C. Marsh, dated 29 May 1987;

Subject:

CEA Motion Restrictions (RP-080)

.18 Memorandum for File from R. W. Waldo, dated September 11, 1987;

Subject:

Evaluation of LPD Changes Due to CEA Motion (RP-082)

.19 Letter from M. d. McDevitt to W. C. Marsh, dated i June 15, 1987;

Subject:

Recommended Limits for Power Ramp Rates (101-131)

.20 Memorandum for File from V. B. Fisher, dated I November 30, 1987;

Subject:

Positive ITC on Unit 2 Reactor l Startup (RP-085)

.21 Special Order 88-01, issued by V.B. Fisher, dated April 19,1988;

Subject:

Forecast Operation of Unit 3 :

l (50-8801)

.22 SONGS LER 2-88-028 (501-894)

.23 Letter from David J. Ramendick, dated January 25, 1989;

Subject:

Updatet. ASI Control Guidance San Onofre Nuclear Generating Station, Units 2 and 3. (101-239)

.24 Letter from J.F Hirsch, dated April 18, 1989;

Subject:

Power Operations with One Main Feedwater Pump, San Onofre Nuclear Generating Station, Units 2 & 3. (10I-257)

.25 Memorandum for File from R. Waldo, oated September 6,1989;

Subject:

Axial Shape Index Control on SONGS 2 End of Cycle 4 Shutdown (10I-279)

.26 Letter from Ray Waldo to V. Fisher, dated December 27, 1989; subject: . Rod Insertion Versus Power Level for ASI Control. (10I-?92)

.27 Letter from J. T. Reilly to R. W. Krieger, dated January 12, 1990;

Subject:

Units 2 and 3 Main Steam Safety Valve Flow Capacity (101-296)

.28 Letter to USNRC from H. E. Morgan, dated October 6,1989;

Subject:

Unit 3 Emergency Chilled Water System LER 89-009 (101-281)

.29 E-Mail from Walter Marsh to Chuck Elliott, dated August 28, 1991;

Subject:

Ramp Rates after Refueling, '

(I0I-378)

.30 E-Mail to T. Vogt from D. Ramendick, dated July 28, 1993;

Subject:

Azimuthal Tilt Guidance (RP-140)

l i _

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 7 0F 100

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l

2.0 REFERENCES

(Continued) 2.4.2.31 E-Mail to V. Fisher from R. Waldo, dated August 11, 1993;

Subject:

Operation at 80% Power with 1 MFW Pump (101-482)

! .32 Letter from W. Strom to J. Hirsch, dated April 1,1993; l

Subject:

INPO SER 91-18, Main Generator Failure due to l Hydrogen Cooler Failure (GEN-196) l .33 E-Mail to D. Hatsford from M. McDevitt dated August 14, i

1994;

Subject:

High Tcold During Physics Testing (RP-143)

.34 E-Mail to D. Hansford from Oscar Flores dated May 10, 1993;

Subject:

Deboration for U2C7 (Ion Exchanger boron removal at EOC). (CVCS-301)

.35 E-Mail to M. Jones from H. McDevitt dated June 6, 1995;

Subject:

Revised Power Ramp Limitations (10I-569)

.36 E-Mail to D. Hansford from R. Clark dated Feb. 17, 1995;

Subject:

U3 Cycle 7 First Point Heater Bypass Operation and Special Test: S03-XXVI-11.3, Unit 3 First Point Heater Extraction Reduction Test. (101-576) 3.0 PRERE0VISITES 3.1 Verify this document is current by checking a controlled copy or by using the method described in S0123-VI-0.9.

3.2 On-shift SR0 Ops. Supv. approval has been obtained.

3.3 Reactor Power is greater than or equal to 15%.

3.4 S023-5-1.3.1 has been completed to the point where power escalation may continue.

3.5 CEDMCS is in MANUAL SEQUENTIAL or OFF, except during ASI control when Reg. Group 5 insertion is performed in the Manual Group Mode.

4.0 PRECAUTIONS 4.1 Reactor Coolant Cold Leg Temperature shall be maintained within the following limits: (Tech. Spec.3.2.6) 4.1.1 At 535-558af when RX power is 30-70% Rated Thermal Power.

4.1.2 At 544-558cF when RX power is greater than 70% Rated Thermal Power.

4.1.3 RCS Cold Leg Temperature may be allowed to drift above 558aF (NOT to exceed two hours) when performing the rapid / accelerated downpower requirements of Attachment 20.

l l

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 8 0F 100 TCN(D'zf, .M _

l 4.0 PRECAUTIONS (Continued)

]

4.2 The Daily Average Differential Temperature (24-hour period, midnight i

to midnight) of the Circulating Water Discharge and Intake shall not i exceed 20.4aF AT. [1] (Ref.2.1.2) 1 4.3 The Instantaneous Differential Temperature of the Circulating Water !

Discharge and Intake shall not exceed 21aF. The Instantaneous '

l Differential Temperature 1s ,

an average taken over one minute.

4.4 Operating the FFCPD with only four beds (4 Cps or 4 MBPs) should be i

minimized when the Unit is at full power, because increased flow

~

l demands on the Condensate Pumps (such as loss of a Heater Drain Pump) could result in an increased pressure drop across the FFCPD. {

l 4.5 Starting the 4th Condensate Pump arms the Condenser Overboard control l System. If controls are set for AUTO with Hotwell cation l conductivity 1.5 pmhos or higher on CR-6700/6701 and/or CR 6702/6703, l then automatic overboarding will be initiated. l 4.6 The chemistry limitations of S0123-III-2.1.23 must be observed at all l times.

1 4.7 The average Pressurizer pressure shall be maintained between '

2025 psia and 2275 psia while in Mode 1. (Tech. Spec. 3.2.8) l 4.8 Jf during operation with CEAs beyond the Long Term Steady State I Insertion Limit for ASI control a failure occurs of 1) COLSS, 2) Both l CEACs, or 3) one CEAC inoperable for more than 7 days, then CEA Group 5 shall be fully withdrawn and CEA Group 6 shall be withdrawn per the requirements of the Tech. Spec. 3.1.3.6.b, and/or Tech. Spec. Table 3.3-1, Item 15 Action 6.

, 4.9 A decrease in letdown temperature will cause a decrease in RCS Boron l L concentration. Conversely, an' increase in letdown temperature w:ll !

cause an increase in RCS Boron concentration. [The Purification Ion i Exchanger resin has a greater affinity to absorb boron at lower temperatures and releases boron at higher temperatures.]

! (Ref. 2.4.2.11) l 4.10 If the Narrow Range Governor (NRG) and Control Valve Open Limit (CVOL) are not set in close proximity of each other (especially during a Turbine load reduction), then the unlikely event of CVOL failure high could result in a primary plant transient.

(Ref.2.4.2.16) l

[1] The Daily Average AT limit ensures the NPDES AT limit of 20af will not be exceeded. Insignificant figures are rounded in accordance with the NPDES

, Permit and Standard Methods (i.e., values up to 20.499aF are rounded down

, to 20aF by Environmental for the monthly NPDES report). AT may rise to 21aF instantaneously, but must be below an average of 520.4af over the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period of midnight to midnight.

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NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 j UNITS 2 AND 3 REVISION 6 PAGE 9 0F 100 t

, TCN I/T 4.0 PRECAUTIONS (Continued) 4.11 Axial Shape Inden 4.11.1 Jf Hot Pin ASI value (CPC PID 187 or PID 266) is greater than + 0.50 or less than - 0.50, then a CPC auxiliary trip will be initiated at power levels above 17%.

4.11.2 When greater than 20'. RX power, then Average ASI shall be maintained within 10.27 with COLSS in service (PID-CV9198), o_r 1 0.20 with COLSS out of service (CPC PID-268). [ Tech. Spec. 3.2.7] .

I l 4.11.3 Failure to maintain Average ASI close to the full power l ESI value during power descension can result in a RX trip due to the Xenon redistribution. effect. (Ref. 2.4.2.25) 4.11.4 Inserting Group 6 CEAs below 80 inches for control of a strongly negative ASI will worsen the problem.

4.11.5 To prevent a CPC generated Trip while using CEA Reg.

Group 5 for ASI control, a minimum separation of at least 15 inches should be maintained between Group 5 and 6.

(Ref.2.4.2.9and2.4.2.10).

4.11.6 On a fast re-start after a RX Trip, if ASI is allowed to remain negative to the ESI value at low power, then Xenon redistribution effect can cause ASI control problems. ,

(Ref.2.4.2.25) I l

4.12 An unused Deborating Ion Exchanger has the capacity to lower RCS boron concentration by approximately 60 ppm at any time of core life.

Following this, no further boron reduction is possible using the DeboratingIonExchanger.(Ref.2.4.2.34) i 4.13 Power shall be maintained below the COLSS Alam (50A02) setpoint. l With Annunciator 50A02 alarming, Reactor Power shall be reduced to 1 clear the alam, or the reason for the alarm shall be clearly understood as a proper response to plant conditions / transients

( e.g., Turbine Stop and Governor Testing, RSHI Sury.) .

4.14 With the COLSS Alarm annunciated, monitor Linear Heat Rate (JI-0011),

DNBR (JI-0012), Reactor Power (CPC), and Azimuthal Tilt (CPC and PMS) to ensure the LCOs for Tech. Specs. 3.2.1 (LPD), 3.2.3 (AZ Tilt), and 3.2.4 (DNBR) are ret.

4.15 Do not place systems in " MANUAL" unless misoperation in " AUTOMATIC" is apparent. Systems placed in " MANUAL" must be checked frequently to ensure proper operation.

5.0 CHECKLISTfS) 5.1 None l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 10 0F 100

, TCN IO 6.0 PROCEDURE 6.1 Preparations for Power Ascension NOTE: All Power Ascension preparations may be performed concurrently or in any order.

6.1.1 Ensure that COL 5S or the COLSS Backup Computer System is in service, or that the applicable surveillances are being performed as directed by 5023-3-2.21.

6.1.2 Estimate pre->lanned power maneuvering boration/ dilution requirements 3ased on desired load and equipment availability per Attachment 15, Power Maneuvering Boration/ Dilution Guidelines.

.1 H the power maneuvering evolution has not been pre-planned, then review Attachment 15, Steps 2.1.1 through 2.1.3.

6.1.3 Notify the Chemistry Department Foreman of the planned power increase.

6.1.4 Determine if S/G and Feedwater/ Condensate Chemistry parameters are within the Normal Range per 50123-III-2.1.23.

.1 H Chemistry is not within the Normal Range then follow the Chemistry Guidelines of Section 6.2.1.

CONTINUED ON NEXT PAGE

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NUCLEAR ORGANfZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 , PAGE 11 0F 100

! 6.0 PROCEDURE (Continued) ,

NOTE: The Equilibrium Shape Index (ESI) is the value of the Axial Shape Index (ASI) of the unrodded core in equilibrium condition at the Power level the core will be brought to for continued j operation.

6.1.5 Determine ESI for the next projected Power Plateau [1]

from the Operations Physics Summary (OPS), Figure 6-1, or from a memorandum approved in accordance with S023-V-13.

(Ref. 2.2.3) l 6.1.6 Initiate ASI monitoring, as follows: (Ref.2.4.2.25)

ASI MONITOR AT RX MONITORING PARAMETER POWER LEVEL % POINT Average ASI 20 - 100 COLSS CV-9198 l 17 - 100 CPC PID-268 Hot Pin ASI 17 - 100 CPC PID-187 l Pseudo Hot Pin 17 - 100 CPC PID-266

.1 Initiate the monitoring of Average ASI using the PMS strip j chart. 1 i

l .2 If the strip chart is not available, then initiate hourly i plotting of Average ASI using Attachment 13.

! 6.1.7 Initiate monitoring of RCS T g using the followin instruments (listed in the preferred order of use)g: ,

.1 PMS - Loop 1, select T112CA (CB, CC, CD); loop 2, select T122CA (CB, CC, CD).

.2 CPCs - Loop 1. Point ID 160; Loop 2, Point ID 161. 1

.3 tis - Loop 1, TI-9178-1 or 3; Loop 2. TI-9179-2 or 4.

.4 TRs - Loop 1, TR-0115; Loop 2, TR-0125.

6.1.8 jf plant conditions permit, then maximize CVCS Purification flow to anticipate a change in RCS Iodine concentration caused by the power increase.

6.1.9 Commence power ascension per Section 6.3 while following the guidelines of Section 6.2.

[1] Planned hold at a given power level of at least 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; normally 100%.

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l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 12 0F 100

, TCN n 6.0 PROCEDURE (Continued) 6.2 . Guidelines Durina Power Ascension 6.2.1 Chemistry Guidelines (Power Ascension)

.1 Ensure S/G and Feedwater/ Condensate Chemistry parameters

are maintained within the Normal Range per f

S0123-III-2.1.23.

.2 H S/G or Feedwater/ Condensate Chemistry parameters are outside the Normal Range, then take action per the

! following guidelines:

.2.1 With Chemistry parameters in the Abnormal Range, power ascension may continue; however, after 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months outside the Normal Range, a plant shutdown should be considered.

.2.2 H Chemistry parameters exceed the Abnormal Range, then notify the Chemistry Supervisor and Unit Superintendent.

A power reduction to less than 25% should be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

, NOTE: Operation at greater than 25% may continue when parameters are returned to within the Abnormal or Normal Range.

.2.3 H S/G sodium concentration exceeds 500 ppb or cation conductivity exceeds 7.0 ps/cm, then inform the Chemistry Supervisor and obtain approval of the Plant Superintendent or his designee and commence a Unit Shutdown.

.3 H Reactor Power change exceeds 15% in a one-hour period, then record the time of the change in the Control Operator's log book, a!1s! notify the Chemistry Department to perform RCS Iodine sample analysis and gaseous release path samples at the required frequencies. (Tech. Spec.

Table 4.4-4, Table 4.11-2)

.4 Based on RCS gaseous activity, operate the Pressurizer Degas System per S023-3-2.1.

.5 H RCS boron concentration is changed by 50 ppm or greater, then force Pressurizer Normal Spray flow until PZR and RCS boron concentrations are within 10 ppm.

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i NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 13 0F 100

, TCN (#'

i 6.0 PROCEDURE (Continued) 6.2.2 ASI Guidelines (Power Ascension) l NOTES: 1. Normally ASI will be less positive in relation to ESI prior to increasing power. Initially, as power is increased, power generation shifts to the bottom of the RX core which results in ESI f being reached. As the power increase continues, CEA withdrawal (in Section 6.3) is required to hold ASI at ESI.

2. ASI is more difficult to control at E00.

.1 During power changes, the preferred CEA sequence for transient ASI control is: PLCEAs (per 5023-3.1.3), Reg.

Group 6, and if necessary, Reg. Group 5.

NOTE: Nonnally Re withdrawn (g. per Group 5 CEAs 5023-3-3.5, should be Attachment 2, CEAfully Position vs. EFPD) when above 50% RX power.

.2 Reg. Group 5 may be used for ASI control under the following conditions: (Ref. 2.4.2.25)

RX power is less than 70% (preferably less than 50's).

Insertion of PLCEAs and Reg Group 6 was insufficient to maintain ASI within 1 0.05 of the ESI value.

COLSS or CBCS is in service. (Tech. Spec.3.1.3.6)

Approval has been granted by the SR0 Ops. Supv.

NOTE: When Reg. Grou) 5 to 6 overlap is increased for ASI control, tien PMS alarms for CEA deviation will annunciate. This is an acceptable condition; however, a CPC trip will be generated without further warning if CEA Group sequencing is violated.

.3 Jf Reg. Group 5 is used for ASI control, then a minimum 15 inch separation between Group 5 and 6 shall be maintained to eliminate the risk of.an out-of-sequence i trip from CPCs. (Ref.2.4.2.9,2.4.2.10,and2.4.2.12) l l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 i UNITS 2 AND 3 REVISION 6 PAGE 14 0F 100 L

l , TCNr Y W i

6.0 PROCEDUR( (Continued) 6.2.2.4 CEA adjustments for ASI control should be accomplished by small (less than 3 in/ min.), smooth, and frequent movements. Whenever possible, the CEA withdrawal guideline, M Step 6.2.2.14 should be followed. l

.5 Ensure CEAs and PLCEAs remain above the Transient l

Insertion Limitations of Tech. Spec. 3.1.3.6 and 3.1.3.7 as applicable. '

.6 Operation of any CEA or PLCEA group below the Long Tenn Insertion Limit shall adhere to the associated time limitations. Since Regulating Group 5 does not have a Short Term Insertion Limit, any Group 5 insertion is limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (Tech. Spec.3.1.3.6)

.7 Log CEA insertions below the Long Term Insertion Limits per S0123-0-42, Attachment 25 and/or 26.

.8 When greater than 20% RX power, then Average ASI Value shall be within 1 0.27 with COLSS in service (PID-CV9198),

gr 10.20 with COLSS out-of-service (CPC PID-268). [ Tech.

Spec. 3.2.7]

.9 Control Average ASI as tightly as CEA insertion limits

~

allow. If possible, then ASI should be maintained within 1 0.05 of the ESI value. When above 40% power and prior to reaching a steady state power plateau, ASI should be maintained within 0.01 of the ESI value.

.10 H Average ASI cannot be maintained within 10.10 of the ESI value, and within the limits of Step 6.2.2.8, then immediately contact Reactor Engineering for support.

.11 H Average ASI cannot be maintained within i 0.20 of the ESI value, and within the limits of Step 6.2.2.8, then consider holding RX power constant until ASI is controlled to within 10.10 (or alternate control value approved by Reactor Engineering). !

.12 Discuss with Reactor Engineering any decision to allow uncontrolled ASI swings. Failure to maintain tight control of ASI will have delayed consequences and may result in a RX trip.

.13 Mhen above 40% power, then all CEAs should be positioned :

in accordance with S023-3-3.5, Attachment 2, CEA Position vs. EFPD, e;; cept as necessary for ASI control or emmency ;

power reduction. However,'if CEAs are inserted foi !

l Power / Temperature control during a load change, then as

, soon es possible, borate and withdraw the CEAs to minimize l the aJverse effect on ASI control.

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f NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 15 0F 100

, TCN 6.0 PROCEDURE (Continued) 6.2.2.14 When above 60% power.1 hen the following guidelines apply for CEA withdrawal: (Ref.2.4.2.17and2.4.2.18)

NOTES: 1. When below 60% power or above 140 inches these guidelines do not apply.

2. The need to control plant stability takes precedence over these guidelines.

.14.1 Limit CEA withdrawals to no more than 10 inches per hour.

.14.2 If full fuel preconditioning has not been achieved

[i.e; restart after a refueling), then limit CEA withdrawals to 1 inch per hour.

.14.3 These guidelines may be superseded by approved station procedures during Physics testing.

.15 Continue monitoring or plotting ASI for a minimum of 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months after completing the power change.

6.2.3 RCS Temperature Guidelines (Power Ascension)

CAUTION Reactor Coolant Cold Leg temperature shall be maintained within the following limits:

(Tech. Spec.3.2.6)

At 535-558'F when RX power is 30-70% Rated Thermal Power.

At 544-558'F when RX power is greater than 70% Rated Thermal Power.

RCS Cold Leg temperature may be allowed to drift above 558'F (NOT to exceed two hours) when performing the rapid / accelerated downpower requirements of Attachment 20.

.1 Maintain Tc within the normal operating band of Attachment 8. Tcold vs. Reactor Power.

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NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 16 0F 100 l

TCN [>gj,V 6.0 PROCEDURE (Continued)

NOTE: For example, a dilution to 100% power results in 98% power with Tc at the programmed level. By picking up slightly more Turbine Load, Tc will decrease and Reactor Power will i increase to 100%. Then as Xenon burns out or builds in, allow Tc to move to the limits of its normal operating band. i 6.2.3.2 H Tc leaves the normal operating band, than borate or i dilute as necessary to return Tc within its normal '

operating band while taking into account the affect on ASI control.

.3 H Tc drops below 544*F when >70% Rx Power E below 535'F i when between 30% and 70% Rx Power, then take action, such i as reducing turbine load, to recover Tc. Use CEAs and '

boration or dilution as necessary to match Rx Power with Turbine load, and restore Tc to within the operating band.

(Tech. Spec. 3.2.6) 6.2.4 Power Level Guidelines (Power Ascension)

NOTE: Shiftly Excore Instrumentation surveillances should be performed either before E after a scheduled Reactor power maneuver due to the effects on channel comparisons when not in a steady state condition.

.1 The applicable Maximum Core Power Escalation Rate of Attachment I should not be exceeded. !

.1.1 H the Maximum Core Power Escalation Rate is exceeded for i any two (2) consecutive hours, lhga stop the power !

increase until the overall average rate is within the guidelines of Attachment 1, and notify Reactor Engineering.

.2 During Power changes the Secondary Calorimetric Power SI indication (CV9005 AVG) may be inaccurate, therefore, use lC '

the COLSS Plant Power indication (CV9000) or COLSS Backup l Computer Plant Power indication. N

.2.1 H COLSS and the COLSS Backup Computer are out of service, I then use the highest PID-217 of the Operable CPC channels.

PID-217 auctioneers the higher value of AT Power (PID-177) and CPC Neutron Power (PID-171).

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NUCLEAR ORGANIZATION UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.7 REVISION 6 y, PAGE 17 0F 100

, TCN V W 6.0 PROCEDURE (Continued) 6.2.4.3 H a positive ITC is known to exist, then the following guidelines apply: (Ref. 2.4.2.20)

.3.1 Assign a dedicated Reactor Operator to monitor Reactor power and control CEA position until a stable load on the Turbine is reached pr a negative ITC is known to exist.

