ML17329A195

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Summary of 910905 Meeting W/Util Re RPS Instrument Replacement Effort & Whether to Change TS for Plant. Viewgraphs Encl
ML17329A195
Person / Time
Site: Cook  
Issue date: 09/30/1991
From: Colburn T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-80119, TAC-80120, NUDOCS 9110040175
Download: ML17329A195 (44)
v • d • e


Text

Docket Nos.

50-315 and 50-316 September 30, 1991 LICENSEE:

INDIANA MICHIGAN POWER COMPANY FACILITY:

D.

C.

COOK, UNITS 1 AND 2

SUBJECT:

MEETING

SUMMARY

RELATED TO D.

C.

COOK NUCLEAR PLANT, UNITS 1

AND 2 RPS INSTRUMENT REPLACEMENT (TAC NOS. 80119 AND 80120)

On September 5, 1991, the staff met with Indiana Michigan Power Company (the licensee) to discuss concerns related to the subject replacement effort. During the course of the staff's review of this replacement, questions arose as to whether a change to Technical Specification (TS) for the D. C.

Cook Nuclear Plant would be required to support the replacement.

Specifically, the staff questioned whether note 1 which describes the over-temperature delta T equation would require change because of a change in the related time constant, tau sub 2, which would be affected by the replacement.

The licensee and their contractors provided convincing arguments showing that the equation in question was a calculated value which bounded the existing equipment response and will be similarly applied to the replacement equipment.

The values calculated by the overtemperature delta T trip function curve were used in the accident analysis and do not change as a result of the replacement effort.

The replacement effort changes the equipment response and thus may change the amount by which the licensee remains conservative with respect to the calculated trip function, but not the curve itself.

Therefore, no TS change is required.

The licensee agreed to consider whether a change to the basis may be appropriate to better explain the relationship between the TS trip setpoint and the actual equipment response.

This would be required to support the change and would presumably be administrative in nature.

A copy of the licensee s slides is provided in Enclosure 1.

A list of attendees is contained in Enclosure 2.

Original signed by PDR ADOCH, 050003i5 P

PDR

Enclosures:

As stated cc w/enclosures:

See next page DISTRIBUTION h dp g

Timothy G. Colburn, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation CE~ COlI'V

  • SEE PR VIOUS CONCURRENCE NAME
TColburn:sw DATE

'9/ga/91

SNewberry
9/26/91

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PY Document Name:

DC COOK MEETING

SUMMARY

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,Mr. Gene Fitzpatrick

'Indiana Michigan Power Company Donald C. Cook Nuclear Plant CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.

Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvil le, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 Mr. S. Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

OOK NUCLEAR PLANT Sridgman, Michigan

INTRODUCTION BECKY GREEN AMERICANELECTRIC POWER SERVICE CORPORATION SEPTEMBER 6, 1991

JUSTIFICATION FOR NOT NEEDING A TECH SPEC CHANGE INTRODUCTION BECKY GREEN - AEP EXISTING OTQT LOOPS DAVE SCHMADER AEP MOD 30 IMPLEMENTATION OF OTQT JEFF ARPEN

- ABBCE REVIEW OF SETPOINT TIME CONSTANTS VANCE VANDERBU RG -

AEP TECHNICAL SP ECIFICATION CONFORMANCE STAN FARLOW

- AEP CON CLUSION

,. BECKY GREEN

- AEP

SCOPE OF REPLACEMENT

EQVATION FOR QVERTEMPERATVRE DELTA T SETPOINT AS DEFINED IN TECHNICAL SPECIFICATIONS Overtemperature bT < hT

[Kl-K2[(1 + rlS)/(1 + r S)J(T-T')+K (P-P')-f (hI)J o

1 2

1 2

3 1

Where:

hT Indicated hT at RATED THERMAL POWER 0

0 Average temperature, F

- Indicated T

at RATED THERMAL POWER less than or equal to 576.0 F

pt 1 +~>R 1+ r2S 1'

- Pressurizer

Pressure, psig

- 2235 psig (indicated RCS nominal operating pressure)

- The function generated by the lead-lag controller for T

dynami.c compensation avg-Time constants utilized in the lead-lag controller for T r.

