Text

Non-proprietary MDE-92-0485, Tech Spec Improvement Analysis for Reactor Protection Sys for River Bend Station,Unit 1
	ML20059G843
Person / Time
Site:	River Bend
Issue date:	04/30/1985
From:	Chi L, Cornwell K, Tran P; GENERAL ELECTRIC CO.
To:	;
Shared Package
ML19311B360	List: ML20059G818; ML20059G843; ML20059G846; RBG-39895, Application for Amend to License NPF-47,extending Allowable Outage Times of Instruments Involved & Increase Channel Functional Surveillance Test Interval from Monthly to Quarterly Requirement.Proprietary Rept Encl;
References
	DRF-AOO-02119-D, DRF-AOO-2119-D, MDE-92-0485, MDE-92-485, NUDOCS 9401250327
	Download: ML20059G843 (80)
	v • d • e

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GENERAL ELECTRZC COMPANY 1

CLASS III j

i

.T E-92-048 5 DRF A00-021'9-D APRIL 1985

.{

TECHNICAL SPECII.ICATION IMPROVEMENT ANALYSIS FOR TF.E REACTOR PROTECT!ON.

SYSTEM FOR RIVER BEND STATION, UNIT.1

(~FIS REPORT MAS BEEN PREPAP.ED FOR GULT STATES UTILITIES

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COMPANY THROUGH TFE TECHNICAL SPECITICATION IMPROVDfDIT C0te!!TTEE OT THE Bk1t OWNERS' GROUP)

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PREPARED BY:

P. T. Tran/K. F. Cornwell, Engineers Application Analysis Services VERITIED BY:

L. L. Chi, Senior Engineer-l Application Analysis Services APPROVED BY:

. G. it. Sozzi, ManYger Application Analysis Services APPROVED BY:

-R.J. McCandless, Manager Reliability Engineering-

+

APPROVED BY:

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[A. E. Rogers, Manager Application Engineering Services f$S1jggg2lgggg GENER AL $. ELECTRIC PDR I-NucLEAa txacy susMss CMAAnows GENW EIICitsC CCAdANY e 175 CLitTNta Am e $An gsg, cmpoemA 951g3

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CENERAL ELECTRIC COMPAM CLASS III TABLE OF CCNTENTS

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Page 7

1.

INTRODUCTION 1

2.

EVALUATION METHOD 2

3.

RESULTS OF RPS EVALUATION 4

i 4.

SUMMARY

AND CONCLUSIONS 6

5.

RETERENCES 7

APPENDIX A: RPS EVALUATION TOR RIVER BEND STATION, UNIT 1 b

GENERAL ELECTRIC COMPANY CLASS III 1.

INTRODUCTION entends the generic study of modifying the technical This report specification requireeents of the Reactor Prctection System (RPS) on a plant specific basis for River Bend Station, Unit 1 (R351).

The I

generic study (Reference 1) provides'a technical basis to modify the surveillance test frequencies and allowable out-of-service time of the RPS f r:m the genetic technical specifications.

The generic study also RPS provides additional analyses of various known different configurations to support the application of the generic basis On a plant specific basis. The generic basis and the supporting. analyses i

were utilized in this plant specific evaluatien. The results of the plant specific evaluation for RBS1 are presented herein.

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- i CENERAL ELECTRIC CC.9ANY -

C1. ASS III 2.

EVALUATION METHCD The plant specific evaluation of the cdification of the surveillance -

l f recuencies and allevable cut-of-service time of the ItPS was..

l

ent performed in the following steps:

s a.

Cather plant specific information on the RPS frc: Gulf l

States Utilities Company.

The information includes the l

I folleving:

i (1)

Elementary Diagram of the RPS and related systems.

i (2)

RPS description such as plant final Safety Analysis l

Report (FSAR).

(3) Technical specifications on the RPS.

(4) RPS surveillance test procedures.

The latest revision of Items 1,2 and 3 above were supolied

- i by Gulf States Utilities Company.

Item 4 above was provided l

by Gulf States Ceilites Company -in the form of a

questionnaire identifying the. differences between the procedure used in the generic evaluation and the procedure used at RBSI.

Section I of the checklist in Appendix A was e

used to identify the data source.of the plant specific j

information.

b.

Construct the ;ilant specific RPS configuration from the plant specific information.

Questions " A". through "H" in Section II of the checklist were used for this process.

l l

c.

Compare the plant specific RPS configuration with ~ che generic RPS configuration using the generic RPS _ elementary.

f diagram, RPS description, technical specification require-l ments, and other generic inputs.

Section III of the checklist was used for this process.

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.I CENERAL ELECTRIC COMPANY l'

' CLASS-III

)

d.

Classify the differences into.hree categories:

(1) Obvious items which have'no effect on the reliability of the RPS.

Examples of these "no ef fect" items are l

cemponent came differences, symbol differences, and r

other minor nen-functional differences. Disposition of the obvious "no effect" items does not require addi-l' tional analysis.

(2)

Potential differences which require considerable engineering judgment for disposition because of-the functional differences.

Examples of these potential f

differences are separate channels for manual scram as

(

opposed to non-separate channel in.the generic plant and dual redundant contacts per sensor relay in the applicable trip channels as opposed to a single set of.

contacts in the generic plant. The disposition of such items would require engineering assessment as shown in Appendix K of Reference 1.

(3)

Potential differences which require additional analyses 5

to evaluate the effect on the PJS reliability.

Examples of. such potential differences are using RFA -

relays as opposed to using both Potter and Brumfield j

relays and Agastat relays in the generic evaluation.--

Disposition of these items would. require additienal-analyses to compare with the generic results.

These analyses are documented in Reference 1.

e.

Compile a list of plant specific differences of Category (2) and (3).

f f.

Assess the reliability effect of the differences identified in Step (e) on the. generic results. The results of-the-assessment are documented in Section III of the. checklist.

l g.

Document the results of the plant specific evaluation.

.f The above seven step process is documented in Appendix A of this report.

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l GEFER/1 ELECTRIC COMPANY-CLASS III' i

' I 3.

RESULTS OF RPS EVAL'JA!!CN i

The results.of the plant specific evaluation of the PJS for R351 are.

l t

decu-ented 16 Appendix A of this report.

The results shew that.~ the l

RPS configuration of RAS 1 has the following differences which are classified Category (2) or (3):

i A.

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GENERAL ELECTRIC COMPANY CLASS III SLYFARY,O") CCNCLUSIONS A plant specific evaluation of modifying the surveillance test fre-quencies and allowbie cut-of-service time of the RPS free the techni-cal soecifications of R3Si has been performed. The evaluation utilized the generic basis and the additional analyses documented in Reference 1.

The results indicated that the RPS configuration for RBS1 is similar to the RPS configuration in the generic evaluation.

Therefore, the generic basis in Reference 1 is applicable to R3Si also.

e f -

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GENERAL ELEC!a!C-COMPANY CLASS III 5.

REFERENCES (1)

" Technical Specificacion bprovement Analyses for Sk7.

1 Reactor Protecti:n System."

Ceneral Electric

Company,

[

NCC-30851P May 1985.

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GENERAL ELECTRIC CCMPANY r

t CLASS !!!

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APPEND:X A RPS EVALL'ATION CHECKLIST FOR RIVER BEND STATION, L* NIT 1 9

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1 A-1 l

GE.MERAL ELECTRIC COMPANY ;

CLASS III i

Sectice I - RPS Plant Specific Data Source I

k i

Cu,f States '.tilities Ccecanv-1 Ceility:

.i Plant:

River Bend Station Unit 1 Source

.i Number 1.

RPS Elecentary 82SE521 AA. Rev.18 2.

RFS IED 762E42'AA. Rev.3 Control S stem Elementary 944E981. Rev.2 3.

RPS.MC Set i

i RPS Interconnection Scheme Elementary 828E532CA, Rev.2 4

t 5.

RPS Design Specification 22A3771AG, Rev.1 6.

FSAR Section 7.2 Amendment 12

?

l 7.

Technical Specifications Section 3/4-3, Rev.2 (Pr 3.1-3.10) 8.

Survaillance Test Procedure Checklist Not supplied - assumed

[

same as generic plant h

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GENE:UJ., ELECYa:C COMPANY CLASS III i

Section !! RPS Configuration Data Data

Data Source A.

RPS System 2

(1.2)

Number of trip systems 2.

Number of logic channels per trip system Tor Autecatic Scram 2

( 1,,2)

For Hanual Scram 2

(1,2) 3.

Power supply source for each channel MG Set (2) 4 Operation mode Yes (1,2)

- De-energize to trip 5.

Logic arrangement Yes (1)

- one-out-of-two twice 6.