.3.2 Closely monitor'RCS temperature and adjust CEA position to maintain a stable power level. An increase in RCS temperature will tend to increase RX Power. Conversely, a decrease in RCS temperature will tend to lower RX power.

.3.3 Ensure CEAs are maintained in a good " Bite" position (good reactivity position with room to move in both directions).

.3.4 During any inadvertent steam transients power should be controlled by the Operator without waiting for the final effects of doppler.

.3.5 Make all changes slowly and in a controlled manner; be prepared to respond if sudden changes occur.

.4 H this Startup is after a refueling outage, then power calibrations may be suspended at the request of Reactor Engineering during power ascension testing provided power calibration is performed upon reaching a major test plateau and again before continuing to the next plateau.

(Tech. Spec.3.3.1)

.5 During RCS boration/ dilution, periodically adjust the blended makeup setpoint.

.6 When the desired power level is reached, then perform the following:

.6.1 Verify the Turbine Load is blocked by CVOL.

.6.2 Maintain Reactor Power constant by adjustment of load and/or boration/ dilution as required.

.6.3 Follow Section 6.4, Guidelines for Steady State Power Operation.

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w NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-2.7 UNITS 2 AND 3 REVISION 6 PAGE 18 0F 100

/

TCN

f#h 6.0 PROCEDURE (Continued) 6.3 Power Ascension 6.3.1 Throughout the power increase, follow the guidelines of Section 6.2.

6.3.2 Increase RCS temperature b Section for Dilution Mode,yfollowing dilution per S023-3-2.2, hourly flowrates and volumes established in Attachment 15, Power Maneuvering Boration/Dilutien Guidelines and/or Attachment 18, Boration/ Dilution Schedule. Concurrently increase Turbine load as necessary to maintain Tc within the normal operating band of Attachment 8.

.1 Power increase may require boration per S023-3-2.2, Section for Borate Mode, to maintain desired rate of power increase due to Xenon burnup.

6.3.3 20% Reactor Power

.1 J.f not already in service, then initiate placing the remaining Main Feedwater Pump (5023-2-1 , two Heater Drain Pumps (5023-2-3), and at least three Con)densate Pumps (5023-2-2) in service (must be in service by 50% power).

.2 As power is increased from 20% to 40% power, establish ASI at ESI + 0.01 Shape Index Units in accordance with Section 6.2.2, XSI Guidelines (Power Ascension).

.3 After the Main Turbine has been loaded and the SBCS valves Closed with no Open signal, then restore the SBCS to normal, as follows:

CAUTION The SBCS Master Controller, PIC-8431, should be placed in MANUAL prior to changing the setpoint selector switch.

.3.1 Return SBCS Master Controller, PIC-8431, to normal (usually 1000 psi).

.3.2 Place SBCS Master Controller, PIC-8431, setpoint selector in REMOTE.

.3.3 Verify / place SBCS Master Controller, PIC-8431, in AUTO.

.3.4 Verify / place all operable SBCS Valve Controllers in AUTO

.3.5 Return the SBCS Valve Permissive Switches for all operable SBCS Valves to AUTO.

6.3.4 220-250 Nwe Generator Load

.1 Perform the applicable steps of 5023-10-1, to close steam drains and apply live steam to the MSRs.

I NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6

, TCN Wg PAGE 19 0F 100 6.0 PROCEDURE (Continued) l 6.3.5 30-50% Reactor Power

.1 When Unit reaches 330 MWe gross, if permissible, then

increase the Turbine loading rate to 11 MWe/ min. Do not !

exceed the maximum allowable Core Power escalation rate per Attachment 1.

i

.2 At approximately 330 MWe, shift the Blowdown Flash Tank !

Vent to the Third Point heaters per 5023-9-4, Section for Operation of the Blowdown Flash Tank Vent.

1

.3 Between 35% and 50% RX Power start two Heater Drain Pumps per 5023-2-3.

I 1

.4 Prior to exceeding 40% Reactor power, verify the CEAs are i either positioned per S023-3-3.5, Attachment 2, CEA Position vs. EFPD, o.r maintaining ASI at ESI i 0.01 Shape Index Units. I g 6.3.6 450-550 We Generator Load ;

.1 If not reauired for cascade draining, then Close the first through sixth point Feedwater Heaters Startup vents.

4 (Ref. S023-9-1) These vents may be left throttled open if necessary to facilitate cascade draining of Feedwater Heaters.

.2 When

._ e Unit Load reaches 500 MWe, then contact the SCE Switching Center, for the proper System Separation switch selection. ~

l 6.3.7 45-50% Reactor Power

.1 Prior to increasing above 50% power, ensure the PLCEAs are above the Long Term Insertion Limit of 112.5 inches.

(Tech. Spec. Fig. 3.1-3)

CONTINUED ON NEXT PAGE I

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I NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 20 0F 100

, TCN W 6.0 PROCEDURE (Continued)

CAUTION Starting the 4th Condensate Pump arms the Condenser Overboard Control System. If controls are set for AUTO with Hotwell cation conductivity 1.5 pmhos or higher on CR-6700/6701 and/or CR-6702/6703, then automatic overboarding will be initiated.

6.3.7.2 Prior to increasing above 50% power, ensure two Main !

Feedwater Pumps (5023-2-1), two Heater Drain Pumps I (5023-2-3) and at least three Condensate Pumps (5023-2-2) are in service, otherwise limit power per Attachment 6.

NOTE: The Condensate Overboard Control System (C0CS) should be operated per Section 6.4.2.

.3 When 50% power is reached, then ensure the Circulating Water Temperature Data Logger, 2(3)L-168, is in service,

.a_nd ensure 2(3)64A14, Cire. Wtr. Temp. Monitor System Trouble, alann is clear. If the data logger is not in service o_r if 64A14 is alarmin guidelines of Section 6.4.4.) g, then follow the

.4 If the Turbine has been shutdown for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , then after reaching 50% power, blowdown the Feedwater Heater instrument bridles per S023-9-2, Section for Blowdown of FW Heaters and Drain Tank Level Columns. !

6.3.8 50-70% Reactor Power

.1 Adjust CPC Azimuthal Tilt (Tq) Limit Constant (PID 063) to 1.03 per S023-3-2.13.

pT C

N CONTINUED ON NEXT PAGE

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6

, PAGE 21 0F 100

, TCN (D' ['t' .

6.0 PROCEDURE (Continued) l 6.3.9 60-75% Reactor Power NOTE: Main Steam Drain Tanks T-098 and T-101 vent to the opposite First Point Heater than they drain to.

.1 At approximately 60% power, if not required to facilitate cascade draining ajid the associated 1st Point Heater is not out of service, then Close the Main Steam Drain Tank Startup Vents.

S2(3)1301MU528 T-098 Startup Vent (to E-037)

S2(3)1301MU546 T-101 Startup Vent (to E-036) l NOTE: H flow instabilities return during operation, then MSR Live Steam Vents to Cold Reheat may be reopened.

Continued operation with excessive flow oscillation will likely result in a large amount of premature tube failure.

1

.2 When power exceeds 60%, then Close the 13% MSR Live Steam Vents to Cold Reheat and monitor for main steam flow instabilities to the MSRs (E-112 at DPI-2284 & 2285; E-113 ,

at DPI-2290 & 2291). H instabilities are noted, then re-open the 13% Live Steam Vents and notify Station Technical . (Ref. 2.4.2.4)

S2 1301MU1044 MSR E-112 13% Live Steam Vent

S2 1301MU1045 MSR E-11213% Live Steam Vent

S2 1301MU1048 MSR E-113 13% Live Steam Vent S23)1301MU1051 MSR E-113 13% Live Steam Vent

.3 When power exceeds 60%, then to place Feedwater Pump Mini-flow Valves FV-3433 and FV-3432 in MODULATE, perform the following:

To ensure Mini-flow valves will stay closed when placed in MODULATE, verify locally on Mini-flow Controllers FIC-3433 and/or FIC-3432, flow indicating greater than 10,000 gpm.

l Place the valve handswitches (one valve at a time) in MODULATE.

Monitor the system response and adjust as necessary.

1

( NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UN!TS 2 AND 3 REVISION 6 PAGE 22 0F 100

, TCN W Y 6.0 PROCEDURE (Continued)

I 6.3.9.4 When both Heater Drain Pumps are in service, t!}e3 (at the discretion of the SR0 Ops. Supv.) place Condentate Pucp P-053 in AUTOMATIC per S023-2-2.

.5 Prior to exceeding 70% Jower: if Reg. Group 5 CEAs were used for ASI control, tien ensure Reg. Group 5 CEAs are fully withdrawn per 5023-3-3.5 Attachment for CEA Position vs. EFPD. (Tech. Spec. Figure 3.1-2)

.6 After reaching 70% power, And n while continuing to 100%

steady state, then closely monitor by group trend E-036 and E-037, First Point Feedwater Heaters, shell side water level and drain temperature. Use PMS Points TE3957 for E-036 and TE3941 for E-037. Adhere to the following guidelines:

NOTE: FW Heater shell side blow-by will cause drain

'tamperatures to increase significantly (10af or more) above 100% power steady state values.

.6.1 To prevent shell side blow-by, maintain shell side water level at approximately the 100% power steady state level.

.6.2 H shell side level falls out of the nonnal range, o_t if drain temperature exceeds 386aF, then request the I&C Department to readjust level.

.7 When power is 2:75%,thenposition2(3)HS-2808,VacuumTrip Setpoint Select Switch, to 6.5 INCHES HG.

6.3.10 90-95% Reactor Power

.1 Prior to exceeding 95% Power, verify CPC Nuclear Power and AT Power indications agree with COLSS (or COLSS Backup computer) calculated Power per 5023-3-3.25, Attachment for Power Distribution and Burnup Log.

.2 Monitor Condenser Circ. Water AT to ensure that 'the daily average AT does not exceed 20.4aF when 100% Power is reached.

.2.1 H it is projected that the unit will exceed a circ. Water daily average AT of 20.4aF, then hold Power at a level that will maintain the daily average AT at less than 20.4aF, and notify the Unit Superintendent and the Station NPDES Engineer. (Ref.2.1.2)

l l

NUCLEAR ORGANIZATION 5023-5-1.7 UNITS 2 AND 3 OPERATING INSTRUCTION f REVISION 6 PAGE 23 0F 100 j 6.0 PROCEDURE (Continued) 6.3.11 100% Reactor Power

.1 Final adjustment to Power level should be made in small incremental reactivity changes using dilution or boration i

per S023-3-2.2, as applicable.

.2 Following a plant restart and return to full )ower, do not l l exceed 100.5% Reactor Power as indicated by t1e highest PID-217 of the Operable CPC channels until an excore calibration has been completed per S023-3-3.2.

,qSLT1Q'i If the Narrow Range Governor and Control Valve Open Limit (CVOL) are not set in close proximity of each other, then the unlikely event of CVOL failure high could result in a primary i plant transient. l 1

.3 During normal operation, the CVOL and Narrow Range Governors should be e.aintained within close adjustment of each other. This can be accomplished by adjusting the non-controlling Governor down until it becomes in control, then re-adjust up slightly until the desired Governor resumes control.

.4 Maintain Generator MVARs within the limits of Attachment 22.

{

NOTE: Throttling Open TV-2579, Generator Cooler Bypass '

Valve, ensures that a failure of TV-2579 will l not result in total loss of Hydrogen Gas Cooling !

flow. (Ref.2.4.2.32)

.5 Position the Generator Evdrogen Cooler Bypass Valve per S023-6-18, attachment for Generator Hydrogen Cooler Flow Configuration.

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i NUCLEAR ORGANIZATION UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.7 REVISION 6 , PAGE 24 0F 100 f

6.0 PROCEDURE (Continued) 6.4 Guidelines for Steady State Power Ooeration 6.4.1 First Point Heater Bypass Guidelines "

.1 When Full Load is reached, then Open/ Throttle .

' 52(3)l305MU120,per5023-9-1, Attachment for Opening / Throttling First Point Heaters Bypass Valve. T Maximize Megawatt output by Throttling S2(3)l305MU120, as g required throughout core life. (Ref. 2.4.2.36) N 6.4.2 Chemistry Guidelines (Steady State)

.1 When the Secondary Chemistry parameters of S0123-III-2.1.23 are within the Normal Range, .then Steam Generator Blowdown may be reduced to 200 gpm total.

.2 After a change in S/G blowdown rates, then K9008 and K9009, COLSS Blowdown Constants, should be updated per S023-3-2.21.

NOTE: 1. Secondary Chemistry Limits are divided into

three groups

Normal Range

Abnormal Range Immediate Shutdown Limits

2. The following are basic Guidelines and Recommendations from S0123-III-2.1.23.

Compliance with these actions will provide a more reliable overall secondary system with fewer repairs due to long-term corrosion problems.

.3 If the Normal Ranae is exceeded, then immediate investigation of the problem will be initiated. If the parameter (s) is (are) not returned to within Normal Range within one week,.then a recommendation to reduce Power to

<30% will be issued.

i

NUCLEAR ORGANIZAT10N UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.7 REVISION 6 PAGE 25 0F 100

/

6.0 PROCEDURE (Continued) l j

6.4.2.4 i

H the Abnormal Ranae is exceeded, then Chemistry Dept.

will request a power reduction to <30% Power. This power reduction should begin within four hours of exceeding the Abnonnal Range.

! .5 H an ]mmediate Shutdown Limit is exceeded regardless of I duration, then the Unit should be shutdown to at least Mode 2 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . !

l CAUTION A decrease in letdown temperature will cause a l decrease in RCS boron concentration. {

Conversely, an increase in letdown temperature will cause an increase in RCS boron concentration. [The Purification Ion Exchanger resin has a greater affinity to absorb boron at lower temperatures and releases boron at higher temperatures.] (Ref. 2.4.2.11)

.6 After PZR and RCS boron concentration are within 10 ppm, t ensure PZR Backup Heaters are energized as required tiell to maintain PZR Proportional Heater capacity at approximately 50% (indicated by PIC-0100, Pressurizer Pressure Controller, output signal of approximately 33%).

CAUTION Operating)the or 4 MBPs should FFCPD with only be minimized fourthe when beds Unit(4isCps at full power, because increased flow demands on the Condensate Pumps (such as loss of a Heater Drain Pump) could result in an increased ;

pressure drop across the FFCPD. j

.7 With the FFCPD in service (bypass valves closed), operate theCondensateOverboardControlSystem(C0CS)inManual ,

to prevent unnecessary overboarding/ power reduction during i the final flush of a FFCPD polisher. This poor quality final flush water will be cleaned u) as it passes through the in-service polisher vessels wit 1out the need for overboarding. Operation of the C0CS in Manual is addressed in 5023-9-9. (Ref.2.4.2.8) '

.8 When all of the following conditions are met, then the l C0CS should be operated in Automatic:

The FFCPD bypass valves are open; '

I

Four Condensate Pumps are operating, o_r three Condensate Pumps are operating with Condensate Pump P-053 selected to AUT0/0FF; Two lieater Drain Pumps are operating.

l NUCLEAR ORGANIZATION UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.7 REVISION 6 PAGE 26 0F 100

, TCN W 6.0 PROCEDURE (Continued) 6.4.3 Circulating Water Guidelin6s

.1 Whg11 above 50% power, than :nonitor Condenser Circulating Water tesy,erature AT using the Cire. Water Temperature Data Logger, 2(3) L-168.

.2 H the Circ. Water Temperature Data Logger, 2(3)L-168, is out of service 4C if 2(3)64A14, CIRC. WTR. TEMP. MONITOR SYSTEM TROUBLE, is in the alarm condition, lhta initiate monitoring per Attachment 11. (Ref. 2.1.2)

.2.1 Monitoring per Attachment 11 shall remain in effect until the data logger is returned to service and 2(3)64A14 has cleared. l

.3 H Circulating Water Conduit reverse flow exists for greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during heat treat, then initiate monitoring per Attachment 11. i i

6.4.4 Power Level Guidelines (Steady State)

.1 Monitor power based on Secondary Calorimetric Power, PMS PID CV9005 AVG.

l0

.2 N Maximize Unit generation. H at full power plateau, than when conditions allow, average Reactor Power over the entire shift.

.3 Power shall be maintained such that the COLSS Alarm (50A02) is not annunciated. H the alarm is annunciated, then determine the cause for the alann and complete the following:

.3.1 H Annunciator 50A02 is alarming due to exceeding a Power Operating Limit, than reduce power to clear the alarm.

.3.2 H Annunciator 50A02 is alarming due to an understood condition that affects COLSS power calculations (e.g.

Turbine Stop/ Governor valve test, RSMI Sury.), than comence monitoring Linear Heat Rate (JI-0011), DNBR (JI-0012), Reactor Power (CPC), and Azimuthal Tilt (CPC and PMS) to ensure compliance with Tech. Specs. 3.2.1 (LPD), 3.2.3 (AZ Tilt), 3.2.4 (DNBR).

.4 H Azimuthal Tilt exceeds 0.03 during steady state conditions, ihan initiate a Non-Conformance Report.

(Ref. 2.4.2.30)

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 27 0F 100

/ '

, 6.0 PROCEDURE (Continued) i j 6.4.4.5 H a transient (i.e., uncontrolled Power decrease, Pressure or Temperature change) occurs, then after conditions are stabilized, borate as necessary to restore I CEAs to the desired axial shape control position. j

.5.1 H required by the Shift Superintendent or Shift Technical Advisor after the transient, then implement the applicable l

ortion of S0123-0-25 for transient review and ;

ocumentation.

1 CAUTION An unused Deborating Ion Exchanger has the l capacity to lower RCS boron concentration by approximately 60 ppm at any time of core life.

Following this, no further boron reduction is possible using the Deborating Ion Exchanger.

1

.6 To minimize (dilution) radwaste volume at E0L, RCS boron concentration should be lowered by using ion exchangers. Refer per 5023-3-2.4 Section for Reducing Boron Concentration Using a Purification Ion Exchanger.

6.4.5 Secondary Plant Guidelines

.1 When Reactor Power is t 80%, then maintain Secondary Plant conditions as follows:

Steam Generator Pressure, based on the average readings of all available channels from Point ids PT1013 (1-4) and PT1023 (1-4) or equivalent [1], is t 825 psia Feedwater Temperature, based on the average readings from Point ids TE3921 and TE3922 or equivalent [1], is 2 410*F y

+

Feedwater Flow on Point ids P01112 and PD1122, or O PD1111 and PD1121 [1], is a 165 inches of water N l

l [1] Plant parameter may be monitored by any of the following available methods; i PMS, Control Panel indication, or COLSS alarm (when software modification iscompleted). ,

7+ .- ew .-.- -

NUCLEAR ORGANIZATION OPERATING TNSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 28 0F 100 6.0 PROCEDURE (Continued) 6.4.6 RCSTemperatureGuidelines(SteadyState)

NOTES: 1. To minimize Steam Generator corrosion over the duration of plant life, Tcold should be maintained as close as possible to 553*F during steady state conditions at 100% power.

2. When controlling RCS temperatures by Tcold, then programmed values for That and Tavg should follow per Attachment 9.

CAUTION Reactor Coolant Cold Leg temperature shall be maintained within the following limits:

(Tech. Spec. 3.2.6)

=

At 535-558af when RX power is 30-70% Rated Thermal Power.

At 544-558+F when RX power is greater than 70% Rated Thermal Power.

RCS Cold Leg temperature may be allowed to drift above 558af (NOT to exceed two hours) when performing the rapid / accelerated downpower requirements of Attachment 20.

.1 Maintain Tcold within the normal operating band of Attachment 8 (qd as close as possible to the program value during steady state (e.g., *0.5aF).

.2 Monitor Tcold using the instrument indication that is most representative of the average Tcold. This value may be obtained from TCOLDAVG on CFMS (using PMARS) gr by averaging all of the indications for one of the following instrument methods (listed in preferred order of use):

PMS Method: Loop 1 Til2CA, Tll2CB, Tll2CC, T112CD Loop 2 T122CA, T122CB, T122CC, T122CD

CPC Method: Loop 1 PID-160 Loop 2 PID-161

MCB Method: Loop 1 TI-9178-1 or TI-9178-3 Loop 2 TI-9179-2 or TI-5179-4

REC Method: Loop 1 TR-0115 Loop 2 TR-0125

.3 If space is available on PMS, then the most representative indication of average Tcold should be placed on the Alarming Trend Recorder with alarm setpoints as directed by the SRO Ops. Supv.

l 1

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 i UNITS 2 AND 3 REVISION 6 PAGE 29 0F 100 i TCN (lY l 6.0 PROCEDURE (Continued) 6.4.7 CEA Guidelines (Steady State)

.1 Eh e Part length and Group 6 CEAs are not being used for j ASI control,.th e position in accordance with EFPD ;

(S023-3-3.5, Attachment for CEA Position vs. EFPD). ;

.2 Borate or dilute as required to achieve CEA position !

per S023-3-2.2.-

6.4.8 ASI Guidelines (Steady State)

NOTE: ASI may be permitted to swing for determining ESI if directed by Reactor Engineering.

.1 Maintain ASI at the ESI 0.05 Shape Index Units per the Operations Physics Sumary, Figure 6-1 or as directed by a memorandum approved in accordance with S023-V-13.

(Ref.2.2.3)

.1.1 If the ESI per the Operations Physics Sumary differs from the " observed ESI" (ASI average over an oscillation cycle), then the " observed ESI" may be used at the SRO Ops. Supv. discretion. (Ref. 2.4.2.22)

.2 Make adjustments to ASI per Attachment 14, ASI Control Strategy During Steady State Operation.