= 28 secs, 2

= 4 secs.

avg 1

F2 Laplace transform operator

EXISTING OTQ T LOOPS DAVE SCHMADER AMERICANELECTRIC POWER SERVICE CORPORATION SEPTEMBER 5, 1991

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EQUATION FOR OVERTEMPERATURE DELTA T SETPOINT AS DEFINED IN TECHNICAL SPECIFICATIONS Overtemperature bT < hT (Kl-K2f(1 + rlS)/(1 + r2S))(T-T')+K3(P-P')-fl(bl)j Where.'bT0

- Indicated hT at RATED THERMAL POWER 0

Average temperature, F

- Indicated T

at RATED THERMAL POWER less than or equal to 576.0 F

g pt xR 1 + r2S rl, r2

- Pressurizer

Pressure, psig

- 2235 psig (indicated RCS nominal operating pressure)

The function generated by the lead-lag controller for T

. dynamic compensation avg Time constants utilized in the lead-lag controller for T

rl

= 28 secs, 2

4 secs.

avg' r2 Laplace transform operator

TRANSFORMATION OF THE OTQT SETPOINT EQUATION INTO THE FORM THAT IS USED BY THE FOXBORO H"LINE EQUIPMENT MULTIPLY 80TH SIDES OF THE TECH SPED EQUATION SY RT i QQ1I i K1-K2{(1+Tj)/(1+Tj)){T-T')~KS(P-P')-f(kl)

ATo MULTIPLY BOTH SIDES OF THB BQUATIOH BY 100:g OTh T 100 c 100)K1 "K2((1RP/(1+pl)(T-T')<KS(P-P')-f($)j To

RECOGNIZING THAT {OT&T)/&ToIS EQUIVALENT TO PERCENT OF FULL-POWERQT, THIS EQUATION CAN BE WRITTEN AS:

% PWR s 100(K1-K2{(1Ti)/(1Ti))(T-T) KS(P-P )-r{LQ)

THE FORM THAT IS UTILIZED BY THE FOXBORO H-LINE SETPOINT GENERATOR.

MOD 30 IMPLEMENTATION OF OT DT JEFF ARPEN ABB CE SEPTEMBER 5, f99)

D.C.COOK REACTOR PROTECTION SYSTEM INSTRUMENTATIONREPLACEMENT FOXBORO H-UNE (EXISTING) SYSTEM VS. MOD 30

  • EXISTING SYSTEM IS ANALOGBASED AND IS COMPRISED OF VARIOUS MODULES TO PERFORM DISCRETE FUNCTIONS
  • MOD 30 SYSTEM IS DIGITALBASED AND PERFORMS FUNCTIONS THROUGH USE OF STORED ALOGORITHMS

~

EXISTING SYSTEM (ANALOG)IS CONTINUOUSLYADJUSTABLE

  • MOD 30 SYSTEM (DIGITAL)IS ADJUSTABLE IN STEPS

OC COOK, EXIS) lflG OTAI'RIF EIEII 55545I alit lfIER Ks I lloi C

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SPEC. I 5 ~ LaPLACE TRAHSFNIM CPERaltWI t Ibrl ~ 0-I801 POlfR PEHALfr K -Kl.Tl.f CTCLE OEPEIIDEHT

DC COOK TAYLOR MOD 30 OThT thtr FIIIICI. 9900) I bf~lg5 10-1505 PthIERI tth/fh IIALF Lh'IE Phlrfh... f P f R IIALf - -I PRE SSllh1 ff8 Vhf S)th:E l)00-2500 P5)0 OlbLSE}+O}N} ~0-)5~11) i t)IIPUI k)-k)f)5)ttf f'I) k)IPS+')

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CAL SPECIFICATIONS

  • HOW DOES AEP ASSURE THAT ITS HARDWARE SATISFIES TECHNICAL SPEClFICATION REQUIREMENTS'
  • SPECIFICALLY HOW DID AEP ADDRESS ig AND.I~ IN THE OTQT SETPOINT FORM ULA'?

COMMENTS ON THE EXISTING INSTRUMENTATION I 1 ANDY"2 CANNOT BE EXACTLY INPUT TO THE EXISTING EQUIPMENT

  • RATHER 2 AND+11 J 2 LEAD GAIN ARE ITERATIVELY TUNED TO THE TECHNICAL SPECIFICATION TRANSFER FUNCTION OF THE OT/NT SETPOINT FORMULA.