Electrical Protection Assemblies (EPAs)

Yes (2)

IEEE-279 (5) 7.

Design requirement

Yhe numbers shown in the Data Source column refer to the docueents listed in Section I.

A-3

i GENERAL ELECTRIC CCMPANY I

CLASS III.

i Sectien II R?S Configuration Data 3.

RPS Sensors 1.

~dentify the type, total numeer, and number per PJS channel for the following RPS sensors.

Total Number /

Data Type Number RPS Channel:

Source.

- APRM Analog 8

2 (1,2)

- Turbine Stop Valve Switch 8

2 (1,2)l

- Turbine Control Valve Switch 4

1 (1.2)

- KSIV Position '

Switch 8

4 (1,2)

- MSL Radiation Gassna 4

l' (1,2)

Detector

- Level 8 (High Water Level 3 Analog 4

1 (1,2)

- Level 3 (Lew Water Laval)

Analog 4

1 (1,2)

- SDV Level Type ] (Analog)

Analog 4

1

.(1,2)

Type 2 Svitch 4

L

. (1,2)

- High Reactor Pressure Analog 4

l' (1,2)

- High Drywell Pressure Analog 4

1 (1,2)

- Manual Trip Switch 4

1 (1)

- Mode Switch Trip One Switch 4 banks l~ bank (L)-

- Low Condenser Vacuum N/A N/A N/A N/A A-4

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. GENERAL CLECTRIC CCMPANY CLASS ' III

~

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't Section !! RPS Configuration Data Data

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3.

RPS Sensors (Cont'd)

Source r

2.

Turbine Stop Va*ve logic arrange =ent i

Closure of 3 out of a valves initiates scram (1) 3.

Turbine Stop Valve closure monitoring Position switches (1) a.

Turbine Control Valve fast closure monitoring 011_ Pressure Switches (1)

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5.

MSIV elosure logic arrangement Isolation of 3 out of 4 steamlines initiates scram t

6.

Diversity in SDV level sensors i

Float switches and-analog transmitters (1,2) 7.

Number of MSL (2) 4 8.

List of available bypasses

( 1) 1 IRM Trip Bypass Yes Noncoincident Neutron Monitoring System Trip Bypass Yes RFV Righ Water Level RPS Trip Bypass Yes j

Turbine Stop Valve RPS Trip Bypass Yes Turbine Control Valve RPS Trip Bypass

'Yes MSIV Closure RPS Trip Bypass -

Yes SDV High Water Level Trip Bypass Yes Reactor Mode Switch " Shutdown" mode j

Trip Bypass Yes Condenser Lov Vacuum N/A A-5

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i CENERAL ELECTRIC COMPANY

.l CLASS ::I 4

i i

i Section !! RFS Configuration Data 1

-l Data Data

. Source l

C.

Sensor Relays t

Potter & Brumfield,

-(1) 1.

ypes of relays s

Agastat j

2.

Number of pairs of contacts per telay in the trip channel 1

(1)

-l 3.

List type of relay for each RPS sensor

'(1)

I i

Potter &

Brumfisld-Arascat MTA CR105 APRM x

Turbine Stop Valve x

1\\

Turbine Control Valve x

MSIV Position x

j MSL Radiation x-Level 3 x

I i

SDY Level Type L (Analog) x

}

Type 2 (Switch) x l

High Reactor Pressure x

High Drywel;. Pressure x

f Manual Trip x

Mode Switch Trip x

Low Condenser vacuus N/A N/A Level 8 x.

'i A-6

GENERAL ELECTRIC COMPANY CLASS I!!

Section !! R?S Configuration Data Data D.

Scram Contactors Data Source 1.

Type of scram contactors GE Type CR105-(1) 2.

Total number of scram contact.ers 16 (1) 3.

Number of scram contactors per channel 4

(1) i 4

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A-7

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CENERAL ELECTRIC COMPA.Y Y

CLASS III Section !! - P.PS Configuration Data Data E.

Air Pilot Solenoid valves Data Seur:e 1.

Number of solenoid valves per contrcl rod drive 1

(2) 2.

Number of solenoid operators per valva 2

(2) a l

A-8

t GDiERAL ELECTRTC COMPANY CLASS III R?S Configuration Data l

4 i

.n Data-Data Source F.

Backup Scram l.

Type of scram centactors fer backup scram valves Potter & Brumfield,

(*)-

and Agastac

.+

7 2.

Number of scrae. contactors 2

(1)'

per backup scram valve 3.

Same RPS scram contactors are used to actuate backup scram No (1) valves i

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4 Operator mode Yes (2)

- energized to trip 5.

Test requirement for backup scram valves

-Not specified in Tech. Spec.

(7))

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Intermediate telays are used i

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'i GENERAL ELECTRIC CCHPANY CLASS III

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Section II R?S Configuration Data j

i Data Source G.

RPS Tech. Spec. Requirements 1.

Calibration Frequency for L?RM At least once per 1000 effective full power hours

(?)

2.

Calibration frequency for trip units.

l 1

Once a month (7) l 3.

Frequency of Logic System Functional Tests Once per 18 months (4) i 4

Allowable time to place an inoperable channel or 7

trip system in the tripped conditions when the-number of operable channels is less,than'the required einimum operable channels per trip system.

j Within i hour (7)

~

5.

Exception to Item 4 Allows two hours to restore inoperable channel without (7)

-i cripping if the tripped channel v111 cause the Trip Function to occur.

6.

Allowable time to place a trip system in the tripped conditions when the number of operable channels'is less than the required minimum operable channels for both trip systems.

Within l' hour (7) 7.

Exception to Item 6 due to surveillance test.

Two hours for surveillance

-(7)'

i 8.

Complete the Table ~on the following page.

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CI NFRAI.1:1.ECTRIC tm.4PANY CLASS III REACTOR PROTECTION SYSTi.tl INSTRl1HENTATION REllillRFHENTS Cleanne l Minimusi Channel Functlunal Chann.l opesable Clianne l s Check Te t. t C.a l lb r.it t on Per_ Trip System

,,Cene ric Plant Generic Plant

,Generle Plant Ceneric Plant Punc t ional linit Model Specific Model Specific Model Specific

,He nle l Specific

1. Average Power Range Monitor:

a. Flow Blased Simulated S.D S.D S/U,W S/U,W W.SA,R W,SA,R 3

3 Thermal Power - High

b. Neutron Flux - High S

S S/U,W S/W.W W.SA W.SA 3

I c.

Inoperative N/A N/A W

W N/A N/A J

l

2. Recctor Vessel Steam Dome S

S H

H R

lt 1

Pressure - Higli

3. Reactor Vessel Water Level -

S S

H H

k R

2 2

Low, i.evel 3

4. Racctor Vessel Water Level -

S S

H H

R R

2 2

High, Level 8

$. Main Steam 1.ine Isolation N/A N/A H

H R

R 4

4 Valve - Closure

6. Hsin Steam Line Radiation -

S S

H H

R R

2 2

liigh

7. Drywell Press.ure - High S

S H

H R

R 2

2

8. Main Condenser Vacuum - Low N/A N/A N/A N/A N/A N/A N/A N/A A-lI e

..m.

_ -. -. -..... - - - - ~.... -...... ~ ~.. -,

_....... -. -. ~.... - - -.. -..... - ~......

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

l Ct NI.kAi, ELECTl:lO l'elMPANY CLASS III REACTON l*POTECTION SYSTEM INSThilMENTATipH HFyu t kl Hl'NTS Channel Minimum i

Ch.enne1 Funct1o:44 1 Cliasine 1 Ope r abl e-Cliaisine i s Cla ck Test C.illbtation l'es Trip System Ceneric Plant-Generic-Plant i ener ic Plant beneric. Plant Fuxetional Unit Model Specific Model Specific Model Specific Hudel Spect!!c i

a 9.

Scras' Discharge Volume Water Level - High' Type 1 - Analog S

S H

H R

R 2

2 Type 2 - Switch N/A N/A H

Q H

R 2

2

10. Turbine Stop Valve - Closure

~N/A S

H H

R R

4 4

!!. Tuthine Control Valve Fast N/A S

H H

P R

2 2

Closure Valve Trip System 011

. Pressure - Low

12. Racetor Mode Switch N/A N/A R

R N/A N/A 2

2 Shutdown Position

13. Manual Scram M/A N/A N

R N/A N/A 2

2 S= Shift.

H-Monthly S/U=Startup

'D= Daily Q= Quarterly N/A=Not Applicable W. Weekly

-R=Refueltog Durage A-12 I

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- GENE 3.AL L".ECTRIC CCMPANY i

CLASS III Section II - RPS Configuration Data (Cont'd)

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Data

'l H.

