ML19312D119

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Notification of 800325 Meeting W/Util in Bethesda,Md to Discuss Instrumentation & Control Sys W/Emphasis on Instrumentation Upgrade Package.Draft FSAR Questions Encl
ML19312D119
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 03/04/1980
From: Burwell S
Office of Nuclear Reactor Regulation
To: Baer R
Office of Nuclear Reactor Regulation
References
NUDOCS 8003210094
Download: ML19312D119 (11)
v • d • e


Text

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s n Meeting Notice" Docket File R.'Tedesco' SYNRCPDR-S. Pawlicki Local PDR F. Schauer-

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- X.LKniel.

TLWR #2 File T.:Novak rNRR' Reading-Z. Rosztoczy H. Denton -

R. Bosnak 1E.-Case R. Satterfield H.EBerkow W. Butler-

R. Mattson F. Rosa

.R.

DeYoung V. - Fbore D. - Mull er; W. Kreger

D. Ross M. Ernst
D. Vassallo' R. Denise

. S...Varga R. Ballard.

D. Skovholt:

B.-Youngblood i

F. Williams-W. Regan J. Stolz G. Chipman

10. Parr-R. Houston JL.' Rubenstein J.' Collins P.~. Collins T. Murphy T. Speis LWi-Haass~

G. Lear M. Spangler 4C. Heltemes-V. Benaroya

'ACRS(16)-

R. Jackson L~ Crocker.

L. Hulman.

Project Manager

. S. Burgwll H. Ornstein Attorney, ELD - i4. Ulman J. LeDoux, IE IE(3)

Principal Staff

Participants:

SD(7)

T. Dunning

'J.

Lee L. Soffer

.J. Knight OPA

.S. Hanauer Region IV 0ffice

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20555 upR 0 4 M Docket Nos. 50-445 and 50-446 MEMORANDUM FOR: Robert L. Baer, Chief, Light Water Reactors Branch No. 2, DPM FROM:

_ S.- B. Burwell, Project Manager, Light Water bet 9rs Branch

-No. 2, DPM

SUBJECT:

. MEETING WITH TEXAS UTILITIES GENERATING COMPANY (TUGCO) 04 DRAFT QUESTIONS ON INSTRUMENTATION AND CONTROL SYSTEMS F0?

COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2

.DATE & TIME:

Tuesday, March 25,1980 - 9:00 a.m.

~

L0 CATION:

Phillips Building, Room P-500 7920 Norfolk Avenue Bethesda, Maryland

~ PURPOSE:

To discuss the instrumentation and control system with emphasis on the Comanche Peak " instrumentation upgrade

-_ package. The enclosed " draft FSAR questions" will be used as the agenda for this discussion.

-PARTICIPANTS:

TEXAS UTILITIES GENERATING COMPANY (D. Woodlan, et al)

WESTINGHOUSE (L. Campbell, J. Mesmeringer, D. Duminicis)

GIBBS AND HILL-(D. Castro)

NRC - STAFF (S. Burwell, DPM; T. G. Dunning, DSS)

NRC - CONSULTANTS (I. Charak, ANL, G_

Popper, ANL)

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,vc S. B. Burwell Light Water Reactors Branch No. 2-Division of Project Management TEnclosure.

Draft-FS/R-Questions

- ces w/ei closure:

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.See nyxt pages -

Pr.R.'J.(Gary-

- MAR 041990

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'Mr. R. J. Gary Executive.Vice President and' LGeneral Manager-9 Texas Utilities Generating Company 2001. Bryan Towers

-Dallas, Texas: 75201 Nicholas S. Reynolds, Esq.

Debevoise & Liberman 1200 Seventeenth Street Washington, D.C.

20036 Spencer C. Relyea, Esq.

Worsham, Forsythe & Sampels 2001 Bryan Tower Dallas, Texas 75201' Mr. Homer C. Schmidt Project Manager - Nuclear Plants Texas Utilities Generating Company

-2001 Bryan Tower Dallas, Texas 75201 Mr. H. R. Rock-4 Gibbs and Hill, Inc.

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-393 Seventh Avenue New York, New York -10001 Mr. G. L. Hohmann-Westinghouse Electric Corporation P. 0.. Box 355 Pittsburgh, Pennsylvania 15230 Richard W. Lowerre, Esq.

Assistant Attorney General Environmental-Protection Division P. 0. Box 12548, Capitol Station Austin,. Texas -78711 Mrs..Juanita Ellis, President.

Citizens Assocletion for Sound

Ener gy -

.1426 South Polk Dallas', Texas 75224 Geoffrey M. Gay, Esq.

. West 1 Texas Legal Services

.406.W.T. Wagccner Building

^ 810 Houston ',treet Fort Worth, Texas 76102 e

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p,, p, g, g,,y MAR o 41980 ye, "Ms.~ Nancy'Holdam Jacobson

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Citizens for Fair Utility Regulation
1400 Hemphill
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-Fort Worth, Texas 76104 Mr. Richard Fouke

-1668-B Carter Drive

Arlington, Texas 76010 Resident Inspector / Comanche Peak Nuclear Power Station c/o U. S. Nuclear Regulatory Commission P. 0. Box'38 Glen Rose, Texas :70642 Mr. ' Ira Charak

' Argonne National Laboratory Building 301 9700 South Cass Avenue Argonne, Illinois 60439 4

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ENCLOSURE.