WE BELIEVE THIS TO BE CONSISTENT WITH INDUST RY P RACTICE. FOR EXAMPLE A WESTIN6 HOUSE "PROCESS CONTROL SYSTEMS SCALING MANUAL" REGARDING THE CALIBRATION OF LEAD-LAG, RATE-LAG, AND FILTER UNITS STATES: 5-2

Thaedare, i,t ia reeoaaaaekal chat aaeaai the napoaaaa be worked ouc aeaeNWy foi the des&ed value uaBg the eyethnae ak t1guree 5-i,,

I 2 y 406 5 ) ~ The teSit ~ bo L Set M OxpeccsEL vs'504 . EQT Conc.

  • THEREFORE, THE TECHNICAL SPECIFICATIONS MUST BE VIEWED AS A LIMITING FUNCTION WHICH SAFETY ANALYSES HAVE USED AND TO WHICH THE HARDWARE MUST BE CONSERVATIVELY TUNED.
  • ALLOWANCES FOR INSTRUMENTATION ERRORS ARE MADE IN THE DETERMINATION OF TECHNICAL SP ECIF ICATION SETPOINTS
  • FURTHERMORE, IN VIEW OF THE INEQUALITY IN THlS AND ALL OTHER REACTOR TRIP SETPOINTS, THE HARDWARE CAN BE TUNED CONSERVATIVELY

TO DO THIS AEP CONSIDERED THE RESPONSE OF THE LEAD LAG MODULE TO A LINEAR INPUT -tn2 TY MODULE OUTPUT ~ K(t+5l~)(1-e )) 480 540 aio-400 g 0 lK sao 5CO 5iO 520 500 10 12 14 16 18 20 c 0 W 20 1 8 1+2 o I 1O ta 1i 1a 18 TZllg (SEC) Fig re S.S-SA Rod ethdra a at~ Core Average Teuperature and GNBR Versus Time for Full Power, 80 PN/Sec insert~ 1 Rate, Maximum Reactivity Feedback Too 440 LRO t Sso 5u 540 540 520-500 0 25 5O FS lOO 125 150 LTS 20O 225 2SO ZFS 300 32S 35O 375 F00 a.a-2 Ct CZ 2 20 1 8 1 2 0 zs so m 1oO 1ZS rSa rrS ace ass 2so mrs mo sas 3So ~ ~oo TIVE t SBC1 Figure 8.3-8A Rod Nthdrawal at Power Core Average Temperature and {NBR Versus Time for Full Power, 4 PCN/Sec Insertion Rate, Naximu01 Reactivity Feedback 700 610 660 440 o 670 600 R 5jo L 560 CI $40 TCOLD $20 $ 00 0 10 20 30 40 $ 0 60 70 10 90 100 Zoo b40 600 Sao Sbo $40 520 500 0 >0 70 30 40 .50 Qt W fO 90 100 TlnE ~ SEC i Figure 8.3-28A Loss of Load Loop and Core Average Temperatures Versus Time for Ninimum Reactivity with Pressurizer Spray and PORVs Revision 1 700 COO C00 R Sio cL 5 CO 8 540 520 500 0 10 20 80 40 Sl 40 70 Io %0 10G TGO Ceo-C<0 tZ Seo o sco 540 Sao 5&0 0 !0 20 30 +0 SO Co 'FO IO %0 100 T111E I SEC ) Figure 8.3-31A Loss of Load Loop and Core Average Temperatures Versus Time for Maximum Reac.ivity Feedback with Pressurizer Spray and PORVs AN EXAMPLE OF EXPECTED

RESPONSE

UNIT 2 CYCLE 7 PARAMETERS

CONCLUSION AEP BELIEVES IT WILL BE IN LITERAL COMPLIANCE WITH THE OTQT REACTOR TRIP TECHNICAL SPECIFICATION IN ITS CURRENT FORM.