CONTINUED ON NEXT PAGE h

6 0 b 100 i - -,

6.0 PROCEDURE (Continued) 6.4.9 Unexpected Plant Transient during Steady State Operation CAUTION Do not place systems in " MANUAL" unless misoperation in " AUTOMATIC" is a) parent.

Systems placed in " MANUAL" must ae checked frequently to ensure proper operation.

.1 H a Primary to Secondary Power mismatch occurs (e.g., an HP Stop or Governor Valve fails closed 1 or SBCS malfunction), then reduce Reactor Power !

and/or increase Secondary Power to restore plant l balance as follows: !

.2 Verify proper automatic SBCS response or manually operate the SBCS to balance Secondary Power with i Primary Power.

l

.3 H necessary to lower Primary Power, . thin Place CEDMCS in manual sequential and insert CEAs to match Tave to Tref.

.4 H a transient (i.e., uncontrolled Power decrease, Pressure or Temperature change) occurs, then after conditions are stabilized, borate as necessary to restore CEAs to the desired axial shape control position, and ensure Reactor Power and Turbine Load are matched.

.5 If desired to lock down a failed HP Stop or Governor Valve, then refer to 5023-10-3, Attachment for Procedure ,

to Remove a Unitized Actuator from Service During on Load Operation.

.6 When the transient is stabilized, then ensure any control systems that have been place in Manual are returned to Automatic Operation per applicable Operating Instructions.

.7 H required by the Shift Superintendent or Shift Technical Advisor after the transient, then implement the applicable portion of S0123-0-25 for transient review and documentation.

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 31 0F 100 TCN (V 6.0 PROCEDURE (Continued) 6.5 Preparations for Power Descension NOTES: 1. This Section concerns decreasing plant load to a lower power plateau. All Power Descension preparations may be performed concurrently or in any order.

2. If the power descension is to be followed by a shutdown and cooldown, then Steps 6.5.2 and 6.5.3 should be initiated approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to starting the power descension in order to save time degassing the RCS.

6.5.1 Refer to unit outage schedule and outage package to determine the time to start load reduction, anticipated time Unit will be off-line, if Turbine tests will be conducted, and whether any special tests, procedures or observations will be mada during load reduction.

6.5.2 jf a cooldown is planned, thgn to assist with RCS Degassing, perform the following: (N/A if a cooldown is notplanned.)

H CAUTION When VCT Pressure is less than 25 psig, then the 'T plant is in a moderate risk evolution due to the g potential for Charging Pump gas binding.

N

.1 Lower the setpoint of PCV-9213, VCT Hydrogen Regulator, as follows:

ST 15 to 25 psig as directed by the SR0 Ops. Supv. C N ;

5 to 15 psig as directed by the Chemistry Division

.2 Log the new PCV-9213, VCT Hydrogen Regulator, setpoint in the C.O.'s Log.

NOTE: Burping the VCT pressure down to the new setpoint may waste Hydrogen by causing the VCT Hydrogen Regulator to open.

.3 Lower VCT pressure to iust above the new setooint by burping the VCT per 5023-3-2.1, Section for Burping the VCT.

.4 Notify the Chemistry Dept. that VCT Hydrogen pressure has been reduced. .

l NUCLEAR ORGANfZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 32 0F 100 ;

6.0 PROCEDURE (Continued)

NOTES: 1. In order to avoid scheduling conflicts and possible entry into Technical Specification Actions, ESF components common to both !

Units should be supplied / powered from the Unit remaining in the 1 higher Mode of operation if a shutdown to Mode 5 is planned.

(Ref. 2.4.2.28) 1

2. H the ESF component 4ransfers are ' initiated' in the next step, then they must be completed prior to removing the Turbine-Generator from service.

6.5.3 H the Unit shutdown will be to Mode 5, then initiate I transferring the following ESF components to the Unit remaining in the higher Mode of operation: (N/A if a shutdown to Mode 5 is not planned.)

.1 Initiate transfer of Emergency Chiller E-335 power source per S023-1-3.1 and CCW supply per 5023-2-17.

.2 Initiate transfer of Emergency Chiller E-336 power source per S023-1-3.1 and CCW supply per 5023-2-17.

i NOTE: In order to avoid additional TGIS and CRIS '

actuations, TGIS and CRIS power transfer should be coordinated with the transfer of MCC BS and BQ.

l

.3 Initiate transfer of MCC BS and BQ per S023-6-3.2. i

.4 Initiate transfer of TGIS per S023-3-2.29, Attachment for j Transferring Logic Power Supplies.

I

.5 Initiate transfer of CRIS per S023-3-2.24.6, Attachment for Transferring Power Supplies.

6.5.4 If Power Descension will decrease power to < 75%, then ,

determine pre-planned power maneuvering boration/ dilution requirements based on desired load and equipment availability per Attachment 15, Power Maneuvering Boration/ Dilution Guidelines.

.1 H the power maneuvering evolution has not been pre-planned, then review Attachment 15, Steps 2.1.1 through 2.2.5.

6.5.5 If Power Descension will decrease power to a 75%, then Attachment 19, Rapid and Accelerated Downpower Boration/CEA Insertion Determination, may be used to calculate the volume of boric acid o_r Group 6 CEA position required to attain various target power levels.

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 33 0F 100 TCN_h" 6.0 PROCEDURE (Continued) 6.5.6 Notify the Chemistry Department Fore: nan of the planned power decrease.

6.5.7 For reduced power operations anticipated to last less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , maintain ASI at the initial equilibrium (typically HFP) value.

.1 H the duration'of the reduced power operation is anticipated to be greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , _ thall contact Reactor Engineering for ASI control recommendations.

.2 H the duration of the reduced power operation is extended, a_n_d the change will extend past 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then contact Reactor Engineering for specific guidance.

(Ref.2.4.2.23) 6.5.8 Initiate ASI monitoring, as follows: (Ref.2.4.2.25)

ASI MONITOR AT RX MONITORING PARAMETER POWER LEVEL % POINT Average ASI 20 - 100 COLSS CV-9198 17 - 100 CPC PID-268 Hot Pin ASI 17 - 100 CPC PID-187 Pseudo Hot Pin 17 - 100 CPC PID-266 )

l 6.5.9 H the Power reduction is to a plateau above 40% power, then initiate monitoring of Average ASI using the PMS Strip Chart., (N/A if decreasing to less than 40%.)

.1 H the PMS Strip Chart is not available, then initiate hourly plotting of ASI using Attachment 13.

6.5.10 Initiate monitoring of RCS Tcold using the following instruments (listed in the preferred order of use):

.1 PMS - Loop 1, select T112CA (CB, CC, CD); Loop 2, select T122CA (CB, CC, CD).

.2 CPCs - Loop 1, Point ID 160; Loop 2, Point ID 161.

.3 tis - Loop 1, TI-9178-1 or 3; Loop 2, TI-9179-2 or 4.

.4 TRs - Loop 1 TR-0115; Loop 2, TR-0125.

6.5.11 To enhance system response to plant transients, commence forcing Pressurizer Nomal Spray flow as directed by the 5R0 Ops. Supv.

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 :

UNITS 2 AND 3 REVISION 6 PAGE 34 0F 100

/

6.0 PROCEDURE (Continued) j 6.5.12 If plant conditions permit, then maximize CVCS !

Purification flow to anticipate a change in RCS Iodine concentration caused by the power reduction. l l

l 6.5.13 If the power decrease is occurring at End Of Cycle (RCS l baron concentration less than 50 ppm), then three Charging !'

Pumps should be maintained available to provide maximum deboration capability. (Ref. 2.4.2.21) 6.5.14 7 If power for is intentionally e one week, reduced to curtail ensure Closed S2(3)1305MU120, First plant Point output, " O ,

Feedwater Heater Bypass Valve. N t 6.5.15 Commence power descension per Section 6.7 while following ,

the guidelines of Section 6.6.

6.6 Guidelines Durino Power Descension l

POWER DESCENSION RATE GUIDELINES RATE CLASSIFICATION DEFINITION 3 TO 15 %/Hr Normal Power decrease within the guidelines of Attachment 5.

Rate of power decrease to be used when shutdown 15 to 60 %/Hr Accelerated is occurring in response to a Tech. Spec. Action Statement or a power reduction is required by Tech. Spec. (e.g dropped CEA)

I to 5 %/ min Rapid Rate of power decrease to be l used when power decrease must be accomplished rapidly to prevent a Rx Trip (loss of a MFWP or Circ Water Pump) gr in response to actions from i

an A0I (SGTL)

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 35 0F 100

, TCN b'h 6.0 PROCEDURE (Continued) 6.6.1 Chemistry Guidelines (Power Descension)

.1 H Reactor Power change exceeds 15 percent in a one-hour period, then record the time of the change in the Control Operator's log book, ad notify the Chemistry Department to perform RCS Iodine sample analysis and gaseous release path samples per the required frequencies.

(Tech. Spec. Table 4.4-4, Table 4.11-2) 4

.2 Based on RCS gaseous activity, operate the Pressurizer Degas System per S023-3-2.1.

.3 H RCS boron concentration is changed by 50 ppm or greater, then force Pressurizer Normal Spray flow until PZR and RCS boron concentrations are within 10 ppm.

6.6.2 ASI Guidelines (Power Descension)

.1 During power changes, the preferred CEA sequence for transient ASI control is: PLCEAs (per S023-3-1.3),

Reg. Group 6, and if necessary, Reg. Group 5.

NOTE: Normally Reg. Group 5 CEAs should be fully withdrawn (per S023-3-3.5, Attachment 2, CEA Position vs. EFPD) when above 50% RX power. ]

.2 Reg. Group 5 may be used for ASI control under the following conditions:

RX power is less than 70% (preferably less than 50%). ,

Insertion of PLCEAs and Reg Group 6 was insufficient to maintain ASI within 2 0.05 of the ESI value.

COLSS or CBCS is in service.

(Tech. Spec. 3.1.3.6)

Approval has been granted by the SR0 Ops. Supv.

/

NUCLEAR ORGANIZATION OPERATING INSTRUCTION 5023-5-1.7 l UNITS 2 AND 3 REVISION 6 PAGE 36 0F 100

, TCN b' 6.0 PROCEDURE (Continued)

NOTE: When Reg. Group 5 to 6 overlap is increased for ASI control, then PMS alarms for CEA deviation will annunciate. This is an acceptable condition; however, a CPC Trip will be generated without further warning if CEA Group sequencing is violated.

6.6.2.3 If Reg. Group 5 is used for ASI control, then a minimum 15 inch separation between Group 5 and 6 shall be maintained to eliminate the risk of an out-of-sequence trip from CPCs.

l

.4 CEAs and PLCEAs shall remain within the Transient Insertion Limitations of Tech. Spec. 3.1.3.6 and 3.1.3.7. l

.5 Operation of any CEA or PLCEA group below the Long Term l Insertion Limit shall adhere to the associated time l limitations. Since Regulating Group 5 does not have a l Short Tenn Insertion Limit, a_py Group 5 insertion is !

limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (Tech. Spec.3.1.3.6) l

.6 CEA insertions below the Long Term Insertion Limits shall be logged per S0123-0-42, Attachment (s) for Regulating CEA Insertion Limits and/or Part Length CEA Insertion Limits as applicable.

NOTE: The maximum dampening position of any CEA group is approximately 85-92 inches depending upon actual Average ASI value. Further insertion may help Average ASI, however the CPCs may calculate a worse Average ASI.

.7 CEA adjustments for ASI control should be accomplished by .

small (less than 3 in. per min.), smooth, and frequent movements.

CONTINUED ON NEXT PAGE

T l NUCLEAR ORGANIZATION OPERATING INSTRUCTION 5023-5-1.7 l UNITS 2 AND 3 REVISION 6 PAGE 37 0F 100 l

, TCN hN 6.0 PROCEDURE (Continued) 6.6.2.8 The recommended CEA insertion strategy for maintaining Average ASI close to 0.0 at EOC is, as follows:

(Ref.2.4.2.25)

% RX PLCEAs GROUP 6 GROUP 5 l POWER INCHES INCHES INCHES 1

100 150 150 150 95 139 150 150 90 127 150 150 85 116 150 150 80 115 [2] 140 150 75 115 129 150 70 115 117 150 [1]

65 115 106 150 60 115 95 150 55 115 83 150 50 115 75 150 45 101 75 150 40 89 75 150 35 78 75 150 30 75 75 150 25 75 75 131 20 75 75 119 NOTE: The following strategy is designed to minimize Xenon redistribution in the Core and its adverse effect on ASI (especially at EOC) during power reduction.

.9 )Lh.gu greater than 20% RX power, Mign maintain Average ASI Value within 10.27 with COLSS in service (PID-CV9198), o.r

+ 0.20 with COLSS out-of-service (CPC PID-268).

ITech. Spec.3.2.7]

.10 Control Average ASI as tightly as CEA insertion limits allow. If )ossible, then ASI should be maintained within 1 0.05 of tie full power ESI value (see Step 6.5.9).

.11 _lf Average ASI cannot be maintained within 1 0.10 of the full power ESI value, a_nd within the limits of Step 6.6.2.8, thgn immediately contact Reactor Engineering for support. ;

i

[1? Group 5 may be used below 70% power; see Step 6.6.2.2.

[2? PLCEA Transient Insertion Limit .

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 38 0F 100

, TCN D 6.0 PROCEDURE (Continued) 6.6.2.12 If Average ASI cannot be maintained within 1 0.20 of the TEll power ESI value, and within the limits of Step 6.6.2.8, then consTder holding RX power constant until ASI is controlled to within + 0.10 (or alternate control value approved by Reactor Engineering).

.13 If Average ASI is greater than + 0.20, then monitor Hot PTn ASI (CPC PID-187) closely. -

.14 Discuss with Reactor Engineering any decision to allow uncontrolled ASI swings. Failure to maintain tight control of ASI (especially at EOC) will have delayed consequences and may result in a RX trip.

.15 When above 40%

per S023-3-3.5, power,hiireM for CEA Position vs. EFPD.then all CEA Attac except as required for ASI control or emergency power reduction.

.16 J_f power reduction is to a plateau above 40% power then continue monitoring / plotting ASI for a minimum of 50 nours after completing the power change.

6.6.3 RCS Temperature / Pressure Guidelines (Power Descension)

CAUTION Reactor Coolant Cold Leg temperature shall be l maintained within the following limits:

(Tech. Spec.3.2.6)

1. At 535-558aF when RX power is 30-70% Rated Themal Power.

2. At 544-558'F when RX power is greater than 70% Rated Thermal Power.

l

3. RCS Cold Leg temperature may be allowed to drift above 558aF (NOT to exceed two hours downpo)wer requirements of Attachment 20.when perform

.1 Maintain Tc within the nomal operating band of Attachment 8, Tcold vs. Reactor Power.

.2 If the power decrease is occurring at End Of Cycle (RCS then Turbine load Foron should concentration be used to maintainless Tcthan 50 ppm) in the h igh end of the normal Power. op(erating band of This guideline willAttachment 8, Tcold vs. Reactor assist in recoverin unanticipated Xenon transients.) (Ref. 2.4.2.21)g from any

.3 Lf Tc drops below 544af when >70% Rx Power AC below 535'F when between 30'. and 70% Rx Power, then take action, such as reducing turbine load to recoverTc. Use CEAs and boration or dilution as n,ecessary to match Rx Power with Turbine load, and restore Tc to within the operating band.

(Tech. Spec. 3.2.6)

.4 After completin PIR7RCS boron, g the then power decrease terminate forcing PZRandSpray any matching flow. of

l l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 39 0F 100 6.0 PROCEDURE (Continued) 6.6.4 Power Level Guidelines (Power Descension)

NOTE: Shiftly Excore Instrumentation surveillances should be performed either before at after a i

' scheduled Reactor power maneuver due to the effects on channel comparisons when not in a steady state condition.

l NOTE: The licensed Power Limit is factored into the COLSS Power Limit Margin Display JI-0013 and COLSS Backup Computer Pcwer Limit Margin Display.

T

.1 During Power changes the Secondary Calorimetric Power RC indication (CV9005 AVG) may be inaccurate, therefore, use IN the COLSS Plant Power indication (CV9000) or COLSS Backup Computer Plant Power indication. .

.l.1 H COLSS and the COLSS Backup Computer are out of service, lhtJ1 use the higher of CPC AT Power (PID-177) or CPC Neutron Power (PID-171).

.2 H Reactor Power is being decreased by boration, then slow down or stop boration prior to reaching the desired Reactor Power level. This will lessen an overshoot due to transit time for the Charging Pump discharge to reach the core and due to Xenon buildup.

.2.1 During RCS boration, periodically adjust the blended makeup setpoint.

CAUTION An unused Deborating Ion Exchanger has the capacity to lower RCS boron concentration by approximately 60 ppm at any time of core life. 4 Following this, no further boron reduction is possible using the Deborating Ion Exchanger.

.2.2 H the power decrease is occurring at End Of Cycle (RCS boron concentration less than 50 ppm), ihan use the Deborating Ion Exchanger to limit overshoot and decrease the associated recovery time. (Ref. 2.4.2.21)

.3 H the power decrease is occurring at End Of Cycle (RCS boron concentration less than 50 ppm), _qnd a sudden drop in power occurs (greater than 3/. In less than 30 minutes),

then power must be returned to near its original value within 15 minutes. Otherwise the resultant Xenon l transient may be difficult to stop by dilution alone.

~

(Ref. 2.4.2.21) i

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION.6 PAGE 40 0F 100

, TCN b 6.0 PROCEDURE (Continued) 6.6.4.3.1 To restore from the sudden power drop quickly; use erature to insert a large amount of moderator reactivity. temp (A one degree change in temperature will result in approximately a one percent change in Reactor power.)

.3.2 To restore temperature to the high end of the normal ope.ating band;'deborate and/or dilute as required.

.4 When the desired power level is reached, then perform the following:

.4.1 Verify the Turbine Load is blocked by CVOL or NRG (Section 6.6.5).

.4.2 Maintain Reactor Power constant by boration/ dilution. ,

i

.4.3 Follow Section 6.4, Guidelines for Steady State Power -

Operation. 8 y-C 6.6.5 Turbine Control Guidelines (Power Descension) l

NOTE: Turbine load The j is withrecommended the Narrow Rangemethod Governorof reducing (NRG) followe by lowering the Control Valve Open Limit (CVOL) accordingly. This arrangement protects against l inadvertent throttle opening. If the NRG l adjustment is too coarse, then the CVOL may be i used provided the NRG is also lowered accordingly.

CAUTION IftheNarrowRangeGovernor(NRG)andControl Valve Open Limit (CVOL) are not set in close proximity of each other (especially during Turbine load reduction), then the unlikely event of CVOL failure high could result in a primary planttransient.(Ref.2.4.2.16)

.1 H turbine load is reduced using the NRG, then the CVOL should be lowered accordingly.

.2 H turbine load is reduced using CVOL, then the NRG should i be lowered until the low value gate shows NRG in control, then raised slightly until NRG is no longer in control.

. ._ - - . =_ =_ - .

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 41 0F 100

, TCH bM 6.0 PROCEDURE (Continued)

. 6.7 Power Descension 6.7.1 Ensure Section 6.5, Preparations for Power Descension, has been completed.

i 6.7.2 Throughout the power decrease follow the guidelines of Section 6.6.

NOTE: 1. During an emergency situation, power may be decreased by either CEA insertion, boration or both. During normal maneuvering, power decrease should be accomplished by baration.

2. The rate for a normal power decreas'; is defined as 3-15 %/Hr. This is within the guidelines established in Attachment 5 Recommended Maximum Rates for Decreasing Load.

3. If this is an E0C Shutdown, then Attachment 21 may be used as an example for plant parameter expectations between 75% to 20% power decrease.

6.7.3 Obtain System Operating Supervisor and SRO Ops Supv approval to start trie load reduction.

6.7.4 Decrease power by boration per S023-3-2.2, Section for Borate Mode in accordance with the following:

If power descension will decrease power to < 75%,

then Attachment 15, Power Mane.uvering Boration/ Dilution Guidelines will establish the hourly flowrates and volumes and/or Attachment 18, Boration/ Dilution Schedule.

If power descension will decrease power to a 75%, then Attachment 19, Rapid and Accelerated Down)ower Boration/CEA Insertion Determination may )e used to calculate the volume of boric acid o_t Group 6 CEA position required to attain various target power levels 4

and/or Attachment 18, Boration/ Dilution Schedule.

.1 Concurrently decrease Turbine load as necessary to maintain Tc within the operating band of Attachment 8.

.2 Power decrease may require dilution per 5023-3-2.2, Section for Dilution Mode, to maintain desired rate of power decrease due to Xenon buildup.

NUCLEAR ORGANIZATION UNTTS 2 AND 3 OPERAT2NG INSTRUCTION S023-5-1.7 l REVISION 6 PAGE 42 0F 100 !

l '

TCN I# N !

i 6.0 PROCEDURE (Continued) '

\

6.7.5 50-75% Reactor Power

.1 Whtn power is <75%, jhan after verifying Main Condenser i backpressure is <3.5 Hg, position 2(3)HS-2808, Vacuum Trip Setpoint SeTect Switch, to 4.5 INCHES H6.

i j l .2 power is <75% ;

gCoo er Bypass Valve,pe.thAD Close the Generator r S023-6-18, attachment for Hydrogen :

Generatur Hydrogen Cooler Flow Configaration.