R?S Surveillance Tests Procedure Source 1.

The following components are all tested as part (8) f of an individual channel functional test:

'j 1

I Individual channel sensor (s),

e.g., Transmitters a.

and Trip Units, switches, flux or radiation

.[

l sensors.

[

b.

Associated logic relay (s) c.

Associated scram contactors List any plant specific differences f rom the above.

r RISPONSE The surveillance test procedure for 1551 is not written yet.

Per instruction of Gulf States Utilities Company, f

the evaluation assumes that the surveillance test procedure for RSSI is the same as the generic model.

2.

When an individual sensor channel ~1s in test or repair, (8) is associated logic channel tripped or is the sensor channel jumpered? State which of the two conditions applies to your plant.

If any other condition exists in your plant, describe.

RESPONSE

See response for Question H.L.

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A-13

.r GENERAL ELECTRIC COMPANY CLASS III Section II - RPS Configuration Data (Cont'd)'

[

i Data:

H.

RPS Surveillance Tests Procedure (Cont'd)

Source 3.

For those plants which do not place individual channels

-(8)

+

in a tripped condition during test or repair. it is assumed in the GE analysis that only the individual sensor and. associated logic relay is placed in an.

inoperable condition during cast or repair of the individual channel.

If this assumption is not true for your plant, list the cemponents (from sensor to scram contactors) which are placed in inoperable l

condition during test or repair.

RESPONSE

See response for Question H.1.

4 The following number of individual scram (8) contactor actuations are assumed in the GE analyses for each channel functional cast:

i l

a. APRM channel functional tests _ -

l 2 actuations per scram contactor pair in sach trip logic channel.

b. MSIY closure channel function tests -

4 actuations per scram contactor pair in each trip logic channel,

c. Other channel functional tests -

L actuation per scram contactor pair in each trip logic channel.'

1 List any differences from the above for your specific plant.

RESPONSE

See response for Question H.1.

D

GENERAL ELECTRfC COMPANY CLASS.III Section II - RPS Configu,racion Data (Cont'd)

Data E.

RPS Surveillance Tests Precedure (Cone ' d )

Scurce 5.

Do planc procedures allow simultaneous (8) inoperable conditions (failed condition) of diverse sensors in a given logic channel?

RESPONS E See response for Ousseion H.1.

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' GENERAL ELECTRIC COMPANY CLASS III t

i Section III - Assessed Reliability Effect of RPS.Configura:ica Differences.

Plant Specific Assessed Reliability 3!!R Ceneric Medel Difference Effect

i A.

RPS System i

1.

Generic model has No difference two trip systems.

2.

Generic model has No difference two logic channels per trip system for automatic scram.

3.

During operation.

No difference the trip systems are energized and trip when de-energized.

4 The RPS logic is one-No difference out-of-two evice, i.e.,

a one out of two logic channels will trip o

an individual system and trip of both systems is required for scram.

5.

Generic model has No difference Electrical Protection Assemblies (EPAs).

6.

Each RPS channel can be No difference

,i manually tripped from the Control Room ustas the manual scram circuits.

1 A-16

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GENERAL ELECTRIC CCKPANY

- 1 CLASS III

+

Sectica :::.- Assessed Reliability Effect of RPS Configuration-Differences

- i Plant Specific Assessed Reliabilitt 3VR Generic Mrdel Difference Effect F

B.

Sensors 1.

Generic model has No difference Analog Trip Unit /

Transmitter for ressure and level

]

sensors.

2.

Mini =um number of No difference sensors is one per RPS channel for each

. i scram variable.

3.

Generic model has No difference i

eight APRM conitors with evo per RPS channel.

4 Stop Valve Closure No difference trip logic is a reduced two-of-four required for trip.

5.

Stop Valve Closure is No difference monicered by limit switches.

6.

Turbine Control Valve No difference fast closure is monitored by control oil pressure.

7.

MSIV closure trip No difference logic requires i

isolation of three l

out of four steam-lines to scram.

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CENERAI. El.ECTRIC COMPANY l

Cf. ASS ZIZ l

i Assessed Reliability Effect of RPS Configuration Differences j

Plant Specific Assessed Reliability' 3WR Ceneric Model Difference Effect 3.

Sensors (Cont'd) 8.

Generic model has a No difference j

Level 8 (High Reactor l

Water Level) Trip.

i 4

9.

Generic model has No difference diverse Scram Dis-charge Volume (SDV) level sensors.

10.

Generic model has No difference 4 main steam 11nes.

i 11.

Generic model does No difference not have a direct scram on low condenser vacuum.

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1 A-18

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.. GENERAL ELECTRIC'CCt'JANY CLASS !!!

Assessed Reliability Effect of R?S Configuration Differences Plant Specific

' Assessed Reliability 3E Ceneri Model Difference-Effect i

f C.

Sensor Relays 1.

For all transients No difference there are at least two scram variables i

with different type

. logic relays (either Agastat er Potter

& 3rumiield).

2.

Each sensor relay No difference has a single pair j

of contacts in the applicable l

trip channel.

l l

D.

Scram Contaccors 1.

All scram contactors No difference are one type (CE Type CR105).

i' 2.

Eight scram contactors Sixteen scram contactors (two per RF5 channel)

(four per RPS Channel) perform the trip function.

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GENERAL ELECTQIC COMPANY CLASS III 1

Assessed Reliability Ef fect of RPS Configuration Differences

-i Plant Specific Assessed Reliability

.l B'4R Ceneric Model Difference Effect

-l E.

Air Pilot Solenoid Valves 4

1.

Generic model has No difference i

dual solenoid operators l

fot each individual HCU air pilot valve.

De-1 energizing both sole-noids results in a scram of the individual l

control rod.

i F.

Backup Scram

_j 1.

Actuation of backup Backup scram valves are scram valves are con-actuated from a separate trolled by same output set of intermediate relays l

scram contactors as (Potter & Brumfield),

i EPS.

2.

Trip logic for backup No difference scram valves is an energized to trip versus de-energized to trip for individual RCU air pilot valves.

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L GENERAL ELECTRIC COMPANY' CLASS III Assessed' Reliability Effect ef RPS Configuration Differences:

Plant Specific Assessed Reliability 3'.7. G e n e r i c.wedel Difference Effect F.

Backup Scram (Cont'd)

~

3.

Backup se' ram valves Test requirements for the are tested during backup scram valves are shutdesm at least not specified in the ente per 13 =enths.

plant Technical Specifi-cations.

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GENERAL ELECTRIC COMPANY CLASS III i

Assessed Reliability Ef fect of RP3 Configuration Differences ~

Plant Specific Assessed Reliability l

SWR Ceneric Model Difference Effect C.

Technical Specifications and Surveillance Test Procedura:

Generic =odel uses See Section II.G BWR6 Standard Tech-of this Appendix nical Specifications for plant specific which requires:

differences.

I Allowable out-of-service time:

I hr

~

Test time:

2 hrs Test frequency:

j IW for APRM IM for others Calibration frequency:

iM for trip units R for transmitters 2.

Generic model assumes No difference j

evo actuations per scraa contactor pair in sach crip logic channel for the AFRK channel funce-ional tast sad four act-i uscions for the MSIV Closure Chamael function-al tests, and one actuation for tha other l

seren variables. This leads to 272 total j

actuations of each scram contactor per year.

I A-22

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ENCLOSURE 1 - Supplement 1 Page 1 of 2 H. RPS Surveillance Test Procedure 1.

The following components are all tested as part of an individual channel functional test; a.

Individual channel sensor (s), e.g., Transmitters and Trip Units, Switches, Flux or Radiation Sensors, b.

Associated Logic Relays.

c.

Associated Scram Contactors.

r

RESPONSE

"or H.I.a above, sensors are not tested in functional tests, only in calibrations.

2.

When an individual sensor channel is in test or repair, is associated logic channel tripped or is the sensor channel jumpered? State which of the two conditions applies to your plant. If any other condition exists in your plant, describe.

RESPONSE

P If the sensor channel is in test or repair for longer than two hours, the sensor channel is placed in a tripped condition which causes a logic channel trip.

3.

For those plants w hich do not place individual channels in a tripped condition during test or repair, it is assumed in the GE analysis that only the individual sensor and associated j

logic relay is placed in an inoperable condition during test or repair of the individual j

channel. If this assumption is not true for your plant, list the components (from sensor j

to scram contactors) which are placed in an inoperable condition during test or repair.

RESPONSE

This assumption is true for RBS.

4.

The following number of individual scram contactor actuations are assumed in the GE analysis for each Channel Functional Test:

APRM Channel Functional Tests - 2 actuations per scram contactor pair in each I

a.

trip logic channel.

b.

