ML20099M303

Rev 1 to Nonproprietary Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series Summary Rept

ML20099M303
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/31/1985
From:	Garber F, Hedrick R, Mobley R TECHNOLOGY FOR ENERGY CORP.
To:
Shared Package
ML19269B255	List: 0CAN038502, Forwards Proprietary & Nonproprietary Rev 1 to R-84-011-NP & R-84-011-P, Summary Rept,Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series. Proprietary Rept Withheld (Ref 10CFR2.790) ML20099M303
References
R-84-011-NP, R-84-011-NP-R01, R-84-11-NP, R-84-11-NP-R1, NUDOCS 8503250159
Download: ML20099M303 (105)

Text

_ _ _ _ _ _ _ _ _ _ _ _ . _ . __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

T 3

TEC Report No. R-84-011-14P

)

SUMMARY

REPORT PHASE I 0F AP&L ICC MONITORING SYSTEM PROGRAM TEST SERIES Revision 1 3

9 Submitted to:

Arkansas Power and Light Company P.O. Box 551 Little Rock, Arkansas 72203 Contract No. T-064-G, Task No. 001A

) TEC Project Team Wayne Garber, Project Manager R. K. Mobley, Project Engineer J

Prepared by: .

Technology for Energy Corporation One Energy Center, Pellissippi Parkway Knoxville, Tennessee 37922

') (615) 966-5856 l

i S T E $$88o3 P PDR January 1985 l

Approved: #fs// M ((A./ Bedefck ,d ! t R'.

F./ Garber 4 _.

I WI d 7/ V ~

R. R,. Mdbley CO . Moor'e' l

l 54.1.84011 L_

q TABLE OF CONTENTS O Section Page

1. INTRODUCTION 1-1

2. AIR / WATER TEST SERIES 2-1 O 2.1 Overall Objectives of the Air / Water Test Series 2-1 2.2 Air / Water Experimental Configuration and Test 2-1 Matrix for Manometer Equalizing Port Testing 2.3 Air / Water Results and Conclusions for Manometer 2-4 Equalizing Port Testing -

2.4 Air / Water Experimental Configuration and Test 2-12 O Matrix for Manometer / RIM Assembly Testing 2.5 Air / Water Results and Conclusions for Manometer / RIM 2-17 Assembly Testing 2.5.1 Results and Conclusions for AW2100 2-17 2.5.2 Results and Conclusions for AW2200 2-20

. 2.5.3 Results and Conclusions for AW2300 2-20

> 2.5.4 Results and Conclusions for AW2400 2-21

3. UPPER HEAD TEST SERIES 3-1 3.1 Overall Objectives of the Upper Head Test Series 3-1 3.2 Upper Head Experimental Configuration and Test 3-1 g

Matrix

• 3.3 Upper Head Results and Conclusions 3-11 3.3.1 Basic Response Patterns During Blowdown 3-11 3.3.2 Differential Pressure Transducer 3-17 Comparisons During Blowdown 3.3.3 Basic Response Patterns During Reflood 3-21 a' 3-26 3.3.4 Differential Pressure Transducer Comparisons During Reflood

4. IN-CORE TEST SERIES 4-1 4.1 Overall Objectives of the'In-Core Test Series 4-1 a 4-1 4.2 In-Core Experimental Configuration and Test Matrix 4.3 In-Core Results and Conclusions 4-6 4.3.1 FPS Sheath Thermocouple Comparisons 4-6 During Blowdown

• 4.3.2 Differential Pressure Transducer Comparisons 4-10 0 During Blowdown 4.3.3 FPS Sheath Thermocouple Comparisons 4-15 During Reflood 4.3.4 Differential Pressure Transducer Comparisons 4-15 During Reflood J

ii1 54.3.84011 L ~..nm

7 TABLE OF CONTENTS (Continued) 3 Section Page

5. REGULATORY REQUIREMENTS COMPLIANc; 5-1 5.1 Compliance with Section II.F.2 of NUREG 0737 5-1 5.2 Compliance with Regulatory Guide 1.97 5-5

6. OVERALL CONCLUSIONS 6-1 O

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3 LIST OF TABLES O Table Page 2-1 Manometer Port Patterns Tested in the Air / Water Test 2-5 Series 2-2 Sensor Steady-State Outputs in Stagnant Air and Lcw-Flow 2-18 0 (6.55 in./ min) Water at 120 W RIM Heater Power 2-3 Sensor Time Constants in Stagnant Air and low-Flow 2-19 (6.55 in./ min) Water at 120 W RIM Heater Pcwer 3-1 Summary of Upper Head Test Series Sensor Arrangement 3-9 g

3-2 Major Upper Head Test Series Parameters 3-12 3-3 Delay Times Until Initiation of Uncovery' Signal During 3-20 Upper Head Test Series for Slow and Fast Sensors Using Differential Pressure Transducers as the Basis

• 3 for Collapsed liquid Level Sensor Crossing Times 3-4 Delay Times Until Initiation of Recovery Signal During 3-29

. Upper Head Test Series foc Slcw and Fast Sensors Using Differential Pressure Transducers as the Basis for Collapsed Liquid Level Sensor Crossing Times -

.)