COMANCHE PEAK STEAM ELECTRIC' STATION

'FSAR QUESTIONS 1..

The following s;gnificant differences have been. identified to exist-s-

between. the William B. - McGuire Station reference design Reactor LTrip System (RTS) and'the' Comanche Peak' Steam Electric Station-(CPSES) RTS.- CPSES uses:
a.. In-line fast response thermowells for the T measurement.

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.b.

Overpower and overtemperature N-16 trips.

c.

Four segment power. range neutron' flux detectors.

d.

Transit time N-16 flowmeter.

These differences are a result of the so called " instrumentation upgrade package." Describe in detail the total upgrade package hardware to be specifically installed on CPSES and explain the A

safety implications of these system changes as they relate to GDCs, S

LCOs, RGs, BTPs, and IEEE Standards.

l 2.

There are several instances in Section 6 of the FSAR, for example i

subsection 6.3.3.1, whets statements ars included that make reference to instrument signals used to perform safety-functions in the RTS or. SIS systems as described in Section~7. These-functions no longer i

exist'in Section 7.

Particularly, items 2 and 3 in subsection 6.3.3.1 1

have evidently been replaced in Section 7.2 by other types of measure-ments.

Perform'an. audit to assure that all such inconsistancies have

-been found and amend the FSAR to reflect the-necessary changes.

3.-

JIn subsection 5.4.3.2 the! statement is made, "To increase reactor coolant-flow measurement accuracy', an N-16 power monitor.(one per

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D 2-a io,p and externa 11y' connected tolthe hot legs)~will replace'the-L w

! function.of the hot [ leg RTD ma'nifold." Explain.in detail how:the E

%.. e LN'-16' power monitor increases' reactor coolant flow measurement ac-J Icuracy an'.where and how:the hot leg RTDs are installed in the new d

' configuration.:

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Subsection 7.4.2 states.that " Hot Standby is.a safe, stable,

-plant condition,1 automatically reached following a plant shutdown.

Hot Standby.can be maintained safely for an extended period o'f time.

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In.the unlikely event that access to-the Control Room'is restricted,

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the. plant.can be safely kept at Hot Standby until the Control Room' can be re-entered by:use of'the monitoring indicators and controls
listed in subsections 7.4.1.1 and 7.4.1.2." ' Explain in detail how

~the plant automatically reaches Hot Standby following all-kinds of-1

' plant-shutdowns and how long the plant can be kept at Hot Standby

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.l following a Control Room evacuation'without' violating'the Technical Specifications.- Include a detailed list of actions required to; place s

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the plant in-Hot Standby from-the hot Shutdown Panel-and.the instru-

.ments,-conErols-and otb r devices used'to complete this action.

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State hbw CPSES conforms.to'. Regulatory Guide.=1.97, " Instrumentation for q

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!. Light: Water.Cooldd Nuclear? Power Plants.to Assess Plant Conditions

-j During and Following an; Accident." Justify any-exceptions taken orialternate methods.uset.

16.

. The -lists. of j CPSES electrical, jinstrument'ation and. control-drawings

'ini.FSARLsubsection-1.7/and'specifically. Tables l.7-1 and 1.7-2, are-

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incomplete.- lFor example in Table 1.7-1, Westinghouse drawings 8758D39, 5656086 andLothers,previously_ referenced and included in Table 7.1-2.

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are not listed. NRCl requires that a11' safety related drawings be listed and issued-in their final ~ form af ter an audit -is performed to assure that the information presented:

a.

_ represents-the most recent revision b.

contains the necessary! cross references

'c.:

includes all safety related equipment such.ss control board and panel layouts, valves, motors 'and instruments, and; L

d. '. permits _ a poi'nt ~ by point identification from the sensors - to the actuating device.-

'7.-

'The Nuclear. Instrumentation System Functional Block Diagrams in

referenced report-WCAP-8255 do not provide the-information necessary to review the use of the four section power range ionization chamber

. arrangement incorporated into the CPSES_ upgrade package.

Provide a detailed discussion'of the changes made to the nuclear instrumentation sys' tem _ and thelRTS to incorporate this change.

Also provide a complete. set of construction functional block and schematic diagrams of the: system. ' Explain how the use of the four-section detectors

affect the high flux set-points defined in the. Technical Specifications.

l8.

_ The figures :in Section 7. of the~ FSAR do not cross reference-Gibbs and. Hill. Westinghouse or other vendor drawing numbers.

Far example, Figure 7.2 is not referenced to Westinghouse - drawing 5655D30.

On each figure in the FSAR.that represents a drawing.. provide a cross-A

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. d treference toithe appropriate drawing number.

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1The= responses to questions Q32.32 and Q32.35 are not acceptable.

The NRC Standard Review Plan Table 7-l'contains the acceptance criteria for controls used to review the-FSAR.: The applicability of these criteria to specific subsections of Section~71of the FSAR are.

indicated in a matrix -listing of criteria and. FSAR subsections.