MSIV closure Channel Functional Tests - 4 actuations per scram contactor pair in each trip logic channel.

ENCLOSURE 1 - Supplement 1 7

Page 2 of 2 c.

Other Channel Functional Tests - 1 actuation per scram contactor pair in each trip logic channel.

RESPONSE

4.a Six actuations per scram contactor pair in each RPS trip logic channel.

4.b Two actuations per scram contactor pair in each trip logic channel.

l 4.c One actuation per scram contactor pair in each trip logic channel.

5.

Do plant procedures allow simultaneous inoperable conditions (failed condition) of diverse sensors in a given logic channel?

RESPONSE

r No EVALUATION (Supplements G.2, page A-22, of MDE-92-0485)

Ouestion 1 This difference is consistent with the BWR-6 Technical Specification definition of Channel Functional Test and is within the range of the sensitivity study provided in NEDC-30851P.

Ouestion 2 b

This response to this question is consistent with the Allowed Out of Service Time requirements of a typical BWR-6 Technical Specification and is consistent with the sensitivity study provided in NEDC-30851P.

Ouestion 4 The surveillance test procedures for RBS specify that the RPS scram contactors should be tested with six actuations per scram contactor pair in each RPS trip logic channel (three actuations per APRM per week with two APRMs per trip logic channel for a total of 312 scram contactor actuations/ year /RPS trip logic channel), two actuations for MSIV closure (two MSIVs per trip logic channel per month for a total of 24 actuations/ year), and one actuation for all other sensors (10 sensors per month for total 120 actuations/ year) for a combined 456 actuations per year.

The generic model assumes two actuations for APRM (104 actuations/ year), four actuations for MSIV Closure (48 actuations/ year), and one actuation for other sensors (120 actuations/ year) for a total of 272 actuations/ year. The difference,272 vs 456 actuations/ year, produces an insignificant effect on the RPS failure frequency because the variation in the number of scram contactor actuations has been assessed to be an insignificant contributor to wear out, reference NEDC-30851P, Section 5.6.6.

r

6 1

5 J

I L

d ENCLOSURE 2 f

r 1

4 1

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Euct-os M 2 l

(E.2-)

Pac.e 1 oc' 33 i

- 3 e

GE Noaiser Emerry Gewd Eecme Canon 175 Carmer w Sen.ene. ta 15115 March 22, 1990 j

MFN 024-90 OC90 319 32D Director of Nuclear Reactor Regulation

]

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Millard L. Vehl Technical Specification Branch subject:

Clarification of Technical specification Changes Given in j

RCCS Actuation Instroentation Analysis

Reference:

NEDC 30936F A, " BUR Owners' Croup Technical Specification.

Improvement Methodology (With Demonstration for SUR RCCS Actuation Instrumentation), Part 2. December 1986.

~

The purpose of this letter is to provide you with inforestion that we have forwarded to each BUR Owner _to support his plant specific submittal of changes to the RCCS actuatten instavnentation surveillance test intervals (STIs) and allowed out-of service th2s (ACTS) given in the Reference. The i

information deals with clarifications to modified technical specifications given in Appendix A of the Reference.

l The first clarification concerned the proposed change to the repair

'i AUTs given en pages A-3 and A-9 for EUR 6 Solid State Plants, pages A 4 and A 14 for BUR 5/6 Reisy Plants, and pages A 4 and A-18 for SUR 3/4 Flants.

j In the technical specification markup for the above product lines, Table 3.3.3-1 was not included in Appendix A of the Refereses report. The i

proposed modification as written implies a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AIFF before taking any-action listed in Table 3 1 3 1. It was intended that the Atrf of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1

apply to the individual actions listad in Table 3.3.3-1.

Therefore, we have-advised each utility to easks the following chsages relating to repair ACT in their plant specifie admittals:

4 a) We abange to action b. of paragraph 3/4.3.3. The paragraph

-i eheuld read as follows:

'With one er more BCCS actuation instroentation ehme=als inoperable,

']

take the ACTION required by Table 3.3.3-1."

b) Revise ACTIONS given in Table 3.3.3-1 according to the attached Table 3.3.3 1 modifications (Enclosure 1) for Standard Technical Specifications.

The second clarification dealt with technical specification shanges te.

the reactor core isolation cooling (RCIC) system. The Referense analysis

~

tE. '7_

f44 E

~2-Millard L. Wohl Page 2 March 22, 1990 included proposed STI and ACT changes to this system (see last paragraph of page 2-1).

However, markups of the proposed modifications as they should appear in the Standard Technical Specifications for the RCIC actuation were not provided in Appendix A of the Reference report.. The attached markups-(Enclosure 2) of the Standard Technical Specifications for the RCIC actuation instrumentation were provided to the BWR Owners for their use 'in tt.eir planc specific submittals.

We feel the above information has been considered in the Reference NRC approved analysis and represent clarifications to ensure plant specific changes are properly interpreted. Please give one of us a call if you should have any questions.

Very truly yours, i

J "T

1a n >

=v V. F. Sullivan J. F. Klapproth Reliability Engineering Services BUR Owners' Croup Programs M/C 789 (408)925 6992 M/C 382 (408)925 5434 4

a Enclosures cc: BUROC Technical Specification Committee - D

{

BWROC Primary Representatives of Participating Utilities S. D. Floyd, SWROC Chairman C. J. Beck, SUROC Vice Chairman D. N. Croce, RRC Chairman L. 5. Gifford (CE-Rockville)

3. J. Stark (CE)

A. E. Rogers (CE) l i

1 I

i f

i l

1 F

E7 P%G 3 I

Proposed Repair Allowed Out of-service Time Modifications to the ECCS Actuation Instrumentation Standard Technical Specifications

'f 6

1 i

l w

I E7 Fee 4 l

1 1

i TABLE 3*.3. 3-1 (Continuedj EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

~

1 E LQ" '

ACTION 30

With the number of OPERABLE channels less than required by the Minimum OPERARLE Channels per Trip Function requirement:

With one channel inoperable, place the inoperable channel a.

in the tripped condition within ene eewr" or declare the associated systes inoperable.

y hogn i

.b.. ytth aere than one channel inoperable, declare the

tesociated systes inoperable.

ACTION 31 -

With the number of OPERA 8LE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare '

i i

the associated ECCS inoperable 4)/thl,3.Qy hoqu ACTION 32 -

With the number of OPERA 8LE channels less than required by the Minteum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition withig -- in.

With the number of OPERABLE channels less than requirk:kd ACTION 33 -

Minteus OPERA 43 Channels per Trip Function requireme the inoperable channel in the tripped conditten within :n.a 4

restere the inoperable channel to OPERABLE status within 7 days 3

or declare the associated system tasperable.

ACTION 34 -

With the number of OPERABLE channels less than required by the Minism OPERABLE Channels per Trip Function requirement, resters the inoperable channel to OPERABLE status within 4*pers er declare the associated ECCS inoperable.

JVh e ACTION 35 -

With the number of OPERABW channels less than required by the Minfan OPERABLE Channels per Trip Function requirement:

For one trip systas, place that trip system la the tripped a.

condition within eme4oura er declare the WCI system inoperable.

2 Y heoc b.

For beta trip systems, declare the WCI system inoperable.

ACTION 36 -

With the number of BPERABLE channels less than required by the IHatsum OPERA 83 Channels per Trip Function requirement, place at least one inoperable channel in the tripped conditten within

-- r er declare the W CI systen inoperable.

ACTION 37 -

h b r of OPERAB W channels less tAan the Total Number of Channels, declare the associated emer0ency diesel generater inoperable and take the ACTION required by Specificatten 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 38 -

with the number of OPERA 8LE channels one less than the Total Number of Channels, place the inoperable channel in the tripped

- {

condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ;" operation any then continue until performance of the next required CNANNEL FL20CTIONAL TEST.

1TrE provisions *ef Specification 3.0.4 are not applicable.

GE-STO (8WR/4) 3/4 3 30

ve-y

E., '2.

t%G &

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.

ACTION ACTION 30 -

with the number of OPERABLE. channels less than required by the Minfeue OPERABLE Channels per Trip (Systes) (Function) requirement:

(For "per Trip Systes")

/34 hevc For one trip systas, place at least go inoperable channel a.

in the tripped condition within in associated ADS trip system er ECCS i ;-

er declare the j.

nop rable.

b.

For both trip systems, declare the associated ADS trip system or ECCS inoperable.

(For "per Trip Function")

a.

For the LPCS system and the LPCI mode of the RMR systes, declare the associated LPC5 and/or LPCI systans. inoperable.

b.