(Ref. 2.4.2.32)

.3 af_tfr Power is <70%, .then Reg. Group 5 CEAs !

may be used to assist in transient ASI control per Section 6.6.2, ASI Guidelines (Power Descension). i r

.4 At approximately 60% power, Open the Main Steam Drain Tank Startup Vents (two valves): [

S2(3)l30lMU528 T-098 Startup Vent i S2(3)1301MU546 T-101 Startup Vent g, j i .5 H power is being reduced to a plateau of less than 50%, I . :

.than ensure Closed S2(3)l305MU120, First Point Feedwater g Heater Bypass Valve. l N

.6 H power is being reduced to a plateau of less than 40%, '

.than adjust the CPC Azimuthal Tilt (Tq) Limit Constant (PID 063) to 1.05 per 5023-3-2.13.

.7 At approximately 60% power, Open the 13% MSR Live Steam Vents to Cold Reheat (four valves): (Ref. 2.4.2.4)

' S2f311301MU1044 MSR E-ll2 13% Live Steam Vent S2f 1130lMU1045 MSR E-112 13% Live Steam Vent- !

S2Ibl30lMU1048 MSR E-Il3 13% Live Steam Vent S2 dbl 301MU1051 MSR E-113 13% Live Steam Vent i NOTE: To minimize Feedwater Control System oscillations and prevent significant S/G 1evel transients, the following Step should be performed in a controlled manner and with one Feedwater Pump Mini-flow Valve at a time.

.8 WhSD Power is between 60% and 50%, .t.hta perform the foH owing with FV-3433 and FV-3432, Feedwater Pump Mini-flow Valves:

When a Feedwater Pump Mini-flow Valve receives an AUTO OPEN signal, then place the valve handswitch (one valve at a time) in OPEN l

Monitor the system response and adjust as necessary

.9 Whna power is at 53%, h1.an initiate 5023-5-1.4 up through and including the shift meeting while continuing with this procedure.

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NUCLEAR ORGANIZATf0N OPERATING INSTRUCTION S023-5-1.7 l UNITS 2 AND 3 REVISION 6 PAGE 43 0F 100 l

, TCN to-3(9 l 6.0 PROCEDURE (Continued) 6.7.6 45-50% Reactor Power i

.1 When less than 50% power, then initiate and concurrently perform 5023-9-6, Section for Feedwater Regulating System Operation - Unit Shutdown. '

NOTE: When removing a Condensate Pump or Heater Drain Pump from service, then Condensate Pump P-053 may auto-start unless selected to MANUAL.

.2 When less than 50% power, and at the SRO Ops. Supv.

discretion, then Main feedwater Pump, Condensate Pump and Heater Drain Pump combinations may be changed.

.3 When less than 50% power, then Circ. Water Temperature monitoring per Attachment 11 may be terminated, if previously initiated.

6.7.7 35-45% Reactor Power

.1 Transfer 6.9 kV busses A01 and A02 frem the Unit Auxiliary Transformers to the Reserve Auxiliary transformers per S023-6-1.

.2 Transfer 4 kV busses A03, A07, A08, and A09 from the Unit Auxiliary Transformers to the Reserve Auxiliary Transformers per 5023-6-2.

6.7.8 If this is an EOC shutdown, and it is desired to trip the Turbine and Reactor at 35% Reactor Power due to Hot Pin ASI considerations, then perform Section 6.10.

l l CONTINUED ON NEXT PAGE i

I 4

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NUCLEAR ORGANIZATION UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.7 REVI'SION 6 PAGE 44 0F 100 f TCN k'N l 6.0 PROCEDURE (Continued) i 6.7.9 25-35V Reactor Power ,

1

.1 Prior to reducing load below 330 MWe, shift the Blowdown Flash Tank Vent from the Third Point Heaters to the Condenser per S023-9-4, Section for Operation of the Blowdown Flash Tank Vent.

.2 i

Reduce the ramp" unloading rate to a maxiraum of 4 MWe/ min, for loads less than 330 MWe.

.3 Remove the Heater Drain Pumps from service per 5023-2-3.

.4 Place the Auxiliary Steam System and Air Ejector Steam Supply in the configuration designated by the SRO Ops.

Supv.

.5 H transfer of steam supplies is necessary, then perform the applicable steps of 5023-2-10, Section for Transfer of Auxiliary Steam Supplies. l

.6 H Power is being reduced to a plateau of less than 255, 4 then notify the Chemistry Department Foreman.

6.7.10 220 MWe Generator Load i

.1 M generator load is reduced to less than 220 MWe, mL4 the Turbine is not to be immediately shut down, then reduce ,

l reheat temperature to the L.P. Turbine by closing HV-2702, i Live Steam to Reheater Control Valve. Reheat temperatures !

are on indicated PMS Pt. ID. TE2079 througt TE2084.

{

6.7.11 H the plant is to be shutdown, then continue the plant shutdown per 5023-5-1.4 and S023-10-2.

6.8 Guidelines for Rapid Downnower Transients 6.8.1 Perform Attachment 19, Rapid And Accelerated Downpower Boration Volume Detennination, once a week to calculate j the volume of boric acid g Group 6 CEA position required j to attain various target power levels. '

6.8.2 Transfer the values calculated in Attachment 19 to the table in Attachment 20, Rapid And Accelerated Downpower Boration/CEA Insertion Guidelines, and post the attachment in the Unit Control Room E maintain in the "In-Use" procedures book.

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NUCLEAR OfiGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 5 PAGE 45 0F 100

, TCN V)- N J 6.0 PROCEDURE (Continued) i NOTES: 1. The rate for a rapid dow:, power is 1 to 5 %/ min. This rate )

is established to reduce power to prevent a Reactor Trip (e.g. Loss of MFW Pump or Cire. Water Pump) E in response to actions specified in an A0I (e.g SGTL) ;

2. CEA insertion and turbine load reduction are expected to be the major factors in attaining the target power level.

6.8.3 H plant conditions warrant the need to rapidly. decrease ow p(e.er due toLOCA,

g. SGTL, a Technical Specification large power reduction) action g to requirement prevent a Reactor Trip (e.g. loss of a MFWP or Circulating Water Pump), then initiate a rapid downpower using Attachment 20, Rapid or Accelerated Downpower Boration/CEA Insertion Guidelines, to determine the amount of Boration and CEAs to be used to achieve the target power level.

.1 Jf greater than 50% power decrease is required, itten strong consideration should be given to tripping the Reactor and Turbine-Generator.

.2 H time permits, then to enhance system response to the plant transient, commence forcing Pressurizer Nonnal Spray flow as directed by the SRO Ops. Supv.

NOTES: 1. A 30's power drop by both CEA insertion and l boration would, for example, insert CEAs to the 10% power level decrease position and borate the 20% power level decrease volume.

2. A faster power decrease may be obtained by emergency boration via HV-9247, but this requires careful monitoring of time and charging flow to determine volume of boration. !

.3 Determine whether the rapid downpower is to be performed by boration only, CEA insertion only, or a combination of the two methods. ;

.4 Initiate direct boration and/or CEA insertion per the guidelines of Attachment 20. Stop CEA insertion any time '

the PPDIL alarm is received.

.5 Review the additional guidelines provided by Attachment 20.

.6 Take all necessary actions to compensate for Xenon build-in after stabilizing the unit at the target power level.

I 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 46 0F 100

, TCN LO S 6.0 PROCEDURE (Continued) 6.9 Guidelines for Accelerated DownDower Transients NOTE: 1. The rate for an accelerated downpower is 15 to 60 %/Hr. This rate is established to shutdown in response to Tech. Spec. f Action Statement or a Tech. Spec. required )

power reduction (e.g. dropped CEA)

2. CEA insertion and turbine load reduction are expected to be the major factors in attaining the target p6wer level.

3. "Boration Only" is the preferred method for a dropped CEA event. A combination of the two methods is preferred for other events.

6.9.1 M plant conditions warrant the need to decrease power at an accelerated rate (15 to 60 %/Hr) due to Technical Specification action requirement (e.g. Reactor shutdown required, dropped CEA), then initiate an accelerated downpower using Attachment 20, Rapid or Accelerated Downpower Boration/CEA Insertion Guidelines, to determine the amount of Boration and CEAs to be used to achieve the target power level.

.1 Determine whether the accelerated downpower is'to be performed by boration only, CEA insertion only, or a combination of the two methods.

.2 Initiate direct boratf or, and/or CEA insertion per the guidelines of Attachment 20. Stop CEA insertion any time the PPDIL alarm is received.

.3 Take all necessary actions to compensate for Xenon build-in after stabilizing the unit at the target power level.

6.10 E0C Shutdown - Turbine and Reactor Trio from 35% Reactor Power NOTE: This section is to be used during an E0C shutdown when Hot Pin ASI concerns require a Turbine and Reactor trip from 35% Reactor Power.

l 6.10.1 H time permits, then perform the following actions prior to tripping the Turbine and Reactor:

.1 Shift the Blowdown Flash Tank Vent from the Third Point Heaters to the Condenser per S023-9-4, Section for Operation of the Blowdown Flash. Tank Vent.

1 l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 ,

UNITS 2 AND 3 REVISION 6 PAGE 47 0F 100 l l , TCN (0*

6.0 PROCEDURE (Continued) 6.10.'s.2 Remove the Heater Drain Pumps from service per S023-2-3. l

.3 Place the Auxiliary Steain System and Air Ejector Steam Supply in the configuration designated by the SR0 Ops.

Supv.

.3.1 J_f transfer of steam supplies is necessary, then perform the applicable steps of S023-2-10, Section for Transfer of Auxiliary Steam Supplies. ,

1

.4 To enhance system response to the plant transient, i commence forcing Pressurizer Normal Spray flow as directed i by the SRO Ops. Supv. '

i 6.10.2 Ensure the ESF component transfers initiated in l Section 6.5 have been completed. l l

1 NOTE: Unnecessary steam loads s'hould be isolated prior !

to taking the Reactor subcritical.

6.10.3 Since a mode change may affect chemistry sampling !

frequencies, limits and parameters, notify the Chemistry !

Department Foreman that the Unit is about to enter Mode 3. )

6.10.4 Remove the Turbine Generator from service, as follows:

NOTE: Before tripping the turbine, having the SBCS modulating with a Manual-Local setpoint at the present steam Generator pressure will ensure smoother transfer to SBCS and reduce secondary plant transients.

pgT.J,0J TopreventSBCSValveoscillations,2(3)PIC-8431 SBCS Master Controller, should be placed in MANUAL prior to changing the Remote / Local setpoint selector switch.

.1 Prior to tripping the Turbine Generator, Ensure the SBCS Functions to maintain steam flow constant as follows

Two SBCS Valves have pemissives in Manual (normally HV-8423 and HV-8425)

The Master Controller 2(3)PIC-8431 is in Local with its j setpoint 2 psig to 3 psig below existing Steam ,

Generator pressure. !

l l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 48 0F 100

/ -

6.0 PROCEDURE (Continued) 6.10.4.2 Depress the TURBINE EMERGENCY STOP pushbutton.

.3 Initiate S023-10-2, Section for Actions on a Turbine Trip while continuing with this section.

6.10.5 Place Feedwater Pump Mini-flow Valves, FV-3433 and FV-3432, in NORMAL for proper response to an RTO due to a Reactor Trip, DE Leave the Feedwater Pump Mini-flow Valves, FV-3433 and FV-3432, OPEN if a dedicated Operator is stationed at the Feedwater controls ready to compensate for the higher Feedwater Pump discharge pressure resulting from a RTO due to RX Trip.

6.10.6 Ensure the Steam Bypass Control System is operating in automatic and maintaining 1000 psia.

.1 l If the Condenser is not available or if the MSIVs are 1 closed, thAD use the Main Steam Atmospheric Dump valves. l 6.10.7 When the Secondary plant has stabilized following the Turbine trip, ihan manually trip the Reactor from between 35% to 15% power and initiate S023-12-1, Standard Post 3 1

Trip Actions.

.1 Continue Plant shutdown per S023-5-1.4.

7.0 RECORDS 7.1 Transmit completed Attachment 11 to the NPDES Engineer.

7.2 File Attachment 13 as follows:

7.2.1 if associated with a startup or shutdown, ihan file per i S0123-0-32. !

7.2.2 If associated with Steady State load, lhen transmit to Equipment Control for filing.

7.3 File Attachments 15, 18, 19 and 20 per S0123-0-32.

J7-6.wS1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 49 0F 100 ATT3CHMENT1 TCH b'b MAXIMUM CORE POWER ESCALATION RATE (References 2.4.2.2 and 2.4.2.29 and 2.4.2.35)

Fuel Condition Applicable Power Note Maximum Core Power Category Range Escalation Rate First power escalation 20% to 100% [1] 3% per hour after refueling.

Increase in Reactor Power to a level which has not been previously sustained Above 50% 3% per hour for more than 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months within the last 60 days.

When fuel cladding leaks 20% to 100% [2] 5% per hour are known to exist.

All Other Times 0 - 100% [3] 20% per hour i

[1] Deviation from this ramp rate may be directed by Reactor Engineering per 5023-V-2. '

[2] Refer to the Operations Physics Summary for current status of fuel failure l

l per Reactor Engineering Transmittal.

[3] 10%/hr is the normal recommended power increase ramp rate.

l l l t

3 J7-6.wS1 ATTACHMENT 1 PAGE 1 0F 1 l

l

. NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 50 0F 100 ATTACHMENT 2 TCN k36 TURB1NE RUN-UP AND LOADING RATES WITH REHEAT TEMPERATURF CONTROL j u tol STAnT WAtw START catD STAAT

, , uss . . . . . . . . .

1100 100

SI@jjh5 " h' "8 h h I '[ h h k ite wwth or 1*

% .TMQTM

./ g / :f: )

M 9sc 93 .l.. .;. . .;. . ; j. ; _yk ,,...g., , /_. . . . .. . . . ,

TO BE t.! SED :FOR. /: .

- / ' ,,; ; y' , . . . ,p;/

880 83 DEGM M - 5 Lccsrc h -- - ' -c- s -W f. --y--' i - 9h; . :

s

',f*-

- i - - b' l ' / . -

. /-

770 70 -

-f. l-- .-- -:-- - - 3.< .#-L- 4.'-d*4' ; . ;,h', i-

.[ I - -g - -

t-y aso sa ,

. . f,e. .

):

, . . . }. . ;. . . - . g..l. .. :

,4l- *... :l.

s y .

..-...g O

8 550 53 -

- - .I N-. 4 /- - -- .. - - -

-h - dI L-440 40 - #-- - #-$ A :, - " $/[ $ -

-E f -, ,k. . ' -

'. ' s .

N-j i .

3 30 36 -/: - - - -

3/- - *- ' - - - - . d -- "^M - - na s a 's i! J ?*i,/p?- ' . h: *# '

.mst[y'js./k. -. .1y2wu" - b g - "'. T> sy. jh- s . -- -

220 20 '

-; >-r,- . -- - .... . -

va

.; (

.q."Iyr,s, . {M " - * \ ,-

- q. -

,0 e' pr.< , v ,

D 0 0 l ::: .

w -

l .

j'./ . / . l l

) [ "') ' ' '

'CWamE' ts tmfub.cnM'sidks viO.Ts Ta'TunhTTth tstGS" o f.l y . ;y:. ,, ; .#. A /

f. y. A . . / -

..,C.., . .: . . ,

++N:nc rtname: speEo es as.csso 4eo0:am; r4 canax is r0 as 1800 # . . f . 9. . . . : -.' . . . -Lt. . .:. ; . ., , , . . jY fM Fp Ty S' Tap %Lp p -TNTiu- hatvjs-a[s F0'ttows- 1-

2 a 1200 -/--- -

f. . . - STOR .WAtyE. - - - quNT.OL.- 4. ..:

.g . .gg.4.j . g- .,.g- gy 4.g 9 j ,

i gh y 600 -- 1- , - *

--itsd64 MUPS[ - L - - - j 5"ERkTE. 5LI AS TRAf6FIy .4T E4h JtAIL fo iSTAldJ 5H( 83. f.Da[FFE9ENT tAL .

2 en ./ - TO %'O 'R . P 'M @ : CDMPLETE BIAS ManSFER:USIPC.s SLCw PATE:Dre.y 0

0 20 40 50 80 im 120 140 160 183 200 2?o P40 260 200 E 320 No 360 TIME - MINUTES REHEAT STEAM TEMPERATURE-CONTROL - For all starts live steam should not be admitted to the live steam tube bundles prior to reaching 220 MWe gross.

LOADING RATES - For each type of start, hot, warm and cold, the limits provided can be for all H.P. and/or L.P.

temperatures.

J7-6.wS1 ATTACHMENT 2 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6' PAGE 51.0F 100 ATTACHMENT 3

/

TCN M,-gN RECOMMENDED MAXIMUM RATES EOR INCREASIhG LOAD ON A HEATS 0AKED MACHINE

" LOADING RATE AFTER D g .

LDDifl3N OF BLOCK LOA 9 LOA 0ld'J RATE AFTER ADDITION OF 4 MW/ MIN l SLOCK LOAD .11 MW/ MIN fD g 660- 60-N- . -}- -i- -- 100 y . 1. .

,ff.. , . . . . - . . - -- 90 T

440 40--. . jh { f. , * . .

o f. . y .h * -- 40

, + dN4Nac .. .

-- . +

ik{-i .{,.j. ._- , ,

DE APPLIED TO A TlWE sa0 so--. L'q -

4MMy0^M-u - - -

-- 80 g .

. . .i. 4 .g .: ..i..j..f. d. i .j. , d. s

-- 60 goog I N - '

LOAD 220 20-.- - i . i- .\ i ;. .;. , , ..;.. .>. .;. .i. 4 .-e .;. .--- 40 j

if-

'js, -

l

n- : ;;;,;,yim;;;ig -

\[ LOAD ;TO 100%; LOAD !

1 3,o .

iO --. .; ,

i

.g< . < < < > -- to

. . . 09.. , , , . -- i0 l

0 0 0

!!!!i!!!

10 20 30 40

'Ii!!!!il !!

60 to 70 80 90 1005 o

j 0 ti0 sa0 3:0 440 660 se0 no se0 se0 1100 M w MACHINE LOAD

1. The above rates are the recommended maximum loading rates for a fully heat soaked Turbine operating with the full reheat temperature.

2. These rates should not be used for frequent daily use but should be used as the limiting rate during the occasions when system demands rapid and large load increases.

l

3. If load changes are carried out on frequent basis, then the loading rates provided for a Turbine not fully heat soaked (Attachment 4) should be used as the limiting rates.

4. Following a Turbine startup, the loading rates and times provided by the appropriate startup curve must be followed in preference to the above rates.

5. The minimum time to heat soak the HP Turbine after a large load change is two(2) hours.

EXAMPLE If the Turbine-Generator is Operating at 10% load and heat soaked (110 MWe), then themaximumblockloadthatcanbeappliedis15%(165MWe). Loading can then continue at 4 MW/ min up to 304 load (330 MWe), and then at 11 MW/ min up to full load. The total time to achieve full load would be 64 minutes.

J7-6.wS1 ATTACHMENT 3 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 52 0F 100 j TCN ATT/)CHMENT4 RECOMMENDED MAXIMUM RATES FOR INCREASING LOAD ON A MACHINE NOT HEATS 0AKED AVERAGE LOADlhG MIN TIME RATE (0-30% LOAC) AVERAGE LOADING RATE (30-100%) = '1 MW/ MIN TO LOAD

= 4 MW/ MIN FROM 150 -- - - - - - - - - 0%

14 0 --' > < - < ~ ~ < . . ~ -

13 0 ' ' ' ' ' ' ' --

10 %

12 0 - - - - * - 'L- '- -

T l

tio - + -j o- ?- 5- .. >- ?-

100 -- ' ' ' '

i- ' *-

i- --,20%

90 -' '- - - - -

80 -'

M 70 -- - - . - - - - . '

30%

1 N 60 -- ~ ~ ' - *

' - - - < '40%

, 50 -- ' ' ' - - 60% ,

E 40 -. .: . . . .

iy60%

30 -- + , + + i. .i- , ,70%

20 -- - - - - - -

i- 80% l 10 -- , ,- , . , , , . 007.

' ' ' ' - L- ' ' '

0 : -- J--- ' ' '

20 O 10 30 40 50 60 70 80 90 10 0 %

0 11 0 220 330 440 650 660 770 880 990 1100 MW MACHINE LOAD

1. The above rates are the recommended maximum loading rates for the Turbine o)erating with full reheated steam temperature but not fully heatsoaked at t1e prevailing load.

2. The time to heat soak the HP Cylinder after reaching a steady load is dependent on the magnitude of the load change, but usually can be estimated at approximately two (2) hours.

3. Following a Turbine startup, the loading rates and times given in the appropriate startup curve should be followed in preference to the above rates.

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J7-6.wS1 ATTACHMENT 4 PAGE 1 0F 1 i

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 53 0F 100 ATTACHMENT 5 TCN x(n' -

RECOMMENDED MAXIMUM RATES FOR DECREASING LOAD MW UNLOADING RATE

, - AFTER REMOWL OF UNLOADING RATE AFTER REMOWL OF BLOCK LOAD

4 MW/ MIN BLOCK LOAD = 11 MW/ MIN CA KO i 1

800- So .b.-+.

-~ -. - - - - . . ~ . .

.f -

. . . ;. . . . ;. . . .;. . 4 .;. .;. .;. . ; . . . . .g. .g . . . .g . .;. . . .;. .;. .;. )

THAT:CAN' BE REMOVE D '

I 440- 40 .. .j. .j. .j. { &EEj NOTER .' . j. . .J.

l

. . . . . .. . . , , . . s.