The present Table 7.1-1 of the FSAR does not provide this detailed matrix for all subsections and particularly all of Section 7.

Provide a-. detailed matrix and identify in the table matrix where discussions on conformance to General Design Criteria, Regulatory Guides, Standards and Branch Technical Positions are located.

Include in the Table Regulatory Guides 1.7, 1.78, and 1.96.

10.~

Subsection 7.1.2.6 discusses the conformance to Regulatory Guide 1.47,

~"Bypasse'd and Inoperable Status Indication for Nuclear Power Plant Safety Systems" and states "if suitable signals are not-available to

provide automatic indication, a means of manually providing bypass or unoperablefstatus indication i', provided." Position C.4 of Regulatory; Guide 1.47 states that " manual capability should exist in the control' room to activate each system-level indicator provided."

. Provide a~ detailed description of the Bypassed and Inoperable Status

' Indication System' including functional block logic diagrams and electrical schematic drawings and explain how the' em meets Regulatory Guide 1.47-and Branch Technical ~ Position ICSB 21.

Justify-

-any?except' ions taken.

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~5-11..Section'16] subsection 2.0,-Bases,andspecificallysubsection2.2.1of-theTechnicalSpeEification,.indicatesthattheRTSincludesOver-

'tes' erature and ;0verpower AT, Steam /Feedwater Flow Mismatch and p

Low: Steam Cenerator Water Leve1~ trips.

These RTS trips are 'also includedin Technical Specification Tables 3.3-1, 3.3-2, 3.3-3, and 3.3-4..lThese tripsfare not consistant with the trips listed in

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subsection' 7.2.

Af ter:an audit'is. performed to locate all'such inconsistancies, amend the.FSAR to reflect.the necessary changes..

f 12.

Subsection 17.3.2.1$ states that "A Failure Mode and Ef fects Analysis (FMEA)

'has been performed on a Reneric ESFAS similar to CPSES" but no r

reference is made -to topical or otfier reports that present the results.

Provide' the results of. the FMEA and describe. hardware differences between the generic' design used as the bases for the FMEA and CPSES'and account for^any differernce due to the.CPSES design.

13.1 Subsecticn 7.4.2 states that "The results of the analysis which

- determinsd the applicability to the BOP and Nuclear Steam Supply System Safe Shutdown Systems of the General Design Criteria-(GDC),

IEEE Standard ~279-1971,. and applicable Regulatory Guides and'other

, industry standards.are presented in Table 7.1-1."

These resulta

-cannot be found in Table 7.1-1.

Provide the results and a-detailed discussion of'how'the syst'ess' required for safe shutdown meet j

CDCs11,;.19, 21, 22, 23,' 26, 33, and 34; IEEE Standards 279 and

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J 336;1 Regulatory Guides 1.22.1.47,1.53,1.68 and 1.75.

14. iThe responses to: questions Q32.23.and~ Q32.36. are unacceptable. -

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Identify the systems required for safe shutdown and provide a con-sistant list of the instruments and controls required for safe shutdown in both Table 7.4-1 and the FSAR te.xt.

15.

Provide in subsection 7.6 a detailed discussion and analysis of the instrumentation installed to prevent or mitigate the consequences oft a.

cold water slug injections b.

refuelling accidents, and; c.

overpressurization of low pressure systems as requested by Regulatory Guide 1.70.

Also state how conformance

.to Branch Techni, cal. Positions ICSB 3, 4, and 20 is implemented and justify alternative methods used.

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i Mr. ~ R. : J. Ga ry.

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- Mr. R. J. Ga ry

. Executive Vice President' and General Manager Texas Utilities Generating Company 2001 Bryan Towers Dallas, Texas 201 Nicholas S. Reynolds, Esq.

Debevoise A Liberman 1200 Seventeenth Street Washington, D.C.

20036 Spencer C. Relyea, Esq.

Worsham, Forsythe &-Sampels

- 2001 Bryan Tower

. Dallas, Texas ~ 75201 Mr.'llomer C. Schmidt Project Manager - Nuclear Plants Texas. Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Mr.-II. R. Rock Gibbs and liill, Inc.

393 Seventh Avenue

.New York, New York ' 10001

= Mr. A. T. Parker Westinghouhu Electric Corporation P.

0.~ Box 355.

Pittsburgh, Pennsylvania 15230-

Richard 'W. Lowerre, Esq.

Assistant Attorney General Environmental Protection Division LP. 0 -Box 12548 Capitol Station

Austin,: Texas 78711 Mrs. Juanita Ellis, President

' Citizens' Association for Sound

Energy 1426 South Polk-Dallas,-Texas 75224 Ge'offrey M. Gay,- Esq.-

West Texas Legal-Services 406; N.T. Waggoner Building

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810 llouston Street 1 Fort. Worth. Texas ~~76102-J k

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H MsL Nancy.Holdam Jacobson'

- Citizens for Fair. Utility Regulation, 1

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-1400 Hemphilll

. Fort Worth,- Texas 76104.:

l Mr.: Richard Fouk'e

--1668-B Carter Drive.

Arlington, Texas '76010

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