For the NPCS system and the ADS:-

1.

With one channel inoperable, place the inoperable channel in the tripped condition vihtin n ' -* or declare the NPCS systen and associated AD5' trip \\.Nhwk5 system inoperable.

)

2.

With more than one channel inoperable, declare the MPCS system and the associated ADS trip systas(s) inoperable.

~

ACTION 31 -

With the number of OPERABLE channels-less than required by the Minies OPERABLE Channels per Trip Systes requirement.4S.nM/h.e declare the associated A05 trip systen er ECCS fasperable.

ACTION 32 -

With the neber of OPERABLE channels less than required by the Minious OPERABLE Channels per Trip System requiremen* verify bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months er S lare the associated ECC5 inoperable.

ACTION 33 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip system requirement, restore the insperable channel ta OPERABLE status witM.a Qse. ar-declare the associated A05 valve er ECCS inoperas ACTION 34 -

with the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within ens.houpa er declare the NPCS system inoperable.

.l A V hour.$

"The provisions of Specification 3.0.4 are not applicable..

I GE-STS (BWR/5) 3/4 3-27

E 2.

P4<.c &

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEN ACTUATION INSTRUMENTATION ACTION (Continued)

ACTION 35 -

With the n e er of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel p nerator Inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 36 -

With the number of OPERA 8LE channels one less than the Total Amber of Channels, place the inoperable channel in the tripped condition within I hour *; operation then centtaue until l

performance of the next required L FLETIONAL TEST.

)

i

/

l

'The provisions of Specification 3.0.4 are not applicable.

i GE-STS (IWit/5) 3/4 3-27a l

i l

j 13 '2.

Pae G 'l TA8LE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATIM INSTRtMENTATION

.1 j

M a

\\

ACTION 30 -

With the neber of OPERA 8 2 channels less than reevired by the Minis e OPEAA8 d Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperele channel in the tripped condition within eaM or esclare tne

-l associated systen inspar ele.

f y hea tc b.

With asm than one channel inoperatie, esclare the associstec system inoperable.

ACTION 31 -

With the neber of OptRAB M channels less than required by the Minfan OPERA 8LE Channels per Trip Function requimment, place the inoperable channel in the tH pped conditten within ene- 0 4 h e.or'<

hour.

mestere the insperable channel to OptRABLE status within 7 eays er declare the associated system lamperable.

ACTION 32 -

With the numer of OptRABW shannels less then required by the Rinfan OPERA 8LE Channels per Trip Function reeutrement,a/,tf;., Jy4cc l

declare the associated ADS trip system er ECCS inoperable.

ACTION 33 With the ember of OptRABLE channels less then the Nintem OpfRABM Channels per Trip Function requirement, place the inoperable channel ta the tripped conditten within --- " -

WiththeneberofOttRA83shannelslessthenregufredYtd I

.)

ION 34 -

Rinies OptRABLE Channels per THp Function requirusent, verify e

bus power availeility at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months er declare the assectated ECC5 insparetle.k X

ACTION 35 -

with the au mer of OptRAS W shannels less then regufred by the Minia n OPERABLE Channels e THp Function requirement, restare the insperette channel to LE etatus within4 Aguas or

~

declare the associated A05 velve or ECCS insporetle.Ngg ACTION 36 -

with the ember of OptRABLE channels less then required by the Rinises OptRABLE Channels per TH 1em resent:

a.

For one trip erstas, systan in the tH oped eenditten withis or declare his trCS systas inoperable, b.

For teth tH p systems, esclare the Irc$ system inoperable.

ACTION 37 -

iffth the ausber of OptRABLE shannels less than required by the Rimis m OptRABLE Channels per THp Function requirement, place at least one insparele channel in the tHpped censitten within

.er esclare the trCS system inoperable.

ACf!0N 38 -

number of OptRABLE channels less than the Total #mber

~

of Channels, declare the associated emergency diesel generstar inoperele and take the ACTION required Ey Specification 3.4.1.1, er 3.4.1.2, as apprepd ata.

ACTION 39 -

With the nu mer of OptRAB M channels one less then the Total Naser of Channels, place the inoperable channel in the tripped conditten within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; speration then continue until s

performance of the next required L MmCTIONAL TEST.

"The provistens er specification 3.0.4 are not appliale.

GE-STS (BWR/6) 3/4 3-31

E.1 en S TA8tf 3.3.3-1 (Continvee)

EMttCtWCY C0eE COOLING SYSTEM ACTUATION INSTsVM[NTaTICM AE1E!!

ACTION 30

With the number of OPERA 8LE channels less than reevired by the Minimum OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within lHioge* er declare the associated system inoperable.

1t/hcur#

b.

With more than one channel inoperatie, declare the associstee system inoperable.

ACTION 31

Deleted.

ACTION 32 -

with the nus6er of OPERABLE channels less than reeutred by the Minious OPERA 8LE Channels per Trip Function requirement,iM/,.., Jy he declare the associated AD5 trip systas of ECCS inoperable.

ACTION 33 -

with the neber of OPERA 8LE channels less than the Minfeue OPERA 8LE Channels per Trip Function requirement, place the inoperable thanne1(s) in the tripped conditten within 2 W.

ACTION M =

Seleted.

MM ACTION 35 -

with the naber of OPERA 8LE channels less than required by the i

Minteue OPERABLE Channels per Trip Function requirement, restere the inoperable thannel to OPERA 8LE status within or declare the associated A05 valve er ECC5 insperable.

Jy A.,so

)

g ACTION M -

with the number of OPERABLE channels less than required by the Ninteue OPERABLE Channels per Trip Function requirement:

a.

For one trip system, place that trip systan in the trippec l

'- " or declare the NPCS systas eendition within ^ D

Orb inoperable.

J l

6.

For teth trip systems, declare the W C5 system inoperable.

ACTION 37 -

with the number of OPERA 8LE channels less than required by the l

Mintem GPERAOLE Channels per Trip Function requirement, place at least one faeperable channel la the tripped tendition within

+

[

J destare the WC5 system inoperable.

. ACTION 38 thWauter of 0FSAABLE channels less than the Total Naber l

of Channels, dealere the associated emergency diesel generator' tamperable and take the ACTION required by Specifications 3.8.1.1 er 3.8.1.2. es appropriate.

ACTION 39 -

With the ember of OPERABLE channels one less then the Total Baber of Channels, place the insperable channel in the tripped i

eenettien within 1 heur*; aperation then continue until 4

perfemmase of the mast required L FisiCTIONAL TEST.

ACTION 40 -

With the ausber of OPERABLE channels less than required by the Ninte s SPERA8LE Channels per Trip Function requirement, piece the inoperable thannel in the tripped confitten within one aev.Whese,5 e

Restore the inoperable channel to OPERABLE status within 7 eays or esclare the assoc 1sted system inoperable.

'The previsions of Specification 3.0.4 are Jiet appitcable.

CLINfon - UNIT 1 3/4 3-38

E 7-rhe.G 9 Proposed Modifications to the RCIC Actuation Instrumentation SVR Standard Technical Specifications 1

i I

8 2.

r % e bz Sk1 4 RCIC Actuation Instrumentation Technical Specification I

4 4

e l

t i

-E 2.

F%c ll' 1

I INSTRUMENTATION i

3/4.3.5 REACT 9R CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUNENTATION

- r LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumentation channels shown in Table 3.3.5-1 shall be OPERABLE with their trip setpoints. set consistent with the values shown in the Trip 5etpoint column of Table 1 3.5-2.

APPLICA81LITY: OPERATIONAL CONDITIONS 1, 2 and'3 with reactor steam j

does pressure greater than (100) psig.

ACTION:

a.

With a RCIC system actuation instrumentation channel trip setpoint-less conservative than the value shown in the Allowable Values column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip 5etpoint value.

b.

With.one or more RCIC system actuation instrumentation channels i

inoperable, take the ACTION required by Table 3.3.5-1.-

?

$URVEILLANCE REQUIRENENTS et y 4.3.5.1 Each RCIC systes actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CNECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALISRATION operations at the frequencies shown' in Table 4.3.5.1-1.

l

~

t 4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be perfereed at least once per 18 months.

l l

1 GE-sTs (swr /4) 3/4 3-46 j

d o7 TABLE 3.3.5-1 0

[

EACTOR CEE ISOLATICII COOLIIIG SYSTEM ACTUATION INSTRISENTATION MINIOGSI OPERABLI CHAleElg*I FemICTIGIAAL INitT5 PER 1 RIP SYSTEM ACTION a.

Reacter Wessel tenter Level - (Lew Law. Level 2) 2 50 b.