330- 00 ~~~l * ' ***E ' ' ' * * ' '

i ; ; i i ; ; ;

, i i i i i i

.i. .i . .i . .j. 3 . j. . . j. .i. .i. l 220-- to - ' ' ' ' * * '

~ yy-Qgge y( y y-

M ACHINE 18 TO CONTENUE:

, . . '. OPERATING AT.THE.NE W .',

' LOWER LOAD ;

,,o . 3o . . c. . . . . . . . ..

,' , , .i.

l . 4. . .

i 0- o 3 I I I I I I I I. I I I i 3.- - I I .I.. . . I. I o 10 2o 30 40 So 60 70 Bo 90 10 0 %

0 110 220 330 4$0 660 000 770 800 000 110'O M W MACHINE LOAD 1

1 l

1. The above rates are the recommended maximum unloading rates when the !

l Turbine-Generator is to continue operation at a new lower load.

2. The above recommended maximum block loads can only be removed if the i prevailing high load on the Turbine-Generator has not been exceeded within '

l the previous 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period.

l 3. These maximuri rates are not to be taken as permissible for frequent daily l use but should be regarded as limiting during the occasions when the system l demands rapid large load reductions.

4. If load changing is carried out on a frequent basis, then the recommended l maximum block load is to be reduced as far as possible, a_nd the given l steady unloading rates used as the maximum rates.

! 5. In cases of emergency, such as load reduction followed by operation at low I load, the above rates may be exceeded.

6. In the case of emergency ;hutdown, the above rates may be exceeded, but the Turbine is to be tripped upon reaching low load.

J7-6.wS1 ATTACHMENT 5 PAGE 1 0F 1 l

i I

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 ,

UNITS 2 AND 3 '7[j REVISION 6 PAGE 54 0F 100 ATT3CHMENT6 TCH /1 RECOMMENDED POWER PLATEAUS 1.0 The following list of examples are to be used as an aid in detennining the desired reduced Power Level Plateau. Power / load conversions are based upon Attachment 7. (Ref. 2.4.2.3 and 2.4.2.13) 1.1 Existing or predicted plant conditions may warrant further adjustment of these values.

2.0 Fauioment Out of Service -

Reactor Approximate Power Load (cross) 2.1 Circulating Water System 2.1.1 One Circulating Water Pump Off 75% [2] 860 MWe 2.1.2 Two Circulating Water Pumps Off 65% [4] 740 MWe 2.1.3 Heat Treatment of the Circulating 80-85% 920 MWe to Water System 980 MWe 2.1.4 Circulating Water System Tunnel Swaps 80-85% 920 MWe to 980 MWe 2.1.5 Operation With Reversed Tunnels and 90% [1] 1060 MWe Flow Restrictions Installed 2.2 Condensate /Feedwater System 2.2.1 One Condensate Pump Off and Two Heater 75% 60 MWe Drain Pumps Off ;

2.2.2 Two Condensate Pumps Off and Two Heater 50% 540 MWe Drain Pumps Off 2.2.3 One Main Feedwater Pump Off 754-80% [3] 860 MWe to 920 MWe 2.2.4 One Feedwater Heater Train Out of Service 90% 1060 MWe i

2.2.5 One First Point Feedwater Heater 95%-98% 1085 MWe to Out of Service 1115 MWe

[1] Maintain power level within Condenser Circ. Water AT limitations.

1 l

[2] This limit is necessary to prevent Condenser tube failures caused by high j velocity steam in the midspan regions of the neighboring quadrant tube bundle. (Ref.2.4.2.15) '

[3] See Section 2.6 to determine specific guidance and monitoring requirements.

[4] The Security Shift Commander shall be notified when entering a condition of 2 or less Circulating Water Pumps running.

ATTACHMENT 6 PAGE 10F 3

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 j UNITS 2 AND 3 REVISION 6 PAGE 55 0F 100 ATT3CHMENT6 TCN Q'76_

7(

2.0 EauiDment Out of Service (Continued) Reactor Approximate :

Power Load (aross) 2.3 Turbine / Generator 2.3.1 One Turbine Stop/ Throttle valve Closed 95% 1120 MWe 2.3.2 One Generator Hydrogen Cooler 75% 860 MWe l Out of Service a

2.3.3 One Stator Cooling Water Heat Exchanger 50% 540 MWe Out of Service 2.3.4 One MSR Relief Valve Out of Service 92% 1070 MWe 2.4 COLSS/CEAC 2.4.1 Core 00erating Limit Supervisory System 92% 1070 MWe j and COLSS Backup Computer Out of Service (Ref. 2.4.2.7) 2.4.2 Both CEACs Out of Service with COLSS or [5]

COLSS Backup Compster in Service.

2.4.3 Both CEACs Out of Service with COLSS and [5]

COLSS Backup Computer out of Service.

2.5 Main Steam Safety Valves (MSSVs) i (Per Operable Steam Generator) '

2.5.1 One MSSV out of service. 90% [6] 1060 MWe (8MSSVsOperable) 2.5.2 Two MSSVs out of service. 77% [6] 910 MWe (7 MSSVs Operable) 2.5.3 Three MSSVs out of service. 65% [6] 740 MWe (6 MSSVs Operable) 2.5.4 Four MSSVs out of service. 53% [6] 625 MWe (5MSSVsOperable) [7]

l

~5' Determine Reactor Power level per 5023-3-2.13.

l6 Allowable power levels are a9 proximately 9% below the linear power level-high trip setpoints of Technical Specification 3.7.1.1 Table 3.7-2.

(Ref. 2.4.2.27)

[7] With less than 5 MSSVs Opei able, then apply Tech. Spec. 3.7.1.1, Action b.

ATTACHMENT 6 PAGE 2 0F 3

I l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 56 0F 100 ATTAjCHMENT 6 TCN@h 2.0 f.automent Out of Service (Continued) l l

2.6 Guidelines for Single Main Feedwater Pump Operation (Ref. 2.4.2.31) l 2. t, ,1 75% Power Limitation

.1 Assumes the following MFW Pump support conditions:

4 Condensate Pumps in operation

2 Heater Drain Pumps in operation

.2 Exceptions to above support conditions are allowed when approved by Operations Management and Station Technical.

.3 Actual power level may vary depending on plant conditions e.g., Feedwater Heater 0.0.S for tube repair, Heater Drain )

Pump 0.0.S., or Condensate Pump 0.0.S. (Ref. 2.4.2.24) '

2.6.2 80% Power Limitation l

.1 Assumes the following MFW Pump support conditions: 1

4 Condensate Pumps in operation

2 Heater Drain Pumps in operation

.2 Obtain approval from Operations Management and Station l Tecnnical.

.3 Periodically monitor the following parameters. Report any rising trends to Station Technical.

VIBRATION BEARING LUBE DIL TEMPERATURE L-183 K-005 K-006 TJR-8299 K-005 K-006 PUMP 08 NIT 4533A NIT 4532A TURBINE IB TE 4507 TE 4509 PUMP IB NIT 4533B NIT 45328 TURBINE OB TE 4506 TE 4508 l PUMP THRUST NIT 4533C NIT 4532C ACT THRUST TE 4555 TE 4554 TURBINE IB NIT 4533D' NIT 4532D INACT THRUST TE 4557 TE 4556 TURBINE OB NIT 4533E NIT 4532E THRUST DRAIN TE 4558 TE 4559 TURB THRUST NIT 4533F NIT 4532F PUMP IB TE 4520 TE 4514 TURBINE CASING DRAIN LEVEL PUMP OB TE 4517 TE 4510 Monitor Casing Drains; level is THRUST TE 4550 TE 4546 expected to rise due to increased steam flow. j THRUST TE 4551 TE 4547 l .4 If a Condensate Pump or Heater Drain Pump trips, or a MFW Pump Miniflow Valve fails, then monitor S/G levels.

If level is lowering, then ramp power down until levels stabilize.

i J7-6.wS1 ATTACHMENT 6 PAGE 3 0F 3 l

i NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 57 0F 100 f,

ATT3CHMENT7 TCN (fd, V,'

s REACTOR POWER vs. MEGAWATTS 3500 -' -

-1400 h 3000 --

LICENSE @OWER LIMIT 1200 lN A 3390 MWfh E h 2500 -

+ !- . i- -

1000

. NWth CURVE ,

T 2000 -- '

800 0 P . R O

W 1500 -- ' -

600 L E

uwe CURVE O l 1000 -- -

L '

A )

400

- ~-- -

M D w

t 500 -. , ~;- M l 200 h -

\

W e

0 O O 10 20 30 40 50 60 70 80 90 100 REACTOR POWER (%)

CONVERSIONS VARY WITH HEAT RATE.

l J7-6.wSI ATTACHMENT 7 , PAGE 1 0F 1

NUCLEAR OR3AH2ATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND a REVISION 6 PAGE 58 0F 100 I

ATT3CHMENT 8 TCN @ '

Tcold vs. REACTOR POWER NOTE: When Reactor Engineering is performing physics testing (e.g., ITC), then the associated procedures may direct that Tcold be raised above 555af.

This is acceptable, provided the AVERAGE Tcold value is 5558aF with the HOTTEST Tcold 5560aF. (Ref.2.4.2.33)

/

660

_. .j. s s .i. .j. .j. .j.

T E. C H' S P E C : 3.2 8 U P P.E R Tc aid L I M I T

.j. .i. .j. . l. .i . .j. .i. .j. .j. <

666 -- , , .

. ~ , , , . . . ,

.u- 555

. . , efffT.~J.

_. . . . . , , , . . .. .e... ,

5ga

. , . . ~ ,

. j, -r'.s .

\

l

- ..: rr'.T . . . .

...3- 651 660 - '

i i I : -'ir'

- . . , , . g. s. p er !.

i. ,

. g . . A,

+ U e-Tf' " D ';.P , ",b'I' T -et-!.; j.

_. , .,. 5. : .

. . . . . . . . d . . ,. ;. g ' , .

N -

sr . '. , . .

.}. , .i.' . i . . .p . . j . . j,r". .-

.}.

c .}. .}. .i. .{.

,.-. . ' ~.~ ~ . . . ..

O

- 9. ~A u : .~ . !

o P ,,Ep ,7er.+, .'

,646< '

+ + . . s + , ,

+ ,

..,.........z. .,. .

d < ,.s.

a-7T,,.;... ,: Ta v.o. . .L l MI T S .

I

= _. s . . . C R ! T ! ,C A t. O.P,E,R, A,T I ,0,N . , , ;

F

~'"

BELOW 535 '

F REQUIRES

? EO'G'G I N G' T E'M P E RNTU R E * 'h " ' 'h I '

640 - -- -

!EVERY H ALFiHOURi F-

< ~ -

. . . . .. M ! N I M U M. .T E M P E R AT,U. R E , .. .

~' ' FDR lCRl!TIO;AL .'OP $iR ATIOlN l$ -

, .;. ,j..;. ,

'52'Of T(T EC; H"S P E'C"3:1 1:4 T: ' ' ' '

I l'

636 . . .

.p. , ............... ..........,................,....,............. ,

_ . . . . . . . .. . . T EC H.: SP.E C ;3.2 6 t; OWE R :Too.ld Li M I.T t' .'

ttt

' l 630 ' ' '

O 10 20 30 40 SO 60 70 80 90 10 0 REACTOR POWER (%)

i J7-6.wS1 ATTACHMENT.8 PAGE 1 0F 1

I NUCLEAR ORGANIZATION S023-S-1.7 OPERATING INSTRUCTION l UNITS 2 AND 3 REVISION 6 PAGE 59 0F 100 ATT3CHMENT9 TCN h'%/, V Thot. Tava AND Tcold PROGRAM I

i 620 610 -- - . . - . . .:- - . .-

608

.i. . , , . .

600 :- - - - - - ..- -..

R !

l c _ . . . . . . . . . . . . . . . . ._

S ' '

T 690 --

i- i- i i- ' '

i- - - otj 4 .; ,;. , ,_

E .

M -, . . . . - , , . . . -

.l . . - -

P . .

E 580 ~ i- '

i- i- ' : -

i- i- i i i- 580 R I ; ; ; ; ; ; ; i ; ; ; ; ; ; ; ; ;

A 'g. . . ,

T U 570

. :T avg.

R ,

E ..

F j 560 -- - - - - . - ~. . . - -

.....T cold.. _.

553 550 ! i-

-' l j- '

.s - '-

I I l i i l l I 540 4 I i l i I I

i i i I

I I

i f

6 l

iiiI I l l l i

l i

l I

O 10 20 30 40 50 60 70 80 90 100 REACTOR POWER (%)

l l J7-6.wS1 ATTACHMENT 9 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 60 0F 100 ATT3CHMENT10 TCNh.'.,

GUIDELINES FOR LOSS OF COLSS AND COLS5 BACKUP COMPUTER I

1.0 Power Reduction Guidelines 1.1 Initiate 5023-3-3.6, COLSS Out of Service Surveillance.

1.2 Power Operation with DNBR/LHR outside of acceptable limits may continue for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following both COLSS and COLSS Backup Computer being declared Inoperable, providing DNBR/LPD Margins are monitored and recorded every 15 minutes and no Adverse Trend is detected. (Adverse Trend is defined in S023-3-3.6.)

1.2.1 Documentation of required 15 minute monitoring and 4

recording of DNBR/LPD Margins is accomplished by performing 5023-3-3.6, Attachment for DNBR Margin / Linear

Heat Rate Limit Monitoring.

1.3 If it is detemined that either COLSS or COLSS Backup Computer may 1

' not be returned to service within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of Inoperability, then determine the magnitude of the Power reduction required to achieve an acceptable DNBR/LPD Margin.

4 1.3.1 Required power reduction shall be completed to ensure ;

4 DNBR/LPD Margins are within Tech. Spec. acceptable limits prior to this 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months time limit.

(Tech. Specs. 3.2.1,&3.2.4) 4 1.3.2 Use the thumb rule that a 3% Power reduction will result !

in an increase in DNBR of 0.1. '

1.4 During the Load reduction, control ASI per Section 6.6.2.

(Reg. Group 5 is not pemitted for ASI control under this condition.)

1.4.1 Monitor Average ASI (PID-268). using the average of the operable CPC channels.

1.5 J_f acceptable DNBR/LPD Margins are not achieved within the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months time limit of COLSS and COLSS Backup Computer Inoperability, then reduce Thermal Power to less than or equal to 20% of Rated Thermal Power within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l 1.6 While operating at reduced Steady State load, maintain ASI at the ESI I 0.01 Shape Index Units per the Section 6.4, Gufdelines for Steady State Power Operation.

1.6.1 Establish an hourly plot of ASI using Attachment 13, to be used for predicting when Xenon oscillation dampening will be required.

ATTACHMEliT 10 PAGE 1 0F 2 l

l l

NUCLEAR ORGANfZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 61 0F 100 ATTpCHMENT10 TCN[B' -

1.0 PowerReductionGuidelines(Continued) 1.7 When operating at a reduced power to maintain DNBR Margin, then monitor DNBR Margin during ASI changes to ensure that it remains in the acceptable region of operation as required by Tech. Spec. Figure 3.2-1 or 3.2-2, as applicable.

1.7.1 If DNBR Margin approaches the region of ur. acceptable operation of Tech. Spec. Figure 3.2-1 or 3.2-2, then reduce Power an' additional 5% or until an acceptable DNBR Operating Margin is reached.

2.0 Technical Specification Actions 2.1 Ensure within Term Steady 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months State Insertion all Regulating Limit. (Group Tech. Spec. CEAs are above their Short Fig.3.1-2) 2.2 Ensure CEA Reg. Group 5 is fully withdrawn per 5023-3-3.5, Attachment for CEA Position vs. EFPD (Tech. Spec.3.1.3.6) 2.3 With one or both CEACs out of service, refer to 5023-3-2.13, Section i for CFAC Inop. I J7-6.wS1 ATTACHMENT 10 PAGE 2 0F 2

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 62 0F 100 ATT$CHMENT11 TCH ( M D'g CIRCULATING WATER INTAKE / DISCHARGE DELTA T 1.0 PREREQUISITES 1.1 The Unit is at a Steady State Power Level of greater than 50%, and any one of the following occurs:

1.1.1 The Circ. Water Temperature Data Logger 2(3)L-168 is out of service. -

1.1.2 Window 2(3)64A14, CIRC. WTR. TEMP. MONITOR SYSTEM TROUBLE, is in the alarm condition. This alarm is inoperable when the Data Logger is measuring a negative delta T due to reverse Circulating Water conduit flow.

1.1.3 Circulating Water Conduit reverse flow for a period greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

1.2 Heat Treatment of the Circulating Water system is NOT in progress.

2.0- PRECAUTION 2.1 The daily (24-hour period, midnight to midnight) average differential temperature exceed of the(Ref.

20.4af AT. Circulating) 2.1.2 Water Discharge and Intake shall not 2.1.1 The Daily Average AT limit ensures the NPDES AT limit of 20af will not be exceeded. Insignificant figures are rounded in accordance with the NPDES Permit and Standard Methods (i.e., values up to 20.499aF are rounded down to 20af by Environmental for the monthly NPDES report).

2.1.2 TheInstantaneousATlimitis21af(oneminuteaverage).

NOTES: 1. Starting or stopping a Saltwater Cooling Pump in the opposite Unit Intake can affect Circ. Water AT. If the opposite Unit injection temperature is lower, then AT may lower. Conversely, a higher injection temperature may raise AT.

2. Prolonged operation with Fish Return Sluicing Water in service can raise Circ. Water AT on the affected Unit.

2.2 If Daily Average Circ. Water AT is close to the limit of 20.4 of, then starting and stopping SWC Pumps in the opposite Unit Intake, or operating with flow through the Fish Return Sluicing line, must be evaluated for possible affect on AT.

ATTACHMENT 11 PAGE 1 0F 5

_ .- - . . =-. . _ . . - . . -- .-

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 63 0F 100 l l ATT/)CHMENT11 TCN 3W IA'qlf i

3.0 PROCEDURE l

3.1 When logging is required per Section 1.0, then monitor and record Circulating Water Intake and Discharge AT every two hours.

l 3.2 Determine Circulating Water Intake and Discharge differential 1

temperature for the daily log sheet, as follows:

NOTE: The NPDES Engineer should be notified if the Circ. Water Temperature Data Logger, L-168, is not available.

3.2.1 If the Circulating Water Conduits are in normal flow, then the following methods should be used in descending order of preference:

.1 Circ. Water Temperature Data Logger, L-168

.2 PMS PIDs:

TE-5228C, " Intake Sea Water Temperature" TE-5296C, " Discharge Sea Water Temperature" OE average the following intake and discharge:

TE-5129, " Main Condenser NE(SE) Inlet"

TE-5125, " Main Condenser NW(SW) Inlet" TE-5179, " Main Condenser SW(NW) Inlet"

-TE-5180, " Main Condenser SE(NE) Inlet" TE-5119A, " Main Condenser NE(SE) Outlet" TE-5120A, " Main Condenser SW(NW) Outlet" TE-5170A,"MainCondenserNW(SW) Outlet" TE-5194A, " Main Condenser SE(NE) Outlet"

.3 Average of available points from recorder TJR-5159 (CR-59)

.4 Circ. Water Temperature Recorder, TR-5296 (L-111, Heat Treat Panel)

.5 Request I&C to monitor Temperatures at the Intake and l Outfall Stop Gates using a calibrated portable temperature l monitoring instrument.

l l

ATTACHMEN.T 11 PAGE 2 0F 5 i

[

i

)

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 64 0F 100 l

ATT3CHMENT11 TCNIV_ f 3.0 PROCEDURE (Continued) i I

3.2.2 H the Circulating Water Conduits are in reverse flow, 2 then only the following methods should be used in descending order of preference:

.1 Circ. Water Temperature Data Logger, L-168

.2 PMS PIDs:

TE-5228C, " Intake Sea Water Temperature" TE-5296C, " Discharge Sea Water Temperature"

.3 Circ. Water Temperature Recorder, TR-5296

.4 Request I&C to monitor Temperatures at the Intake and Outfall Stop Gates using a calibrated portable temperature monitoring instrument.

NOTE: The NPDES requirement of maintaining a temperature difference of less than 20*F is waived during Heat Treatment. Hours of heat treatment should not be used to perform the following calculations.

3.3 Record Circ. Water AT every two hours on the daily log sheet.

(Mark N/A log readings for the hours a heat treatment is in progress.) ;

3.3.1 H the requirement to log Circ. Water AT has just i commenced, then obtain and record )revious AT readings for the current day and mark N/A for t1e previous calculations.

3.3.2 H Cire. Water Temperature Data Logger, L-168 is out-of-service, then from the PMS, generate a two hour average trend at five minute intervals (using preferred PMSPIDs)andrecordthisvalueonthedailylogsheet.

3.4 After Circ. Water AT has been recorded, then perform the following:

3.4.1 Calculate and record a new daily average using the following formula:

Daily Avg. = Sum of Actual Circ. Water AT 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months readings Total Number of Circ. Water AT 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months readings l .1 H the 2300 calculated Daily Average exceeds 20.4cF AT, l then immediately notify the Unit Superintendent and the l NPDES Engineer.