TECHNICAL SPECIFICATIQN CONFORMANCE STAN FARLOW AMERICANELECTRIC POWER SERVICE CORPORATION SEPTEMBER 6, 1991

TECHNICAL SPECIFICATION CONFORMANCE AREAS OF POTENTIAL IMPACT

  • RESPONSE TIMES
  • SETPOINT ACCURACIES AND ALLOWABLES
  • SURVEILLANCE INTERVALS
  • SURVEILLANCE TESTING
  • INTERLOCK LOGIC
  • APPENDIX R

GENERAL NEW EQUIPMENT CONSIDERATIONS

~ IMPROVED ACCURACY

~ REDUCED DRIFT

~ SLIGHTLY SLOWER RESPONSE TIME

~ LIMITATIONSON CONFIGURATION

TIME RESPONSE FOR REACTOR TRIPS OVERTEMPERATURE Q T PRESSURIZER PRESSURE LOW 6.0 c 2.0 1.42 MARGIN

  • AVAILABLE (SECONDS}

(SECONDS 1.32 PRESSURIZER PRESSURE HIGH 2.0 PRESSURIZER LEVEL HIGH c 2.0 LOSS OF RCS FLOW (BOTH 1

5 2 LOOPS}

c 1.0 STEAM GENERATOR LO-LO LEVEL c 2.0 1.45 1.47

.44 1.08

  • MARGIN TO TECH SPEC TIME FOR SLOWEST CHANNEL IN EITHER UNIT 1

OR 2

RESPONSE TIME VERIFIED DURING FACTORY ACCEPTANCES TESTING AND AFTER INSTALLATION

SETPOINT ACCURACY AND ALLOWABLEVALUES ACCURACY COMPONENT RACK CALIBRATIONACCURACY MEASUREMENT 8 TESTING EQUIPMENT RACK ENVIRONMENTALEFFECTS RACK DRIFT RACK COMPARATOR SETTING CHANGE IMPROVED AT LEAST.19'o NO CHANGE IMPROVED AT LEAST

.39'MPROVED AT LEAST.69o IMPROVED AT LEAST.2'

k P

n c

cowcLusio~

WE BELIEVE A T/S CHANGE IS NOT NEEDED BECAUSE:

THE INSTRUMENTATION IS CONSISTENT WITH THE DESIGN BASIS METHODOLOGY OF THE OPDT AND OTQT PROTECTION THE NEW INSTRUMENTATION WILL SATISFY T/S REQUIRMENTS FOR

RESPONSE

TIMES, SETPOINT ALLOWANCES, SURVEILLANCE INTERVALS AND ALLOWABLE VALUES

Enclosure 2

MEETING WITH AMERICAN ELECTRIC POWER SERVICE CORPORATION September 5, 1991 NAME ORGANIZATION PHONE T. Colburn G. Garten Vance Vanderburg Chris Vertes Bert Svensson Charles Brinkman Jeffrey Ardin Martin Ryan Michael Barfelz Scott Newberry Bill Long Steve Brewer Becky Green Dave Schmader Stan Farlow Larry Kopp Ed Kendrick C. Carpenter NRC/NRR/PD31 NRC/NRR/SIC 8 AED/NFA Westinghouse/Licensing ISM Cook Plant ABB/CE ABB/CE ABB/CE IMP/Cook Plant NRC/NRR/SIC B NRC/NRR/PD31 AEP/NS&L AEP/NS5L AEP/IKC AEP/ISC NRC/NRR/SRXB NRC/NRR/SRXB NRC/NRR/PD31 301-492-1341 301-492-0931 614-223-2039 412-374-5683 616-466-2405 301-881-7040 203-285-3258 203-285-9281 616-465-5901 301-492-0821 301-492-3026 614-223-2020 614-223-2082 614-223-1921 614-223-1994 301-492-0879 301-492-0891 301>>492-1347

0 i ~

~la,.

~.a

"- DISTRI BUTION FOR MEETING

SUMMARY

DATED September 3O

) ggi Facility: D. C. Cook Qo,F~lFil~

NRC PDR Local PDR T. Murley F. Miraglia B. Boger J. Zwolinski L. Marsh T. Colburn P. Shuttelworth OGC E. Jordan G. Garten S. Newberry B. Long L. Kopp E. Kendrick C. Carpenter ACRS (10) 12-G-18 12-G-18 15-B-18 MNBB-3302 P-315

h aD p.

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