Reactor Wessel lister Level - Illgh, Level (8) 2(b) 51 c.

Condsesete Storage Tank 1 Aster Level

. Low (2)ICI 52 l-d.

Sgpressten Peel tester Level - Nigh (2)I*I 52 e.

Insanel Inittetten (1)/(systee)IdI (53) b eg (a) A channel may be pieced in en inoperable states for up to A hours for required servelliance without.

placing the tely system la the tripped conditten provided at least one other OPERAtt.E channel in the same trip system is senttering that parameter.

(b) One trip system with tue-out-of-tue logic.

(c) One tely system with one-out-of-tue logic.

(d) One trip system with one channel.

{IN A

. wm-

e,

+--w-

---mm-m e

ew m

e a

r m-am,_s-m

.a w.

~a-_,_,_---a.--

.a.

P i

E

& ?-

E%LE \\b l

}

TA8tE 3.3.5-1 (Continued) l REACTOR CORE !$0LAT!0N COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION 50 -

With the number of OPERA 8LE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement:

i a.

For one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within one-4eeef or declare the RCIC system inoperable.

V havr.5 b.

For both trip systees, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERABLE channels less than required by the sinteum OPERABLE channels per Trip System requirement, declare the RCIC system inoperable.4, Min 2ff houF,,

l ACTION 52 -

With the number of OPERA 8LE channels less than required by the i

Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable-channel in the tripped condition within onr4 eur or declare the RCIC system inoperable.

e2 4 hoJr.b ACTION 53 -

With the number of OPERABLE channels one less than required by r

the Minimum OPERABLE Channels per Trip systes requirement,

{

restore the. inoperable channel to OPERABLE status within i

(O M um or declare the RCIC system inoperable,

$/V hoJW.S 1

i l1

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d GE-sTs (Swn/4) 3/4 3-As

)

b Pae.c I 4-i 6

d W W 5I e

5 G

2

~ ~

n E lE ^@

^

E g

rE_w i

^'"'^8 v'

I t

5

~

t E

l l

.>I I, _1 W

W W

y s

g g-

^

p iE-.a

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v

=

9 5

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Ie E.b i

35 i

I S"E s

dE l

I sj1 3

a 11ga A

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g j 'g 3

5 5

n gz

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E

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te.

E GE-STS ( N t/4) 3/4 3-49 e

i

~ v ss7 TABLE 4.3.5.1-1

1

[

REACTOR W I$stATISII COOLIIE SYSTEM ACTWil011 INSTWINNTAT1911 SURWILLANCE REQIllREMNT5 w

I CHMBEL 1

CNMOIEL FINICTIONAL CHMSEL Fi3ICTitNIAL IAIITS CHECK TEST CAL 193fl0II e.

Reactor Wessel Mater Level -

7Q (Lew Law. Level 2) 5 a

T$

b.

neector vessel Water 5

a Level - Ni p, Level (8) c.

Condnesete Storage Teok 7-G (R)

Level - Law (5)

M y

d.

Segeressten Peel Water Level -

Q Ns*

-(5)

=

m e.

Stensel Inftietlen 11 4 (M*I) (R) 11 4 h

((e) Hammel faltletten switches shell be tested at least once per 18 months delag shutdeun. All other circuitry assectated with mensel inttletten shall receive a CBIMEIEL FINICTIN TEST at least once per & days as port of circuitry regelred to be tested for automatic system actuetten.)

R P

PA q

m

.- u

.. ~.

.-.,......m e-...

m.-,-.v.

...-+s.

..._,w

_%,,...,_-.,,-s_.

-.,w,.--.m

-ww 7,

..+.. -,.

EL Puc \\ s BWR 5 RCIC Actuation Instrumentation Technical Specification 9

3 9

f a

.--_-.~.

I 01.2.

Pat E 11 t

INSTRtMENTATION i

3/4.3.5 REACTOR CORE ISCLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LINITING CON 0! TION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) systan' actuation instrumenta-tion channels shown in Table 3.3.5-1 shall be OPERABLE with their trip set-points-set consistent with tho' values shown in the Trip 5etpoint column of 1

Table 3.3.5-2.

APPLICAgILITY: OPERATIONAL-CO W ITIONS 1, 2 and 3 with reactor-steam does pressure greater than (100) psig.

{

t ACTION:

With a RCIC system actuation instrumentation channel trip setpoint a.

less conservative than the value shown in the Allowable Values colian of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjustedconsistentwiththeTrip5etpointvalue.

b.

With one or more RCIC system actuation instrumentation' channels-inoperable, take the ACTION required by. Table 3.3.5-1.

SURVEILLANCE REQUIRENENTS 4.3,5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CNANNEL DECK, CNANNEL FUNCTIONAL 4

TEST and CN4felEL CALIBRATION aperations at the frequencies shown in Table 4.3.5.1-1.

4.3.S.2 LOGIC SYSTEM FINICTIONAL TESTS and simulated avtamatic operation of

-1 all channels shall be perfereed at least once per 18 months.

- i i

GE-STS (SWR /5) 3/4 3-45

---+%T

+

s+

-=

y

,cw-

-=

P g-rw

-9t3

~

T

Y R

.k TASTE 3.3.5-1 3

MAC10R CORE ISOLATICII COOLING SYSTEM AcillAT1011 IIISTRISENTATI0lt MINIIRpt 5

OPERABLECHAleEt{*)

FINETICIIAL IAIITS PER TRIP SYSTEM ACilON a.

Reacter Wessel Water Level - (Low tow, tevel 2) 2 50 l

b.

Reacter Wessel tester Level - Nigh 2(b)

$g c.

r--te storage Task unter tevel - tow (2)(C) 52 i

d.

Sgpression Pesi Meter level - Nigh (1)IdI 52 l

e.

Namuni Initiatten (1)/(system)(d) 53 l

k G

T (a) A channel may be placed in an lamperable status for g tetheurs for regelred serveillance without placing the trip system in the tripped conditlen provided at least one other OPERASLE channel in the same tely system is monitoring that parameter.

(b) One trip system with tue-est-of-tas logic.

(c) One trip system with one out-of-tme logic.

(d) Slagte channel.

{Ch N

m t

--.----.e

.-.---- - -.- - -----a. --.

.. ~.

em

62.

FA4G R TABLE 3.3.5-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION 50 -

With the number of OPERA 8LE channels less than required by the Minious OPERABLE Channels per Trip System requirement:

For one trip system, place the inoperable channel in the a.

tripped condition within one-4teer or declare the RCIC system inoperable.

JLy M3 b.

For both trip systems, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERA 8LE channels less than required by the minimum OPERABLE channels per Trip system requirement, declare theRCICsystaeinoperablew,gyf, peg _h,gn ACTION 52 -

With the number of OPERAELE channels less then required by the Minism OPERABLE Channels per Trip System requirement pl atleastoneinoperablechannelinthetrippedconditIonace within ses-4 tour or declare the RCIC systes inoperable.

M hoa o ACTION 53 -

With the n eber of OPERABLE channels one less than required by.

I the Minimum OPERA 8LE Channels per Trip System requirement, restore the inoperable channel to OPERA 8LE status within

)

9 ) t r; or declare the RCIC system inoperable.

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TABLE 4.3.5.1-1 l

h KAC15 W ISOLATIM COOLIIE SYSTEM ACTUATICII INSTMBENTATION SURVEILLANCE REQUIREMENTS OWWEEL 5

OWWEEL FUNCTIONAL DWUSEL FIAEileNAL WIT 5 CHECE TEST CALIORATICII s.

Reacter Unseel linter Level -

>Q R

I (te. ten,teesi n 5

a b.

Reacter Wessel IAutor 5

M

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f tevel - Nid c.

Condensate Storage Tank Level - Law (5)

M (R) l 2:'

d.

Segeression Peel lister Level -

Nigh (5)

M

>Q (R) l e.

Manasi Initiatten IIA

/*I y IIA b

l (a) nunmal Initiatten switches shall be tested at least once per le months during shutdown. All other circuitry asseclated with sammel inttlatten shall receive a DIAIBEL FtBICileNAL TE51 at least once per% as part of cleteltry reelstred to be tested for setenotic systen actuation.

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_IN5TRUMENTAT10N 3/4.3.5 REACTOR CORE !$0LATION COOLING SYSTEN ACTUATION INSTRtstflffATION LIMIT!wG CONDITION FOR OPERATION i

i 3.3.5 The reactor core isolation cooling (RCIC) systas actuation instrumenta-tien enannels shown in Table 3.3.5-1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint esl en of Tante 3.3.5-2.

APPLICA81LITY: OPERATIONAL CONDITIONS 1, 2 and 3 with reacter steam esse pressure greater than (100) psig.