ATTACHMENT 11 PAGE 3 0F 5

NUCLEAR ORGAN!ZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 65 0F 100 ATTACHMENT 11 TCH (d'7[,

R 3.0 PROCEDURE (Continued) 3.4.2 Calculate and record a new allowable Circ. Water AT using the following formula: [1]

i l

\'

489.6 - [ Daily Average x (24 - Number Hours Remaining in Day)]

Number of Hours Remaining in Day I

.1 M actual Circ. Water AT is greater than Allowable AT, then notify the Shift Superintendent a03d reduce power as necessary until actual Circ. Water AT is s Allowable AT. j 1

3.5 Refer to 5023-5-1.1 for limitations during heat treating evolutions. l 4.0 RECORDS i

4.1 Route completed daily log sheet to the SRO Ops Supv. for review, then !

forward to the NPDES Engineer.

i

[1] The calculation is derived, as follows:

Allowable AT = Maximum AT available in order to remain within limits 489.6 = Cumulative AT limit constant for any day (20.4*F x 24 hrs.)

Daily Average = Current average hourly AT up to the present time Number Nours Remaining in Day = Number of hours left until mirinight l 24 - Number Hours Remaining in Day = Number of hours to present time j

ATTACHMENT 11 PAGE 4 0F 5 l

1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 66 0F 100 ATTACHMENT 11 TCN l0'

/

CIRCULATING WATER INTAKE / DISCHARGE AT UNIT DATE CAUTION If Actual Circ. Water AT is greater than Allowable AT, th10 the

, Shift Superintendent must be notified And power reduced as i necessary until Actual Cire. Water AT is 5 Allowable AT.

1 TIME PLANT ACTUAL CALCULATED CALCULATED i (Line Thru POWER CIRC WATER DAILY AVG. ALLOWABLE "T tinused AT (*F) AT (*F) [2]

(CV9005 AVG) AT (*F) [3] g

' column)

N 0000/0100 1

0200/0300 j 0400/0500 i 0600/0700 0800/0900 l 1000/1100 1

1200/1300 ;

-l 1400/1500 1600/1700 1800/1900 2000/2100 2200/2300

[2] Calculate per Step 3.4.1. I

[3] Calculate per Step 3.4.2.

0100-0600: PERFORMED BY: REVIEWED BY: /

SR0 Ops. Supv./ Date 0600-1800: PERFORMED BY: REVIEWED BY: /

SR0 Ops. Supv./ Date

! 1800-2300: PERFORMED BY: REVIEWED BY: /

l SR0 Ops. Supv./ Date l File Disposition: Route to SRO Ops. Supv. for review, then forward to NPDES l Engineer.

j ATTACHMENT 11 PAGE 5 0F 5

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 / AGE 670F100 ATTACHMENT 12 TCH b '3f#

AXIAL XENON OSCILLATION DAMPENING EXAMPLE A

X _. , . ,

I A O.04 ESI -0.01 L

ASl TRACE W/O ! DAMPENING S .

UPPE DAM lPENING CONTROL B'AND 0.05 -

- - --- - - - -- --- /

p _.

-- - -- - ------l--- ESI i

E

LOW . R DAMPENING C.ONTROL BAND

. .. , s I '

N 0.06 i D -'

NOTE THAT hAMPENING BEGINS!HERE)SINCE ASI W[1LL LEAVE.: s ESI 40.01 ' ;

E

~

X

~ THE'VT-0.01 !BANb ~ Phi 6R T6 THENMXYDAi/PENIND:DPPDRTtiNiTY'

, , + , .

. coj. 70

_. 10; 20 ,

30 . j,40

.p s

80 90 100 110 TIME (HOURS).

C 150 '- - - -

t E

A 140 -.

l . - -

-g G #

130 --

- -- ~

-I 2~ !

R 120 -- "h" -

. =-

s 110 -

' AXIAL XENON.' OSCILLATION l ~DA;MPENING EXAMP'LE' l (IN WD) _.

1

- ! I i i i i i j

(

a 7 - 12. c H T i

J7-6.wS1 ATTACilMENT 12 PAGE 1 0F 1 .

l I

l

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 68 0F 100 ATTACHMENT

/ 13 TCN n ASI PLOT UNIl DATE

.00

.05

.04 . - - - ,

.03 ' ' $

/- i- '

i- .. i i- . <

.02 - - - : y: - . - . . - -

A .01 S ESI i + . 01

+.02 - 4- - - -

l

+.0 3 - -

+.04 + t- 1

+ o< ,

+.0 5 l

+.06 - - - - l- - - -

100 4- + + + + + , ,

I

% 90 - - - < * , * < s s -

80 - - :- -

PC 70 . , s - . . , . ,, . - , -

OV 60 i- .i- .i < <

i- ' ,

WD 50 . - - - - - . - - - -

l EO 40 . - - ~

RO 30 i + 4 , + + +

6 20 = = r * ' < ~ c i> # < ~ > i i-10 + 4*.i- + - - L. - - -

150 . + < , i + , s + , i + d- .

PP 140 ' ~ *

. - ~ * - s > ' s * ' '

LO 130 -- - - - - - L- - - - - - -

OS 120 . . , . - . s - , s . . - , , . -

E- 110 +-i- . .- -i-

+ + + i- +

A i 100 *

5. ' - - - = - * * -

N 90 - - - - - - - - - - i 80 . . ~ , . . ,s. - . - - - .

150 - - - - - - - - - -

GP 140 J- - - - - - - -

RO 130 . , , , , , s . , , . , .

OS 120 i- - < * * ' ' '

U- 110 :- - - :- :- - - - - - - - -

P 1 100 .

N 90 !- +- + +

6 80 - - < . - < - - - - - - - >

150 ' < - - < . s .- < . - .

GP 14 0 + + i-RO 130 - - - - - - - - - -

OS 120 U- 110 - - - - - - - - - - - -

P 1 100 . , , - . , . - - >

N 90 ' '

5 80 4 8 12 16 20 24 28 32 36 40 44 48 TIME (HRS) i FILE DISPOSITION: File per Section 7.0 of this instruction.

l J7-6.wS1 ATTACHMENT 13 PAGE 1 0F 1 l

i NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 i UNITS 2 AND 3 REVISION 6 PAGE 69 0F 100 ATT3CHMENT14 TCN(D ASI CONTROL STRATEGY DURING STEADY STATE OPERATION 1.0 ASI Guidelines NOTE: To minimize possibility of ASI exceeding band of ESI 0.05 Shape Index Units, ASI is typically maintained within a band of ESI i 0.01 Shape Index Units.

l 1.1 Operations Physics Summary, Figure 6-1, or as directed by a memorandum approved in accordance with 5023-V-13. (Ref. 2.2.3 and i 2.4.2.2) I 1.1.1 If the ESI per the Operations Physics Sumary differs from the " observed ESI" (ASI average over an oscillation cycle), then the " observed ESI" may be used at the SR0 Ops. Supv. discretion. (Ref. 2.4.2.23)

NOTE: ASI may be permitted to swing for determining ;

ESI if directed by Reactor Engineering.

1.1.2 Jf the ASI oscillations are of small magnitude, then p(Ref.2.4.2.23)erform Section 2.0 at the SR0 Ops. Supv. discretion.

1.1.3 jf CEAs are required to dampen ASI oscillations, then perform Section 3.0. However, to minimize potential for pellet / clad interaction in the CEA affected zone, move CEAs in small smooth, frequent movements of less than 3 inches per minute. Offset CEA movement by dilutions or borations, as applicable.

2.0 Control of Small Magnitude ASI Oscillations (Ref.2.4.2.5) 2.1 To minimize CEA motion, the initial control of ASI oscillations of small magnitude may be attempted at SRO Ops. Supv. discretion by utilizing temperature changes within the full power temperature band, as follows:

2.1.1 To prevent large oscillations from starting, attempt to maintain the size of the Xenon oscillation to less tran or equal to 0.01 ASI units, peak-to-peak.

ATTACHMENT 14 PAGE 1 0F 3

I NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7

! UNITS 2 AND 3 REVISION 6 PAGE 70 0F 100 ATTpCHMENT14 TCN h 2.0 Control of Small Magnitude ASI Oscillations (Continued)

NOTE: An approximate value for ASI worth as a function of temperature is 0.002 ASI Units /*F.

2.1.2 Attempt to perform RCS dilutions to return Tc to the upper half of its Control Band (Attachment 8) to coincide with periods when the ASI is more negative than the ESI. ,

2.1.3 Attempt to perform RCS borations to return Tc to the lower half of its Control Band (Attachment 8) to coincide with periods when the ASI is more positive than the ESI.

3.0 Control of Large Magnitude ASI Oscillations NOTE: Attachment 12 is an example of ASI dampening by CEA insertion.

3.1 H CEA half wave dampening is required on projected ASI shift outside the target band, then while power is moving toward the top of the Core, connence inserting PLCEAs or Reg. Group 6 to hold ASI at ESI i 0.01 shape index units (PLCEAs is preferred). Complete one of the following steps: (5ee Step 1.1.3) 3.1.1 Insert the PLCEAs per 5023-3-1.3 until the ASI target is reached, or until 112.5 inches [1] is reached, whichever is more limiting. (Tech. Spec. Fig. 3.1-3) 3.1.2 Insert Reg. Group 6 CEAs until the ASI target is reached, 9I until 120 inches is reached, whichever is nore limiting..(Tech. Spec. Fig.3.1-2) l 3.1.3 H additional CEA insertion is required to maintain ASI within the target band, then perform Step 3.1.1 again for the CEAs not yet inserted._

1

[1] H Reactor Power level is between 20% and 50%, then PLCEAs may be inserted !

until 75 inches is reached. However, in this case the time limits of 1 Tech. Spec. 3.1.3.7 apply and logging is required per 50123-0-42, Att. 26.

[2] H COLSS is out-of-service, then the Short Term Insertion limit may be more limiting than the Transient Insertion Limit. See Tech. Spec. 3.1.3.6.

ATTACHMENT 14 PAGE 2 0F 3

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 71 0F 100 ATT3CHMENT14 TCN fgh 3.0 Control of Large Magnitude ASI Oscillations (Continued)

> 3.1.4 H further CEA insertion is required to maintain ASI l

within the target band, then complete the following:

(See Step 1.1.3)

CAUTION Inserting Group 6 CEAs below 80 inches for control of a strongly negative ASI will worsen the problem. 1

.1 Insert Reg. Group 6 CEAs until the ASI tar l E until the Transient Insertion Limit [2]getisisreached, reached,E l until CEAs are 80 inches withdrawn, whichever is most limiting. (Tech. Spec. Fig. 3.1-2)

.2 When below the Long Term Steady State Insertion limits, then adhere to the time limitations of Tech Spec. 3.1.3.6 and logging requirements of S0123-0-42, Attachment 25.

3.1.5 H further CEA insertion is required to maintain ASI within the target band, then insert Reg. Group 5 while ensuring at least is inches of separation is maintained between Groups 5 and 6. (Ref. 2.4.2.9, 2.4.2.10, and 2.4.2.12) 3.1.6 H ASI cannot be maintained within the 1 0.05 steady state band, then a Power reduction should be considered to restore ASI within the operating band.

3.1.7 As Xenon distribution reverses and shifts the power distribution back toward the bottom of the core, commence withdrawing CEAs to hold the ASI at the ESI 1 0.01 Shape Index Units. (SeeStep1.1.3)

J7-6.wS1 ATTACHMENT 14 PAGE 3 0F 3

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 72 0F 100 ATT/)CHMENT15 TCN [n'V y POWER MANEUVERING B0 RATION / DILUTION GUIDELINES UNIT PERF. BY 1.0 PREREQUISITES INITIALS 1.1 Verify this document is current by checking a controlled copy or by using the method described in 50123-VI-0.9.

NOTES: 1. Enter values"as positive within this procedure.

2. The values required in this attachment may be obtained from Reactor Engint.ering.

3. Data supplied by Reactor Engineering shall be in the fornat specified by 5023-V-13 with a copy of the transmittal affixed to this Attachment.

2.0- POWER MANEUVERING GUIDELINES 2.1 Increasing Power 2.1.1 Determine the maximum loading rate for the power increase based on Turbine temperatures and fuel conditioning. Use the most restrictive loading rate. Review the following attachments:

.1 Attachment 1, Maximum Core Power Escalation Rate ;

.2 Attachment 2, Turbine Run-up and Loading Rates With Reheat Temperature Control {

.3 Attachment 3, Recommended Maximum Rates for Increasing Load on a Heatsoaked Machine

.4 Attachment 4, Recommended Maximum Rates for Increasing Load on a Machine NOT'Heatsoaked 2.1.2 Jf equipment required for the target power plateau is or will be removed from service, then determine the reduced steady state power plateau l p(er Ref.Attachment 2.4.2.3) 6, Recommended Power Plateaus.

2.1.3 Determine the time expected to remain at each intermediate power plateau. Ensure. action has been taken to restore deficient equipment to operability to support reaching the target power plateau.

ATTACHMEN'T 15 PAGE 1 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUClION S023-5-1.7 UNITS 2 AND 3 REVISION 6 [, PAGE 73 0F 100 ATT/jcHMENT15 TCN T 2.0 POWER MANEUVERING GUIDELINES (Continued) 2.1.4 Obtain a Xenon profile based on past power history and the projected power history for the transient to the target ,

power level . The Xenon profile may be obtained by: I

.1 T

Generating the Xenon profile by inputting the necessary data into the Reactivity Calculator Xenon option on the gg applicable PC, or iN l

. s

.2 Requesting Reactor Engineering provide the Xenon profile. -

2.1.5 Calculate the boration/ dilution volumes and injection rates required to achieve the load increase at the desired loading rates per Step 3.0.

2.2 Decreasing Power NOTES: 1. H the power decrease is occurring at End Of Cycle (RCS boron concentration less than 50 ppm),

and plans are to come off line without stopping at some lower power level, then the o)timum is a steady load drop of at least 10% per iour.

2. H the power decrease is occurring at End Of Cycle ( RCS boron concentration less than 50 ppm),

Artd plans are to stop the power decrease at some lower power plateau, then the. optimum is a slow and steady power reduction of 2% per hour or less.

2.2.1 Determine the maximum unloading rate for the power decrease by reviewing Attachment 5, Recommended Maximum Rates for Decreasing Load.

.1 During an emergency situation, power may'be decreased by either CEA insertion, baration, or both, and the limits of Attachment 5 may be exceeded.

.2 During normal maneuvering, power decrease should be accomplished by boration, while CEAs are used for ASI control.

2.2.2 H equipment required for the current power plateau is to be removed from service, then determine the reduced steady I state power plateau per Attachment 6 Recommended Pcwer Plateaus. (Ref.2.4.2.3) 2.2.3 H a load reduction is required to restore DNBR Operating margin due to a loss of COLSS and COLSS Backup Computer, then refer to Attachment 10 for additional guidelines.

ATTACHMENT 15 PAGE 2 0F 17

.. ................___............_. ..' . .. I NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 74 0F 100 ATTA,CHMENT 15 TCNIDb.

l 2.0 POWER MANEUVERING GUIDELINES (Continued) 2.2.4 Jf one or both CEACs is lost, then refer to S023-3-2.13, Section for CEAC Inoperability.

2.2.5 Determine the time expected to remain at each intermediate power plateau. Ensure action has been taken to restore ;

deficient equipment to operability to support reaching the i target power plateau. I

/

2.2.6 Obtain a Xenon profile based on past power history and the projected power history for the transient to the target power level. The Xenon profile may be obtained by:

.1 Generating the Xenon profile by inputting the necessary T ;

data into the Reactivity Calculator Xenon option on the $0 applicable FL, or iN

.2 Requesting Reactor Engineering provide the Xenon profile.

2.2.7 Calculate the boration/ dilution volumes and injection rates required to achieve the load decrease at the desired i unloading rate per Step 3.0.

3.0 BORATJON/ DILUTION VOLUME AND RATE DETERMINATION

_ l 3.1 Record the present power plateau data: I Reactor Power: % Boron Concentration: ppm ,

CEA Position: Group at "

Burnup: EFPD 3.2 l Record target power data Target Power level: %'

l NOTE: In the following steps, the subscripts +1, +2, +3....etc.

indicate the time in hours since the initiation of the power transient at time zero (To ).

3.3 Power Defect (PD) 3.3.1 Determine increwental power defect (PD) for power transient:

.1 Determine the current 100% power defect based on core life (EFPD) from the OPS Summary Physics data book figure 5.4.

100% Power Defect % Ak/k ATTACHME,NT 15 PAGE 3 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 75 0F 100 ATT3CHMENT15 TCN (p' 3.0 B0 RATION / DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.3.1.2 On the figure below, draw a line from the zero to the 100%

power defect determined in Step 3.3.1.1 at 100% power.

. . . .:. . { . , . . . . .p .: . . , ,

,,7 .,

...j.,7 ..j. . , . .. ;

.Tv.

[ .

l ,T, ,

.T

. [.

T. v v'r v

. :T

.s.v,. T, . "-...

" ".va."' T ..T, . .' .ves n T. a .T

. . .: , .1. p p p p;. .y . ..<..!.p , . . . <. , . p . p p : .. .

.p;.. , y 4. , , . p p t .,

C, 2.0

) .----m.

s

.4 t .r-r-r. t. .+;. . -m. . ,t-f . . . . J.. ....y .1. ., ,. .q.

i s F. .re.

rn-1-4

+-: 1.-n-v.

.,: . i ..t---r-r. +t--: .e >

,4 ...p... ... . .

g

. .. .:. 3 .. .

.....).

1.5 ..r. -.'.r. :... ! r. :

t:

4. . .

8" .

-, < 7._,.

.. . . : r t :... , 7--. . , .7.,,. .c. 4..... .. 7.,.,F

- -r,.;-- 1 ".....: .. t.r ,.-.

v --

. .r. n ,

..r . j . . p. ', ..1'

' .' .t. . .,

e l !.; .t........j..'

'l~.

.p. . . r.; ' ' ' ."9 ..

r:

g ... . ..

, : : g. ,7.....

.r.r. .r.,. ,r. T..n,

..., :".. r. . r,: ": ,.-. . - ,:

u x

1.0 -,. ,. :--,,,-r,.,-.-,r.er

.. .p -4.- .<.p

, - . ,,,.s-

. . ; . -, ,c r,...,.

.-4. p , . p . .> .:

- . , ..,- " . < . r .vm.. ,T...

, , . . . ... . ,, ,,...;.. . . . . . . o. . .. . ,,

..... . .: .. . . > . , .. . . . . I, :: .:.<. ,. ..., ...

. .. .. . . ..p. .... ....p. . . . . ...

O.s ;.i..u.62- ;..:- ....;2 2 ,,- - 2 222;-3-;;22

. . . . . . . . . . .. . . . 4. 2c.;t.4. 9. . 4 } ... a..:.4

.. . .p . i...a. ., ..

.s.,, ,.

., ,.~

,7 L., , . . , ,

.4.. .. 3. } . . . .. ., ,

,.p.......,,.. .

.,,7; ...

.,... . , . . , , , , , . . . . , ,.4.,

..p. :. 4

....p.

.,,.....,.,.......~,.i.,.,,

, ..:..,,..l... .. ,..

0.0 '

O 10 20 30 40 50 60 70 60 90 100 PowEA (10

.3 Determine the hourly power defect for the power transient in the following table using the data from the line drawn based on the current 100% power defect. Each entry should reflect the rate of power change.

Power defect at initial power ,

PD o: % AK/K Power defect at T.1 , power ,

PD.1: % AK/K Power defect at T.,, power , PD.,: % AK/K l Power defect at T3 , power ,

PD3: % AK/K l Power defect at T.4 , power , PD.4 : % AK/K !

Power defect at T.5 , power ,

PD.5 : % AK/K Power defect at T.,, power _, PD,,: % AK/K Power defect at T.7 , power ,

PD.7 : % AK/K l Power defect at T., , power , PD.,: % AK/K Power defect at T,,, power , PD., : % AK/K Power defect at T.io, power ,

PD.io: % AK/K Power defect at T+11, power ,

PD+11: % AK/K Power defect at T+12, power ,

PD+12 : % AK/K Power defect at T n, power ,

PD.33: % AK/K Power defect at T.14, power ,

PD+14 : % OK/K Power defect at T.15, power ,

PD.35 : % AK/K Power defect at T.13, power , PD.g: % AK/K l Power defect at T.17, power ,

PD 17: % AK/K Power defect at T+1a, power , PD.3,: % AK/K Power deft.ct at T.ig, power , PD.3,: % AK/K Power defect at T.,o, power ,

PD+20: % AK/K Power defect at T.n, power ,

PD+21: % AK/K Power defect at T+22, power , PD.,, : % AK/K Power defect at T+23, Power ,

PD+23: % AK/K Power defect C. T.u, power ,

PD.3: % AK/K ATTACHME.NT 15 PAGE 4 0F 17

l NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 76 0F 100 ATT3CHMENT15 TCN b -

l 3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.3.2 Determine incremental APD:

PD0

APD.i - PD3 % AK/K f

APD+2 PD.1 - PD+2 % AK/K

APD.3 PD+2 - PD.3 % AK/K APD., =

PD.3 . -

PD., =

% AK/K APD.5 = PD.4 =

- PD.5 % AK/K

PD.,

APD.s -

PD., % AK/K APD.7 = PD., - PD.7

=

% AK/K APD., - PD.7 - PD.3

% AK/K APD., = PD., - PD., =

% AK/K APD.to = PD., - PD.3a

=

% AK/K

=

APD.it = PD.to - PD33 % AK/K

= "

APD+12 PD.it - _ PD+12 % OK/K

=

APD.i3 = PD.ir - PD.13 % AK/K APD.g4 =

= PD.t3 - PD.14 % AK/K APD+ts = PD.14 - PD.g3 -

% AK/K

=

APD.is = PD.is PD.is % AK/K

=

APD.i7 = PD.is - PD.17 % AK/K APD,18 - PD.g7 -

PD.13

% AK/K APD.1, - PD.i. -

PD.3, =

% AK/K APD+20 = PD.g, -

PD.,o =

% AK/K APD.23 - PD.go -

PD.,1 =

% AK/K

=

APO.22 = PD.21 - PD+22 % AK/K 1

- =

A'?D+r3 = PD+rr PD.23 % AK/K

=

t PD+24 = PD+23 - PD+24 % AK/K ATTACHME.NT 15 PAGE 5 0F 17

i I

i NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 77 0F 100 ATT$CHMENT15 TCN k 3.0 BORATJON/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.4 CEA Worth (CEA)

NOTE: The CEA insertion strategy in the following steps maintains the initir:1 equilibrium ASI value.

I 1

3.4.1 i

The recommended {EA insertion strategy for maintaining l Average ASI close to ESI is, as follows:

(Ref. 2.4.2.26) )

.1 Determine inches of CEA insertion per percent power change l l

i based on core life from the figure below: I l

inches CEA insertion per % power change c 3.0 j s -.-. .. . . . . .

A - . . .

l

-.> ,,,,,, . . ....,.....,, +..: . .

M - . , , , . .. .. , , , , , , . . . .. . ....,........

l 2.5 -.

1l++++ + ++++++ + i..i. +++

T,

_..>. 3 .n.>.3..>..>....;..p. .i..i.. ..;.. ..;..;.. ...g..;..;. .;..<. .i.

g .y .s ii..3.. ... . . . . . . . .a. ,.. ,.<,

N -- - - - - - *** *** ** *

r l , .>. .>. .>..>. .>..>..y..>..s. .,. 3..;..g..). .!..l.

I 2.0 - .;

i. .i. .i..i..i..i. ' .i. ' i..' i..i.

i N , .; , , , , , , , , , ,,,,,,,, , , i C -

j E ' ' ' ' ' * *

S 1.5 l -- ---- --- - -

i .-. ...,,.,, ,. .

I P .. ......:.. . . - - .. ..... . .

E _ .i . c. . . .;. .;.2., '....;..

R .

g 1.0 a.-...a.- '

- .; . u . a. . :- . a 4 . - - - ;. - - . a . ----- -

.; 4 .... , . .;. . 4. , 4. ,.,,,,,,,,,,

p - ,; , , . . ;. . < ,,,,,, , ,

O -; .<. + <<< , < <

W _ .; .

i E O.5 -;

5-

! R .; .,.

~~ - ' ' ' ' '

H t' ' '

A l

; ;;. : . , . !. .. .. '..TY" N O '''''''''''''''''''''''

l G O 10 0 200 300 400 500 600 E

CORE BURNUP (EFPD)

ATTACHMENT 15 PAGE 6 0F 17 i

l

J -

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 '

UNITS 2 AND 3 REVISION 6 y, PAGE 78 0F 100 ATT3CHMENT15 TCN (P M.

3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued)

NOTE: The CEA positions determined in the following ste)s is a l recommendation for maintaining the initial equili)rium

! ASI. Deviation from these positions is allowed if l

~

required for ASI control and may require adjustments to the boration/ dilution rates or allowing RCS temperature to swing within the control band.

1 3.4.1.2 Determine the total CEA insertion (AP) required for the hourly power change by multiplying the value obtained in Step 3.4.1.1 times the expected rate of power change.

AP.3 = Rate of change 4 x Step 3.4.1.1 in/% = "

A P., = Rate of change % x Step 3.4.1.1 in/% = "

A P.3 = Rate of change 4 x Step 3.4.1.1 in/% = "

AP.4 = Rate of change % x Step 3.4.1.1 in/% = "

AP.s = Rate of change % x Step 3.4.1.1 in/% = "

AP.6 = Rate of change % x Step 3.4.1.1 in/% = "

AP.7 = Rate of change 4 x Step 3.4.1.1 in/4 = "

AP.e = Rate of change % x Step 3.4.1.1 in/% = "

A P., = Rate of change % x Step 3.4.1.1 in/% = "

! AP.3o = Rate of change % x Step 3.4.1.1 in/% = "

AP.33 = Rate of change % x Step 3.4.1.1 in/% = "

AP+12 = Rate of change % x Step 3.4.1.1 in/% = "

AP.33 = Rate of change 4 x Step 3.4.1.1 in/% = "

AP 34 = Rate of change % x Step 3.4.1.1 in/% = "

AP.35 = Rate of change % x Step 3.4.1.1 in/% = "

A P.3, = Rate of change % x Step 3.4.1.1 "

in/% =

AP.37 = Rate of change 4 x Step 3.4.1.1 in/% =

AP.38 = Rate of change 4 x Step 3.4.1.1 in/% = "

l A P.3, = Rate of change 4 x Step 3.4.1.1 in/% = "

AP 42o = Rate of change 4 x Step 3.4.1.1 in/% = "

AP.21 - Rate of change % x Step 3.4.1.1 in/% = "

AP+22 = Rate of change % x Step 3.4.1.1 in/% = "

AP+23 = Rate of change 4 x Step 3.4.1.1 in/% = "

AP.g. = Rate of change 4 x Step 3.4.1.1 in/% = "

ATTACHMENT 15 PAGE 7 0F 17 l

l t

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 79 0F 100 ATT3CHMENT15 TCN b 3.0 BORATION/ DILUTION VOLUME AHD RATE DETERMINATION (Continued) 3.4.1.3 Determine CEA position required for ASI control based on insertion required in Step 3.4.1.2:

NOTES: 1. In determining CEA insertion for ASI control, CEA sequencing overlap is ignored. The CEA insertion is the total insertion of all groups inserted into the RX Core (e.g., PLCEAs at 115", Group 6 at 90" and Group 5 at 140" results in 105" of CEA insertion: PLCEAs for 35" +

Group 6 for 60" + Group 5 for 10").

2. CEA insertion for ASI control is limited to:

PLCEAs - 115" withdrawn Group 6 - 80" withdrawn Group 5 - Minimum of 15" above Group 6

3. Indicate position for CEA group selected for ASI control until insertion limit is reached.

4. Indicate CEA withdrawal by circling (+) and CEA insertion by circling (-) when determining new CEA positions.

Position P.3 =P o +/- AP.1 =

+/- = Gr at "

Position P+2 = P.i +/- AP+2

=

+/- = Gr at "

Position P,3 = P., - Gr "

+/- AP.3 =

+/- at Position P.4 = P.3 +/- AP., =

+/- = Gr at "

Position P.5 = P., +/- AP.5 =

+/- = Gr at "

Position P+6 = P.5 +/- AP+6 = +/- = Gr at Position P.7 = P+6 +/- AP7 =

+/- = Gr at Position P., =

P.7 +/- AP., =

+/- = Gr . at "

Position P., =

P., +/- AP,, = +/- = Gr at "

Position P.13 = P., +/- AP.1o

=

+/- = Gr at "

Position P.ti = P.go +/- AP.33 =

+/- = Gr at l

Position P.1, = P.it +/- AP+tz =

+/- = Gr at "

l Position P.33 = P+12 +/- AP.13

=

, +/- = Gr at Position P.1, = P.33 +/- AP+1, =

+/- = Gr at Position P.13 = P.14 +/- AP.15 =

+/- = Gr at "

Position P.1, = P.15 +/- AP.35 =

+/- = Gr at Position P.1, = P.i. +/- AP.i, =

+/- = Gr at Position P.1,= P.1, +/- AP+1s

=

+/- = Gr at "

Position P.3, = P.1, +/- AP.ig =

+/- = Gr at "

Position P.,a = P.1, +/- AP.33 =

+/- = Gr at "

Position P.33 = P+20 +/- AP.31 =

+/- = Gr at Position P,,, = P.33 +/- AP.3, =

+/- .= Gr at "

Position P.n = P.3, +/- AP.33 =

+/- = Gr at Position P+24 = P+23 +/- AP+24

=

+/- = Gr at ATTACHMENT 15 PAGE 8 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 80 0F 100 ATT3CHHENT15 TCN [0' ,

3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.4.2 Determine incremental CEA worth: (OPS Figure 4.1, 4.2, 4.5 or 4.11)

.1 Group 6 increr:antal CEA worth at HFP may be taken from OPS Figure 4.1.

NOTE: Position at which ASI control shifts from PLCEAs to Group 6 requires addition of PLCEA and Group 6 worth and is indicated by placing i

Group 6 position in blanks. '

CEA Worth at Po , CEAo = Gr at "= % AK/K CEA Worth at P3, CEA.1 = Gr at "= % AK/K CEA Worth at P.2, CEA+2 = Gr at "= % AK/K CEA Worth at P.3, CEA.3 = Gr at "= % AK/K CEA Worth at P.4, CEA.4 = Gr at "= % AK/K CEA Worth at P3, CEA 5 = Gr at "= % AK/K CEA Worth at P.6, CEA., = Gr at "= % AK/K CEA Worth at P.2, CEA.7 = Gr at "= _. % AK/K CEA Worth at P+a, CEAe = Gr at " = _ ,_ % AK/K CEA Worth at P.,, CEA., = Gr at "" % AK/K ;

CEA Worth at P,3o, CEA,1a - Gr at "= % AK/K j CEA Worth at P31, C EA+11 = Gr at _ "= % AK/K l CEA Worth at P.iz, CEA.32 = Gr at _"= % AK/K CEA Worth at P.13, C EA.13 = Gr at _"= % AK/K CEA Worth at P.34, CEA.14 = Gr at "= % AK/K CEA Worth at P.is, C EA,13 = Gr at "= % AK/K CEA Worth at P.15, CEA.is = Gr at _ "= % AK/K CEA Worth at P.17, CEAiy = Gr at _ "= % AK/K CEA Worth at Pis, CEA.13 = Gr a t __ "= % AK/K 1 CEA Worth at P,13, CEA3, = Gr at "= % AK/K CEA Worth at P.ro, CEA.2a = Gr at "= % AK/K CEA Worth at P.23, CEA.21 - Gr at "= % AK/K l CEA Worth at P.22, C EA+22 = Gr at "= % AK/K CEA Worth .it P+23, C EA+23 = Gr at "= % AK/K CEA Worth at P+24, C EA.2, = Gr at "= % AK/K ATTACHMENT 15 PAGE 9 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 81 0F 100 1 ATT3CHMENT15 TCN b' _

3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.4.3 Determine change in inserted CEA worth (ACEA):

i ACEA.3 = CEA o - CEA.3

% AK/K

=

l ACEA+2 = CEA.3 - CEA+2 % AK/K l

C EA.,

ACEA.3 - CEA.3 % AK/K ACEA., = =

CEA,3 - CEA.4 % AK/K ACEA.s = CEA.4 - CEA., e I

% AK/K

ACEA., CEA+5 - CEA6 % AK/K ACEA., = CEA.6 - CEA.7

% AK/K l ACEA.. = CEA.7 - CEA+a - % AK/K l ACEA., = CEA+a - CEA., = ._ % AK/K ACEA 3o = CEA., - CEA ie

=

% AK/K

=

ACEA.33 = CEA.3a - CEA.33 % AK/K l l

CEA+12 = CEA.33 CEA.32

=

% AK/K ACEA 33 = CEA.3, - CEA.33

=

% AK/K ACEA.3 = CEA.33 - CEA.n % AK/K

=-

ACEA.35 = CEA.a - CEA+1s % AK/K ACEA.3, = CEAis - CEA,33 =

% AK/K

=

ACEA.37 = CEA.3s - CEA.37 % AK/K

=

ACEA+18 = CEA.37 - CEA.38 % AK/K !

ACEA.3, = CEA,is - CEA.3, = % AK/K

{

ACEA+2a = CEA.3, - CEA.za =_ % AK/K j

=

ACEA+21 = CEA+2a - CEA+21 % AK/K

=

ACEA+22 = CEA+21 - CEA+22 % AK/K

- CEA.g3 = % AK/K ACEA.23 = CEA.zz

=

ACEA+24 = CEA+23 - CEA+24 % AK/K l

i ATTACHMENT 15 PAGE 10 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 82 0F 100 ATTAjCHMENT 15 TCN >t' _ kq(,

3.0 B0 RATION / DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.5 Xenon Worth (XE)

NOTE: Obtain Xenon worth from Xenon option of Reactivity Calculator or Reactor Engineering calculations using detailed power history and expected power history projections.

3.5.1 Determine incremental Xenon concentration (XE) worth:

NOTE: Use the Xenon worth for an additional one half hour, i .e., for T.i use the xenon worth for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months into the transient and for T., the worth for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months into the tre sient, to compensate for the delay time required for boration or dilution to rescn the Core.

Xenon worth at initial power, XE o :_ % AK/K Xenon worth at T.1, XE.1: _ _ % AK/K Xenon worth at T.,, X E.,:

4K/K Xenon worth at T.3, XE.3: % AK/K Xenon worth at T.., XE.4 : % AK/K Xenon worth at T.3, X E.3 : % AK/K Xenon worth at T.3, XE.3

% AK/K Xenon worth at T.7, XE.7 : % AK/K l Xenon worth at T. , XE.g: % AK/K l Xenon worth at T.,, X E.,: % AK/K Xenon worth at T.to, XE.3o: % AK/K Xenon worth at T.gi, XE.31: % AK/K Xenon worth at T+12, XE+12 : % AK/K Xenon worth at T.33, XE.33: % AK/K Xenon worth at T.3., X E.3, : % AK/K Xenon worth at T.15, X E.35 : % AK/K Xenon worth at T.36, X E.ie : % AK/K Xenon worth at T.37, XE.37: % AK/K Xenon worth at T.33, XE.13: % AK/K Xenon worth at T.3,, XE3,: % AK/K Xenon worth at T.go, XE,,o: % AK/K Xenon worth at T.21, XE+21: % AK/K Xenon worth at T+22, XE+22 : % AK/K Xenon worth at T.23, XE.33 : % AK/K Xenon worth at T+24, XE.24 : % AK/K ATTACHMENT 15 PAGE 11 0F 17

NUCLEAR ORGANIZAT10N OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 83 0F 100 ATT/)CHMENT15 TCN h b h 3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.5.2 Determine incremental AXE:

AXE.1 = XEa -

X E.1

= % AK/K

=

AXE +2 = XE.1 - XE+2 % AK/K

=

AXE.3 = XE.2 - XE 3 % AK/K AXE.4 =

= XE.3 , - XE.4 % AK/K

=

AXE.3 = XE.4 - XE.s % AK/K AXE +6 = XE,3 - XE.s =

% AK/K AXE.7 = X E., - XE.7 =

% AK/K AXE., = X E.7 - XE., =

% AK/K AXE., = X E., - XE., =

% AK/K AXE.ia = XE., - XE.to =

% AK/K AXE.it = XE.to - XE.gi =

% AK/K AXE.gz = XE.it - XE+12

=

% AK/K AXE.13 = X E.3, - XE.13

% AK/F AX E.14 = XE.13 - XE.i,

% AK/K

=

AXE.is = XE.14 - XE.is % AK/K AX E.1, = XE.13 - XE.1, = % M/K AXE.17 = X E.3, - XE.g7 =

% AK/K

=

AXE +18 = XE.17 - XE+1s % AK/K AX E.3, = XE.is - XE.g, ___

= % AK/K AXE.2, = X E.1, - XE.2o * % Ak/K I

=

AXE +21 = XE+2a - X E.,1 % AK/K AX E.,., =

XE+21 - XE+rz % AK/K AX E.,3

= XE+2z - XE.23 % AK/K AXE +24 - XE.23 - XE.24 ____ % AK/K 3.6 Record Inverse Boron Werth as a function of EFPD:

(OPS Figure 3.1)

Inverse Boron Worth : ppm /% AK/K ATTACHMENT 15 PAGE 12 0F 17

1 i

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 84 0F 100 ATT/)CllMENT15 TCN --

3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.7 Calculate Reactivity Defect (Cg) by totaling A Power Defects (Step 3.3), A CEA worth (Step 3.4), and A Xenon worth (Step 3.5):

(Stop3.3) (Step 3.4) (Step 3.5)

APD.3 _ + ACEA. + AXE.1 _ =C g3 % WK APD,2 _ + ACEA., +, AXE., = Ca2 % AK/K APD+3 + ACEA.3 + AXE.3 = Cg3 % AK/K !

APD.4 + ACEA., + AXE., =C.a % AK/K APD.3 _ + ACEA.3 + AXE.3 =C g3 % AK/K ;

APD+6 + ACEA., + AXE +6 = Ca6 % AX/K APD.7 4 ACEA.7 + AXE.7 =C, g % AK/K APD.a + ACEA., + AXE., =C g3 % AK/K APD., + ACEA., + AXE., =C, a % AK/K APD.io + ACEA.io + AXE.to = C,3a % AK/K APD+12 + ACEA.it + AXE.it =C ait % AK/K APD.1, + ACEA+12 + AXE.1, =C air %AW APD.33 + ACEA+13 + AXE.13 = Cg33 % Ak/K

+ %AW APD.i. ACEAt. + AXE.3, _=C. ai APD.is + ACEAis + AXE.15 =C ais % AK/K APD.is + ACEA.is + AXE.3, =C, g3 % AK/K APD,17 +

ACEA.17 + AXE.17 =C a37 % R/K APD+18 -- + ACEA.is + AXE.1,_ =C,ai % AK/K APD.3, + ACEA.1, + AXE.1, =C aig %AW APD+2a + ACEA+2a + AXE.2a =C a2a % AK/K APD,21 + + AXE.gt =C R21 % AK/K ACEA+21

+ + AXE.2, =C n22 APD+22 ACEA+22 % AK/K APD+23 + ACEA.23 + AXE.23 =C R23 % AK/K 4 + AXE.3, APD.24 ACEA.2. = C,u, % AK/K ATTACHMENT 15 PAGE 13 0F 17 i

I

NUCLEAR ORGANIZATION- OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 85 0F 100 ATT3CHMENT15 TCNln'k, ,-

3.0 BORATION/ DILUTION VOLUME AND RATE DETERMINATION (Continued)

NOTE: Calculation of the adjusted boron concentration provides data needed for the computer SONGS 2/3 Boration/ Dilution Program.

1 3.8 Calculate Boron deviation (ACg ) using Inverse Boron Worth (Step 3.6) and Reactivity defects (Sten a.7):

Initial Boron Concentration (Step 3.1)

Adjusted Boron (Step 3.6) (Step 3.7) Concentration IBW X Cat = AC,1 ppm ppm IBW XC u = AC,, ppm ppm IBW X Ca3 - AC,3 ppm ppm IBW X Cg4 = AC,4 ppm ppm IBW XC as = AC as ppm ppm IBW X C,, = AC,5 ppm ppm IBW XC g7 = AC,7 ppm ppm IBW X C,, = AC sa ppm ppm IBW XC, g = AC,, ppm ppm IBW X Cato = AC aio ppm ppm IBW X Catt ppm ppm

= A Catt IBW X Cal 2 = ACat , ppm ppm IBW X C ,33 - AC,13 ppm ppm IBW XC, a1 = AC,14 ppm ppm IBW X C,33 = ACit , ppm ppm IBW XC, a3 = AC,36 ppm ppm IBW XC a17 = AC ity ppm ppm IBW X C,is = ACais ppm ppm IBW XC, a3 = AC,1, ppm ppm IBW X Ca2e ppm ppm

= A Ca2e IBW XC R21 = AC szt ppm ppm IBW XC uz = Ac azz ppm ppm IBW XC n3 = AC s23 ppm ppm IBW XC u4 = ACar , ppm ppm ATTACHMENT 15 PAGE 14 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 86 0F 100 ATT/)CHMENT15 TCN fo 3.0 B0 RATION / DILUTION VOLUME AND RATE DETERMINATION (Continued) 3.9 Calculate gallons of boration/ dilution re uired to adjust Boron EI concentration per SONGS 2/3 Boration/Dilu ion Program or 5023-3-2.2 C for: N 3.9.1 Indicate BAMU Tank and Boron concentration on which calculations are based:

O T-071 c. '= PPM T-072 C, = PPM 3.9.2 Boration/ dilution required to change C, by:

NOTE: Positive AC, indicates boration required and negative AC, indicates dilution required.

AC,3 at T.3 = gal. O Boration 0 Dilution

! AC ar at T.g = gal. O itoration 0 Dilution AC,3 at T.3 = gal. [] Soration 0 Dilution AC,4 at T.4 = gal. O Boration [] Dilution ACs , at T., = gal. [] Boration O Dilution I

AC,6 at T., = gal. O Boration 0 Dilution AC,7 at T., = gal. [] Boration 0 Dilution AC,, at T., = gal. [] Boration 0 Dilution AC,9 at T,9 = gal. O Boration [] Dilution l AC,3a at T.3a = gal. [] Boration O Dilution AC,33 at T.33

= gal. [] Boration [] Dilution j = gal.