ACTION:

With a RCIC systas actuation instrumentation channel trip setpoint a.

less conservative than the value shown in the A11eueble Values column of Table 3.3.5-2. declare the channel Insperable until the channel is restored to OPEAASLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, With one er more RCIC systes actuation instrc entation channels b.

inoperable, take the ACTION required by Table 3.3.5-1.

SURVIILLANCE REQUIRDENTS 4.3.5.1 fach RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the perfeveance of the CMWelfL DECK, DIMEIEL FUNCTIONAL TEST and CHANNEL CALIBRATION aperations at the frequencies shown in Table 4.3.5.1-1.

4.3.5.2 LAGIC SYSTDI FUNCTIONAL TESTS and simulated avtaastic operation of all channels shall be performed at least esce per 18 months.

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TABLE 3.3.5-(continued)

REACTOR GDRE 150 "0N C00LLbG SYSTEM ACTUATION INF RURENTA" ION

-I ACTION 50 -

with the nemmer of OPERA 8d channels less tRan required by the Minfeum OPERA 4d Channels per Trip nystas requirement:

Qu. m t" -

1 Y

a.

':- ^^: U 4.,. _

Pface the inoperable channe1 W h y

^2 ^...,,.,. : _ in the tripped senditten within one-move er declare the E!C system fraperele.

26l have,5 w'hL m W H ^ % - & ' ;^ !*o t.

': L ;..^. m :s:^ -. declare the E!C system inoperable.

X ACTION 51 -

With the neber of OPERA 83 channels less than required by the Rinfeus OPERA 83 channels per Trip System regut t, declare t,e E r c s y s t t aa p. r. i e s. m a %.

i g

ACTION 52 -

with the neber of OPERA 8 d channels less than reestred by the Ninfaa OPERA 83 Channels per Trip System requirement, place at least one faeper e channel in the tripped conditten

{

within $:Yheur:b re the E!C systas insperable.

. U 1

- t c or P

l ACTION 53 -

With the number of OPERA 8 3 channels less than required by the Rinfem OPER483 Channels per Trip System requirement, restare j

the inoperable channel tm OpfRA8 3 status within 'O 1:r. er esclare the E!C systas inoperable.

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BVR 6 (Clinton) Solid State RCIC Actuation Instrumentation Technical Specification h

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REACTOR CORE ISCLATION COOLING SYSTEM ACTUAT10N Iw$TeuM

,I 3/a.3.5 4

_ LIMITING CONDITION FOR OPERATION l

The reacter core isoletten cooling (RCIC) system actuation instruments-j points set consistent with the values shown in the Trip $4tpein 3.3.$

1 Tamle 3.3.5-2.

i OPERATIONAL CONDITIOe:S 1, 2, and 3 with reacter stese eene j

APPLICABILITY:

pressure great,er than 150 psig, l

~

1 t

M:

l With an RCIC system actuation instrumentation channel trip l

a.

3.3.5-2, dociare the channel inoperable until the channel is res l

I Setpoint value.

With one or more RCIC systes actuation instrumentation channels

.j inoperable, take the ACTION required by Tatie 3.3. F 1.

i t.

1-i EurvtILLarE RfoUI2iMai$

Each RCIC systes actuation instrumentation thennel shall to doesn-TEST and CHANNEL CALIS4ATION operations at the fregu 4.3.5.1 j

4.3.5.1-1.

LOGIC SYSTEN RAICT! ANAL TEST $ sha11 to perfereed at least once per A11 ACIC actmetten system logic shs11 to manually tasted 4.3.5.2 independent of the SELF TEST SYSTIM such that all trip functions are tasted 18 asnths.

l at least once every feve fuel slycles.'

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" Manual testing' for the purpose of satisfying Specification outage.

3/4 3-58 CLINTON - UNIT 1 i

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TA8tf 3.3.5-1 (Continued)

REACT 0s CosE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION-TABLE NOTATIONS I

h (a) A channel aey be placed in an inoperable status for up te { hours for l

1 l

required surveillance without placing the trip systee in the tripped condition provided at least one other OPERA 8LE channel in the same trip

}

systes is monitoring that parameter.

(b) Two trip systems with two channels per trip system.

f (c) One trip system with two-out-of-two logic.

l (d) One trip systan with one-out-e(-two logic.

(e) One trip system with one channel.

i 1

M ACTION 50 -

With the ne ber of OptRA8LE channels less than required by the Mintaum OptRABLE Channels per Trip $rstas requirement:

i e

piece the inoperable channel (s) ana/er For 1 trip systes i

a.

thattripsysteeInthetrippedcondittenwithinone-eeer

/

er declare the RCIC systes inoperable.

J4 hove'b

~

b.

For bot.h trip systems, declare the E!C system inopereele.

J ACTION $1 -

With the as ter of OptRASLE channels less then required by the stes requirement, declare Matsum OptAA8LE channels per Trip Sy?f/ how.6.

the K!C system inoperableAs/,44!i e 4

l ACTION 12 -

With the na ber of OptRASLE channels less then voguired by the piece Mnimum OptRABL1 Channels per Trip Systas requirement et least one tasperable channel in the tripped conditlen within 4 toer er declere the K!C system inoperstle.

3+ haveb ACTION 53 -

with the ember of OptRABLE channels less then required by the I

Winimum OptRASLE Channels per Trie Systas requirement, restere

{

the inoperable channel ta OptRA8Lt status within 4 4eere er i

declare the K!C system inoperable.

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GE Nuclear Energy N.'$5$0m::s::s l

June 25, 1990 MFN 071-90 OG90-579-32A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Millard L. Wohl Technicti Specification Branch

Subject:

Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Analysis

Reference:

NEDC-31677P, " Technical Specification Improvement Analysis i

For BWR Isolation Actuation Instrumentation", June 1989.

The purpose of this letter is to provide you with updated information relating to the implementation of the proposed allowed outage time (A0T) given in the Reference report. Appendix D of the Reference report provided an example of an isolation actuation instrumentation technical specification modified to reflect the proposed A0T changes. Two items were identified during the NRC review of the Isolation Actuation Instrumentation section of the Improved BWR Technical Specifications that can enhance the implementation. The following is a discussion of these enhancements including proposed technical specification modifications:

a)

Insert A to Section 3.3.2b of the revisions to Isolation Actuation Instrumentation Technical Specification (page D2 of Reference),

covered actions to be taken when placing an inoperable channel (s) in the tripped condition that would cause isolation'(Condition 1) or would ng1 cause isolation (Condition 2). A question arose concerning whether these two conditions could be covered by a single action statement.

The analysis given in the Reference supports the same A0T for both Conditions 1 and 2.

The primary reason for specifying two A0Ts was to.

retain the current technical specification fomat. There were no strong technical reasons for retaining the two A0T conditions.

Therefore, it is proposed that the two conditions given in Insert A be combined into one condition as follows:

Insert A to Section 3.3.2b Delete Section 3.3.2b and replace with the following:

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, either 4hWf D h f

0(290-514-Rb 6+

fA< G 2-1) place the inoperable channel (s) in the tripped condition within a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions comon to RPS Instrumentation, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not comon to RPS Instrumentation.

or 2) take the ACTION required by Table 3.3.2-1.

The prnvisions of Specification 3.0.4 are not applicable.

b)

Action c in Section 3.3.2 states: "With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requ u:=_..i for both trip systems, place at least one trip system in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1."

Placing the trip system in the tripped condition could potentially isolate an important system and therefore may not be the best action. A more appropriate action in some cases may be to trip a single channel without tripping the system. This change will reduce the overall number of potential isolations. Therefore the following modification is proposed:

Replace Section 3.3.2c with the followino:

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, 1)

Place the inoperable channel (s) in one trip system in the tripped condition within one hour and 2) a)

Place the inoperable channel (s) in the remaining trip system in the tripped condition within (1) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation, and (2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation.

or b) take the ACTION required by Table 3.3.2-1.

The provisions of Specification 3.0.4 are not applicable.

Delete

Insert B to note Referenced in Section 3.3.2 Action c 9.