AC air at T.12 [] Boration 0 Dilution 3C,33 at T.33

= gal. O Boration [] Dilution 60,3 at T.34

= gal. [] Boration [] Dilution ACais at T.3, = gal. O Boration [] Dilution l AC,3, at T.3, = gal. O Boration [] Dilution AC,37 at T37

=

gal. O Boration 0 Dilution

AC,3e at T.33

= gal. O Boration 0 Dilution l AC,3, at T.3, = gal. O Boration [] Dilution l 6C 820 at T+2e = gal. O Boration a Dilution AC s21 at T+2t = gal. O Boration [] Dilution ACs22 at T+22

= gal. O Boration 0 Dilution AC sza at T.23

= gal. [] Baration [] Dilution l ACs24 at T+24

= gal. [] Boration [] Dilution ATTACHMINT 15 PAGE 15 0F 17 l

._x.___

l l

NUCLEAR ORGANIZATION OPERATING thSTRUCTION S023-5-1.7 I UNITS 2 AND 3 REVISION 6 PAGE 87 0F 100 ATTACHMENT 15 TCN 3.0 B0 RATION / DILUTION VOLUNE AND RATE DETERMINATION (Continued) {

1 3.10 Calculate rates of boration/ dilution to support power l 1evel change per 5023-3-2.2. !

l NOTES: 1. Borations of less than 120 gallons should be injected as a batch at a flow rate of 2 gpm. 1

2. Dilutions of less than 600 gallons should be :

injected as a batch at a flow rate of 10 gpm. l Rate of [] Boration 0 Dilution (To to T.1): gpm Rate of [] Boration 0 Dilution (T.1 to T.,): spm Rate of 0 Boration 0 Dilution (T., to T.3): gpm Rate of [] Boration 0 Dilution (T.3 to T.4): gpm l

Rate of C Boration 0 Dilution (T.4 to T.s): spm l Rate of 0 Boration 0 Dilution (T.3 to T..): spm Rate of G Boration 0 Dilution (T. to T.7): gpm Rate of 0 Boration 0 Dilution (T.7 to T.8): gpm Rate of 0 Boration 0 Dilution (T., to T.,): gpm Rate of 0 Boration 0 Dilution (T., to T.1o): spm Rate of 0 Boration 0 Dilution (T.1o to T.11): gpm Rate of [] Boration 0 Dilution (T.11 to T.12): gpm Rate of 0 Boration 0 Dilution (T.1, to T.13): spm Rate of 0 Boration a Dilution (T.13 to T.14): gpm Rate of 0 Boration 0 Dilution (T.14 to T.1s): gpm Rate of 0 Boration 0 Dilution (T.is to T.1.): spm Rate of 0 Boration 0 Dilution (T.13 to T.17): gpm Rate of [] Boration 0 Dilution (T.17 to T.13): gpm Rate of 0 Boration 0 Dilution (T.i. to T.1,): gpm Rate of C Boration 0 Dilution (T.1, to T.,o): gpm Rate of 0 Boration 0 Dilution (T.,o tot.,1): gpm Rate of 0 Boration [] Dilution (T+21 to T+22): 9pm Rate of 0 Boration 0 Dilution (T.,, to T.,3): spm Rate of 0 Boration 0 Dilution (T 23 to T.,4): gpm ;

3.11 Transfer the following data to Attachment 18. Boration/ Dilution Schedule:

3.11.1 Expected CEA positions from Step 3.4.1.3.

3.11.2 Adjusted (expected) RCS boron concentration from Step 3.8.

3.11.3 Boration and/or dilution volumes from Step 3.9.

3.11.4 Boration and/or dilution flow rates from Step 3.10.

ATTACHMENT 15 PA'iE 16 0F 17

1 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 88 0F 100 ATTACHMENT 15 TCN U 3 Q COM ENTS PERFORMED BY: DATE/ TIME: _

INDEPENDENTLY VERIFIED BY: DATE/ TIME: T IC

'N REVIEWED BY: DATE/ TIME: s SR0 Ops. Supv. -

l FILE DISPOSITION: File per S0123-0-32.

J7-6.W51 ATTACHMENT 15 PAGE 17 0F 17

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 i UNITS 2 AND 3 REVISION 6 PAGE 89 0F 100

h. ' 1 ATT3CHMENT16 TCN W -

-REACTIVITY CALCULATOR - XENON PROGRAM eT 1 Select Reactivity Calculations from the applicable PC menu. C 2 Select Reactivity Calculator from submenu. (N '

3 Select Unit.

4 Select option 3) Xenon Calculations.

5 Enter data prompted by program.

5.1 Cycle burnup (EFPD) 5.2 EquilibriumPower(%)

5.2.1 Enter last power level maintained until xenon equilibrium l reached.

6 Select option N - to key in a new profile.

7 Enter the new input profile for each power level and/or power plateau l expected during the transient. No blanks - use zero (0) instead.

7.1 Percent power (%) < ENTER > (Target power level) l 7.2 Ramp Time (Hours) < ENTER > (Time to reach target power level) 7.3 Plateau Time (Hours) < ENTER > (Time remaining at target power level) 7.4 < ENTER > (After last data entry for each power level, duration of ramp and time at plateau - <NTER>< ENTER >) '

8 Select option E - to evaluate the xenon transient.

9 Answer N to option Do you want the xenon profile consisting of 289 lines printed to the screen?

10 Answer Y to option Would you like a hardcopy of this xenon profile?

11 Answer option Would you like to run another xenon case?

12 Exit Reactivity Calculator.

1 l

l l

1 J7-5.wS1 ATTACHMENT 16 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 % PAGE 90 0F 100 ATTSCHMENT17 TCN h tN, BORATION/ DILUTION CALCULATION y 1 Select Reactivity Calculations from the applicable PC menu. 0 2 Select Boration/ Dilution from submenu.

lN 3 Select Unit.

4 Enter data prompted by program:

4.1 Present RCS boron concentration (ppm) 4.2 Desired RCS boron concentration (ppm) 4.3 RCS T,ys (deg F) 4.4 PZR level (%)

4.5 Do you want to divert? (Y or N) 4.6 BAMU concentration (WT%) [ requested only if boration required]

5 After results displayed, answer Y to option Would you like a printout of this calculation?

6 Answer Y to option Would you like to run another case?

7 After all necessary cases have been run, answer N to option Would you like to run another case?

l l

l 1

l l

l J7-6.wS1 ATTACHMENT 17 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 91 0F 100 ATT3CHMENT18 TCN h S h BORATION/ DILUTION SCHEDULE The Boration/ Dilution Schedule provides the anticipated requirements for controlling the expected power maneuver. Power and ASI control requirements shall override this schedule as necessary to maintain the appropriate limits.

Each time point assumes the conditions for the prior time points have been maintained and a significant reduction in accuracy will occur following deviations from the schedule. Therefore, it is important to attempt to maintain these guidelines as closely as possible.

^ "

AEE TiL*E ' C*[A 08 RC8 C g ( GA .

RAT 7 TalNITI AL T+1 T+2 T*3 T+4 T+5 T+6 T*7 T+8 T*9 T+10 T*11 T+12 T+13 T.14 T*16 T+16 l

T+17 T+18 T+19 T+20 T+21 T*22 T+23 T*24 DISPOSITION: File per S0123-0-32.

J7-6.wS1 ATTACHMENT 18 PAGE 1 0F 1

1 NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 l UNITS 2 AND 3 REVISION 6 PAGE 92 0F 100 ATTr)CHMENT19 TCN[NU RAPID AND ACCELERATED DOWNPOWER BORATION/CEA INSERTION DETERMINATION UNIT DATE TIME PERF. BY l 1.0 PREREQUISITES INITIALS l 1

1.1 Verify this document is current by checking a controlled l copy or by using the method described in S0123-VI-0.9.

NOTES: 1. The values required in this attachment may be obtained from Reactor Engineering.

2. Data supplied by Reactor Engineering shall be in the format specified by S023-V-13 with a copy of the transmittal affixed to this Attachment.

2.0 BORATION VOLUME DETERMINATION 2.1 Record the following:

1 Present EFPD Full Power Boron Concentration ppm NOTE: In the following steps, the subscripts 5, 10, 15....etc. indicate the total expected power level decrease for the rapid / accelerated downpower transient.

2.2 Detennine Power Defect (PD) for expected rapid / accelerated downpower transients.

2.2.1 Determine the current 100% power defect based on ,

Core life (EFPD) from the OPS Summary Physics Data '

Book figure 5.4.

100% Power Defect, PDgp = % ak/k l ATTACHMENT 19 PAGE 1 0F 5

s NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 93 0F 100 1 ATT3CHMENT19 TCN b ~ 1 l 2.0 BORATION VOLUME DETERMINATION (Continued) 2.2.2 Determine the power defect for the expected downpower transients:

5% decrease, PD3 = 0.05 x PDur, =

% AK/K 10% decrease, PD33 = 0.10 x PD HrP =

AK/K 15% decrease, PB33 = 0.15 x PDurp =

% AK/K 20% decrease, PDro = 0.20 x PDug , *

% AK/K 25% decrease, PD2 s = 0.25 x PD HrP =

AK/K 30% decrease, PD3a = 0.30 x PDurp =

% AK/K 35% decrease, PD33 = 0.35 x PD,,, =

% AK/K 40% decrease, PD4a = 0.40 x PD,,, =

% AK/K 45% decrease, PD43 = 0.45 x PD HrP =

AK/K 50% decrease, PD3a = 0.50 x PD ure * % OK/K 2.3 Record Inverse Boron Worth as a function of EFPC:

(OPS Figure 3.1)

Inverse Boron Worth : pps/% AK/K 2.4 Calculate the required change in boron concentration (40 ) using Power Defect (PD) [ Step 2.2.2] and Inverse Baron Worth (3IBW),

[ Step 2.3]:

(Step 2.2.2) x (Step 2.3) l PD 3 x IBW = AC 33 ppm PD 3a x IBW = AC33o ppm PD 33 x IBW = AC 313 ppm PD2o x IBW = ACa2o ppm !

PD 23 x IBW = AC ars ppm l

PD 3a x IBW = AC 330 ppm PD 33 x IBW = AC 333 ppm PD 4a x IBW = AC3 o ppm PO 43 x IBW = AC3,3 ppm PD 3a x IBW = AC eso ppm j ATTACHMENT 19 PAGE 2 0F S

s l NUCLEAR ORGANIZATION OPERATING' INSTRUCTION S023-5-1.7

! UNITS 2 AND 3 REVISION 6 PAGE 94 0F 100 l

ATT/)CHMENT 19 TCNb~3d .

2.0 B0 RATION VOLUME DETERMINATION (Continued)

NOTE: Calculation of the adjusted boron concentration provides i data needed for the computer SONGS 2/3 Boration/ Dilution l Program.

2.5 Calculate adjusted Boron concentration (C,,) using change in boron concentration required (AC,), (Step 2.4) and initial boron concentration (AC,,), (Step 2.1):

Adjusted Boron (Step 2.4) + (Step 2.1) Concentration AC,3 ppm + C , ppm = C,f, ppm AC,1o ppm + Cai ppm = C,fta ppm ACat , ppm + Cai ppm = C ,13 ppm AC sza Ppm + C ai ppm = C arza ppm AC 82s ppm + C,, ppm = Car 2s ppm AC,3o ppm + Cai ppm = C arso ppm AC,33 ppm + C ai ppm = C ,33 ppm AC,,o ppm + C , ppm = C ina ppm AC,43 ppm + C ai ppm = C ,43 ppm AC asa ppm + C ai ppm = 0,,,o ppm 2.6 Calculate gallons of boration required to adjust Baron concentration RI per SONGS 2/3 Boration/ Dilution Program, or 5023-3-2.2 for: lC 2.6.1 Indicate BAMU Tank and Boron concentration on which calculations are based:

T-071 C.

= PFM

, T-072 C a =

PPM ATTACHMENT 19 PAGE 3 0F 5 i

NUCLEAR ORGANIZATION OPERATING INSTRUCTION 5023-5-1.7 UNITS 2 AND 3 REVISION 5 /, ~ PAGE 95 0F 100 ATT$CHMENT19 TCN WC 2.0 B0 RATION VOLUME DETERMINATION (Continued) 2.6.2 Boration required:

AC ,3 =

gal.

AC fio =

gal.

AC,,is =

gal.

A Ca rgo =

gal.

AC ar23 = gal.

AC,,3o = gal.

AC af33 = gal. !

AC sf4a = gal. ;

AC,f45 =

gal.

Ac er3a = gal. l 1

3.0 POWER DEFECT EQUIVALENT CEA WORTH DETERMINATION 3.1 Determine Group 6 CEA positions based on CEA worth equivalent to'the l

power defect (Step 2.2.2) for the expected rapid / accelerated downpower transients using OPS Physic Summary book Figure 4.1.

Enter N/A if required position for Group 6 below 75".

CEA Group 6 worth = PD 3 = " withdrawn CEA Group 6 worth = PDo i

=

" withdrawn CEA Group 6 worth = PDis =

" withdrawn CEA Group 6 worth = PDzo = " withdrawn CEA Group 6 worth = PD,5 = " withdrawn CEA Group 6 worth = PD 3a =

" withdrawn CEA Group 6 worth = PD 33 =

" withdrawn CEA Group 6 worth = PDa 4

" withdrawn CEA Group 6 worth = PD 45

" withdrawn CEA Group 6 worth = PD 3a =

" withdrawn ATTACHMENT 19 PAGE 4 0F 5 l l

i i

l

f

.. .no.ve . . . . . . . . . , , , .

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 96 0F 100 ATTACHMENT 19 TCH b2~ $bf 4.0 UPDATE ATTACHMENT 20 4.1 Transfer the BAMU tank selection from Step 2.6.1, boration volumes from Step 2.6.2 and Group 6 CEA positions from Step 3.1 to 1

Attachment 20. Rapid and Accelerated Downpower Boration/CEA

Insertion Guidelines.

i i

1 ,

COMMENTS lI P

PERFORMED BY: DATE/ TIME:

i

INDEPENDENTLY

VERIFIED BY: DATE/ TIME: If i

' *C I

Il REVIEWED BY: DATE/ TIME:

SR0 Ops. Supv.

i FILE DISPOSITION: File per S0123-0-32.

J7-6.W51 ATTACHMENT 19 PAGE 5 0F 5

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.'

UNITS 2 AND 3 REVISION 6 PAGE 97 CF 100 ,

ATT/)CHMENT20 TCN h '

RAPID AND ACCELERATED 00WNPOWER B0 RATION /CEA INSERTION GUIDELINE _S_

UNIT FOR WEEK OF

% POWER LEVEL DECREASE BORATION ONLY GRoVP 6 CEAs ONLY (BASED ON BAMU T- ) (N/A BELOW 75") [1]

5% GAL "

lo% GAL "

15% GAL "

20% GAL "

25% GAL "

I l

30% GAL " l 35% " l GAL l 40% GAL "

45% GAL "

50% GAL "

1

[1] Technical specification 3.1.3.5 Transient Insertion Limits require tracking below LTSSIL per 50123-0-42 and restoration to greater than 120" withdrawn within required time frames, j Recommended method of perfomina rapid / accelerated downpower maneuvers:

Refer to main body Section 6.8.3.

1) If a combination of CEA insertion and boration is to be used, then:

a. Initiate boration of the required volume.

b. After boration is initiated, then make initial 5% or 10% power decrease using Group 6 CEAs only.

2) Make additional power decrease on Group 6 CEAs (maximum insertion 75") E boration only (gallons based on percent pewer decrease) g combination of CEAs and boration (for example, 20% by boration and lo% by CEAs for total 30% decrease).

Rapid downpower transients are expected to reach the target power level in less than one hour using turbine controls to establish the rate of power decrease and Group 6 CEAs and/or boron for reactivity and RCS temperature control.

The boration volume should be injected in a batch mode as rapidly as possible and is calculated for no CEA insertion. Boration volume may require adjustment if Group 6 CEA positions are adjusted due to ASI control considerations.

Allow RCS cold leg temperature to drift above the control band for short periods of time provided it can be reduced to less than 558aF within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months as required by Technical Specification 3.2.6.

Varying RCS temperature and CEA withdrawal / insertion are used to compensate for xenon buildup and small reactivity changes to maintain the target power level.

FILE DISPOSITION: Maintain in "In-Use" Procedure book o_r post on Control Board.

J7-6.W51 ATTACHMENT 20 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 n j, PAGE 98 0F 100

/

ATT3CHMENT21 TCN V dV EOC UNIT SHUTDOWN PAR'4 METER EXPECTATIONS EXAMPLE Included in the following table are selected parameters that were recorded during the Unit 2 E0C JCycle 7) shutdown from 75% Power to Turbine /Rx Trip at approximately 20% Power. This shatdown occurred on Feb. 10/11 1995. This table ws developed for use as a pre-shutdown tailboard tool to show a,n example of some plant parameter expectations during a EOC shutdown.

l The table time span is from 2112 - 2/10/95 to 0018 - 2/11/95.

The turbine was tripped at 0019 and the Reactor was tripped at 0021 - 2/11/95.

TIME CV9 COO CV9198

^

n .

T112CA MWe 2112 75.0 75.4 76.3 .0 8 .089 140.5 150 150 551.6 835 l 2140 75.0 75.2 74.7 - A66 .064 129.2 150 150 550.5 824 i

2155 70.0 67.2 66.3 .007 .008 115 126 150 549.9 727 2210 65.0 61.6 64.3 .007 .007 115 126 150 549.6 700 2225 60.0 62.0 61.7 .010 .008 115 123.8 150 549.4 660 l

2240 55.0 59.0 58.5 .008 .005 115 122.3 150 549.3 631 2255 50.0 57.0 56.2 .014 .002 115 120 150 549.7 560 !

2310 45.0 51.1 50.2 .006 .0001 115 115 150 549.5 504 l 2325 40.0 45.1 43.9 .0055 .0001 106 115 150 549.5 433 2340 35.0 36.7 35.0 .007 .011 85 109 150 549.1 329 2355 30.0 33.3 32.3 .013 .004 85 10757 150 549.0 241 0010 25.0 28.1 25.3 .006 .021 85 , 85 150 548.0 200 l 0018 20.0 19.6 18.1 .007 - 009 85 85 145 548.0 140

[1] Planned Power decrease, (For this shutdown it was 18-20%/Hr.)

Additional Information:

CV9000 -

PHS PID, Plant Power CPC 171 - CPC PID, Calibrated hautron power CV9198 - PMS PID, COLSS ASI CPC 187 - CPC PID, Hot Pin ASI l i

T112CA -

Loop #1 T-Cold J7-6.W51 ATTACHMENT 21 PAGE 1 0F 1

NUCLEAR ORGANIZATION OPERATING INSTRUCTION S023-5-1.7 UNITS 2 AND 3 REVISION 6 PAGE 99 0F 100 ATT3CHMENT22 TCN NSh GENERATOR CAPABILITY CURVE 1000 _

- co , r.

} o o-69

pg,oEf. hglO 800 e2 . : .. %; ,g .... * ~

-so % ~3 **ath .

600 E

a.

90.j i LAC [

/

q

'g (eOOST) 400

\.

h h '

I g... . - -

i / g s, . i

=

200 - -

j \, M. ((OE8,, ems.TENL t r

.it f: so too sbo 8bo "" * '"

0 ;

,,,y,t ,gs,,, ;,,ve; t i i

_ _ _ _._ _ _ _ y , _: :::_., g r_- ,- _- ,,. _ _._

_ e i P P " E n EXC(TEO CIMIT; i e I E , I Il 3

-200 . . mr!. 4. .

il]!

RORbGCGC. TGD7 i .

s i: -

.N 3 .

//

-400 + '

Ts4610"!

,c,j ~'**' " '

1

(o os To o' a

-600 ._- _

E

_____':"__T."'""_Y_*..............___._ "____"_'"__-* .____ _-l LEAD _

i __ 1 Ceuco :

- c6te simND TIME [0ELAh

-800 ;- - -

= .

. l

~

-1000 ' #

' ~

. . . t h_ '

-1200 h- ' , . . . .. ' , .

. : '.^ ~?ekdarj,mileteubTdiCx_4 i_ (TWEE tYCLE': TIME DELX,Y)

-1400 ATTACHMENT 22 PAGE 1 0F 2

I NUCLEAR ORGANIZATION OPERATlNG INSTRUCTION S023-5-1.7 !

UNITS 2 AND 3 REVISION 6 f PAGE 100 0F 100 ATT4CHMENT22 TCN V, --

EXPLANATION OF CURVE 1

1. The two vertical lines (corresponding to generator hydrogen pressures I

of 60 and 68 psig,) at their point of intersections with the solid i horizontal line signify the MW output from the Generator with the !

Turbine The 1180operating at its

)W figure read rated from the 100%

vertical load and attoitsthemaximum line (farther right capability).

in the capability curve represents the maximum Generator MW output, limited not by the Generator' operating limits, but by Turbine limitations.

2. The dashed curved lines represent the maximum MVA loadings of the Generator. The Generator may be operated at rated MVA 1313 MVA at 68 psig h,ydrogen pressure; 1251 MVA at 60 psig Hydrogen pre (ssure between the limitsfactor power of ratedleading) power factor (0.9 power factor lagging)and

3. The Generator design fully allows the Generator to be operated in the region between the solid vertical lines and the dashed curved lines.

Generator operations in this region are governed by Turbine output limitations, and by restrictions imposed b Generator power factor and NVAR leadings. y SCE System Operations on NOTE: For example: If SOB-17 limits Generator MVARs to less than 200 MVAR boost, the Generator limits for MW are as follows:

0 60 psig Hz = ~1234 MWe gross is the limit O 68 psig Hz = ~1299 MWe gross is the limit END OF ATTACHMENT l

J7-6.W51 ATTACHMENT 22 PAGE 2 0F 2

ML20112C182

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PD0

PD.,

C EA.,

% AK/F AX E.14 = XE.13 - XE.i,

XE+21 - XE+rz % AK/K AX E.,3

" withdrawn CEA Group 6 worth = PD 45

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