.~.

l awsn.m n

1

%E-3 0P 3 t

1 We feel the above changes can enhance the overall modifications to the Isolation Actuation Instrumentation Technical Specification. Please give one of us a call if you should have any questions.

i Very truly yours, i

3 Y Dimb s

W.PISullivan J. F. Klappro't1 Reliability Engineering Services BWR Owners' Group Programs M/C 789 (408)925-6992 M/C382 (408)925-5434

.h I

'h cc: BWROG Technical Specification Committee - B BWROG Primary Representatives of Participating Utilities

~

G. J. Beck, BWROG Chairman R. D. Binz, BWROG Vice Chairman S. D. Floyd, RRG Chairman L. S. Gifford (GE Rockville)

S. J. Stark (GE)

A. E. Rogers (GE)

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EFCLOSURE 5 I

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Es)Lt.o nres-5 can BWn OUJNERS' GROUP O

Pas I o e (o

'"'"" "25?#7%

clo Soutbom Nudeor Operoting Company

P.O. Box 1995. Bin 8052 Birminghom. At 35201 BWROC-92102 November 4, 1992 Brian K. Crimes, Director Division of Operating Reactor Support Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention: Christopher I. Crimes, Chief Technical Specifications Branch

Subject:

BVR OWNERS' CROUP (BWROG) TOPICAL REPORTS ON TECHNICAL SPECIFICATION IMFROVEMENT ANALYSIS FOR BWR REACTOR PROTECTION SYSTEMS - USE FOR RELAY AND SOLID STATE FLANTS (NEDC-30884 AND NEDC-30851F)

Reference:

Letter, C.E. Rossi (NRC) to C.J. Back (BWROC), same subj ect,

dated July 26, 1991

Dear Mr. Grimes:

In the reference letter the NRC expressed concern that model TS ACTION "a",

proposed in NEDC-30851P A, would allow continued plant operation for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with a combination of failures that could prevent a reactor scram function from completing its logic when called upon (i.e., loss-of-function).

This could occur for a relay-type plant if, for example, both channels of the high reactor pressure function (which has a one-out-of two-twice logic) were inoperable in one trip system. The reference letter also noted that the BWROC was preparing clarifying language (i.e., revised model TS ACTIONS) to address this concern, and to be used as an industry standard in future amendments implementing the RPS topical report.

In re sponse. to the above, the BWROG has worked with Carl Schulten of your Staff to develop the model TS ACTIONS provided in Enclosure 1.

The indicated i

changes to ACTIONS 3.3.la and 3.3.lb and their footnotes ensure that appro-priate actions are taken to avoid an extended loss-of-function period in any RFS Functional Unit.

A discussion of the application and justification for the revised model TS ACTIONS is provided in Enclosure 2.

4,2141703/4 pg

J P

-5 6

'B.K. Grimes NRC FAc. E 7. -

BWROG 92102

' November'4. 1992-Page 2 The enclosed information has been endorsed by a substantial number of the members of the BWROG; however, it should not be interpreted as 'a commitment of any individual member to a specific course of action.'

Each member must formally endorse the BWROG position in order for that position to become the member's position.

Very truly yours, C. L. Tully, Chairperson BWR Owners' Group EXEC 6T/CLT/JDF/rt Enclosures 2

~

cc: CS Schulten (NRC) 1A England, BWROC Vice Chairman BWROC Primary Representatives of Participating Utilities BWROG Technical Specifications Comeittee-D LS Gifford, GE SJ Stark, CE 4

1

. l 6

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65 rw 3 BWROG 92102 NEDC 30851P-A ENCLOSURE l' November 4, 1992 Table 5-9 CHANCES TO REIAY RPS TECHNICAL SPECIFICATION 3/4.3 INSTRUMEFTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

)

f_IMITING CONDITION FOR OPERATION

)

3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM

'l RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:gINSERT 1

{a.

W the numbe of OPERAB channels le than requir by the Mini

)

ERABLE Cha is per T p System req ement for o trip systes' place

'I the inoper e channe s) and/or trip systes n the trippe l

conditio within hours.

provisions Specificat 3.0.4 are no applicable b.

Vi the numbe f OPERABLE nnels less required the Min l

0 LE la per Trip ystem requir nc for both rip syst lace at le e one trip stem ** in the ripped cond on withi one hour

_ and take the ACTION req ired by Table

.3.1 1.

d

~

SURVEILIANCE REDUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL F1JNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1 1.

4.3.1.2 IDCIC SYSTEN PUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 e nths.

1NsERT 2.

-y Pan

-verable

.s.1 ne not be pl ed in the ipped co tion wher his wo d cause Trip tion to r.

In th e cases, inopera annel sh he rest ed to 0F LE status thin it,,,

urs or_th CTION equired Table'3..1-1 for e Trip ion she taken.

If more hannels a inoperab in one tr system in the er. pl e the e p system th more i erable c is in e tripped tio (exc t when th would ca the Trip tion occur.

gult o3W

/?*

5-33

s..

a

e. 5 PM Q BWROG-92102 ENCLOSURE 1 November 4, 1992-(continued) l

)

l i

INSERT 1 With one channel required by Table 3.3.1-1 inoperable in one or more I

a.

Functional Units, place the inopertsble channel and/or that trip' system in j

the tripped condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

[The provisions of Specification 3.0.4~are not applicable.]-.

b.

With two or more channels required by Table 3.3.1-1 inoperable in one or I

more Functional Units:

1.

Within one hour, verify sufficient channels remain OPERABLE or.

tripped

to maintain' trip capability in the Functional Unit, and 2.

Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the inoperable channel (s).in one trip system and/or that trip system ** in the tripped condition *, and t

3.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other-trip system to an OPERABLE' status or tripped *,

t otherwise, taka the ACTION required by Table 3.3.1-1 for the Functional-j Unit.

.,e

?

INSERT 2:

An inoperable channel or trip system need not.be placed.in the tripped condition where this would cause the Trip Function to occur. 'In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall be taken.

/

I

- This ACTION applies to that trip system with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION can he applied to either' trip system.

+

.t t

i h

t I

i:: 5

%G5 BWROG-92102 ENCLOSURE 2 November 4, 1992 Anolication and Justification for Chances to NEDC-30851P-A. Table 5-9 for ACTION 3.3.la, with one channel required by Table 3.3.1-1 inoperable in one or more Functional Unit (s) (i.e., any number of Functional Units having only one inoperable channel in each Functional Unit), the entire RPS scram capability remains intact, assuming no additional single failure. Therefore, a loss-of-function is not possible for the rewritten ACTION 3.3.1.a.

The action that allows continued operation for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months was evaluated and the reliability of the system shown to be acceptable in NEDC-30851P-A.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the inoperable channels and/or trip systes must be placed in the tripped condition, This action restores the RPS capability to accommodate a single failure and allows operation to continue with no further restrictions.

If the inoperable channel (s) and/or trip system is not placed in the tripped condition within the required time (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for ACTION a),

then the ACTIONS required by Table 3.3.1-1 must be taken, which require the operators to take actions to compensate for the inoperable RPS channels' function.

For ACTION 3.3.lb, with two or more channels inoperable in any Functional Unit, the Reactor Protection Systes ELY not be capable of perfoming its intended function (i.e., a " loss of scram function" say exist), depending on which two (or more) channels are inoperable.

In this condition, during the period allowed to place the inoperable channels and/or trip systes in the tripped condition, if a valid trip signal was received, a failure to produce a scram signal for that Functional Unit could result. Therefore, ACTION b.1 requires that steps be taken within one hour to ensure the Functional Unit maintains trip capability. This one hour period allows the operator time to evaluate the situation and to repair or trip the channels. One hour is reasonable considering the diversity of sensors available to provide trip signals, and the low probability of an event requiring the initiation of a scram. One hour is also consistent with the current Technical Specification requirement for placing inoperable channels in the tripped condition.

In addition, if it has been verified that a loss-of-function situation does not exist, an allowance of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is provided by ACTION b.2 before the operator is required to place the inoperable channel (s) in one Trip System (or one entire Trip Systes), in the tripped condition. This 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months requirement limits the time the RPS scram logic for any Functional Unit may be degraded in both Trip Systems. Six hours is considered acceptable based on the remaining capability to trip, the diversity available to provide trip signals, the low probability of extensive numbers of inoperabilities affecting all diverse functions, and the low probability of an event requiring the initiation of a

1 EE 53 Pr>4 G Lo 0F &

BWROG 92102 ENCLOSURE 2 November 4, 1992 (continued) b scram. By the end of the six hour period, the ACTION b.2 requirement that one

-Trip System will have its inoperable channels placed into the tripped condition provides a similar level of RPS availability as found in ACTION a above, and evaluated in NEDC-30851P-A to be acceptable for a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowable outage time.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , per ACTION b.3, all the inoperable channels in the other trip system will have been restored to OPERABLE status, or else the inoperable channels will be placed in trip. For all of the proposed ACTIONS, if the inoperable channels are not placed in trip within the applicable required time (1, 6, or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ), then the ACTIONS required by Table 3.3.1-1 must be taken, which requires the operators to take actions to compensate for the inoperable RPS channels' function.

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ML20059G843

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