4-1 Major In-Core Test Series Parameters 4-5 6-1 Performance of Sensor Types 6-4 6-2 Performance of Chamber Lengths 6-5

)

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LIST OF FIGURES O Figure Page 2-1 Manometer Equalizing Port Test Facility Schematic 2-2 2-2 ORNL Airfdater Test Facility Schematic 2-3 0 2-3 Top Manometer Equalizing Port Design Chosen in 2-7 the Air / Water Test Series 2-4 Manometer Efficiency vs. Void Fraction for Port 2-9 Pattern #1 (Table 2-1) - Performance Classified -

Extremely Poor 2-5 Effect of Slot Width (Flow Area) on Manometer 2-10 Efficiency 2-6 Effect of Slot Row Vertical Spacing (Constant Flow 2-11 Area) on Manometer Efficiency ,

2-7 Bottom Manometer Equalizing Port Design Chosen in 2-13 the Airfdater Test Series 2-8 Airfdater Test Series Sensor Types and Locations 2-15 O 2-9 Air / Water Test Series Sensor Designs 2-16

~

2-10 Draining Level Delays at Level 0, Derived frcm AW2300 2-22 Oata 2-11 Filling Level Advances at Level 0, Derived from 2-24 g

AW2400 Data 3-1 ORNL FCTF Schematic 3-2 3-2 Major FCTF Loop Instrumentation 3-4 3-3 Major FCTF Test Section Instrumentation 3-5 3-4 Upper Head Test Series Bundle Cross Section 3-6 3-5 Prototype Sensor Oosigns Used in the Upper Head Test Series 3-8 0 Relative Positions of the Upper Head Test Series Bundle 3-10 3-6 Sensors 3-7 Response of a Slow Sensor to a Medium Rate of 3-13 Level Fall (1.33 ft/ min)

,u 3-8 Response of a Fast Sensor to a Medium Rate of 3-14 Level Fall (1.33 ft/ min) vi 54.2.84011 l

T LIST OF FIGURES (Continued)

O Figure Page 3-9 Response of a Signature of Uncovery Sensor to a Medium 3-15 Rate of Level Fall (1.33 ft/ min) 3-10 Comparison of Collapsed Liquid Level Calculated from 3-18

.) Dif ferential Pressure Transducers POE-T3(3) and POE-T7(7) with the Responses of the Slow Sensors in Rod 2 During Test UH1331 Blowdown 3-11 Comparison of the Collapsed Liquid Level Calculated 3-19 3 from Differential Pressure Transducers POE-T3(3) and POE-T7(7) with the Responses of Fast Sensors in Rod 3 Ouring Test UH1331 Blowdown 3-12 Response of a Slow Sensor to a 1.19 ft/ min Reflood 3-23 Rate 7

• 3-24 3-13 Response of a Fast Sensor to a 1.19 ft/ min Reficed Rate 3-14 Response of a Signature of Uncovery Sensor to a 3-25 1.19 f t/ min Reflood Rate 3 3-27 3-15 Comparison of Collapsed Liquid Level Calculated from Dif ferential Pressure Transducers POE-T3(3) and PDE-T7(7) with the Responses of Slow Sensors in Rod 2 During Test UH2201 Reflood Comparison of Collapsed Liquid Level Calculated from 3-28

) 3-16 Dif ferential Pressure Transducers POE-T3(3) and POE-T7(7) with the Responses of Fast Sensors in Rod 3 During Test VH2201 Reflood 4-1 In-Core Test Series Bundle Cross Section 4-2 3

4-2 Axial Locations of FPS Thermocouples (TC) and RIM 4-4 Sensor Hot and Cold Junctions (CJ) in the In-Core Test Series Bundle. All Dimensions are in inches.

4-3 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-7 3 Response and a RIM Fast Sensor Response at level B Ouring Test IC2501 Blowdown 4-4 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-8 Response and a RIM Slow Sensor Response at Level C Ouring Test IC2501 Blowdown vii 54.2.84011 1

^

LIST OF FIGURES (Continued)

O Figure Page 4-5 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-9 Response and a RIM Signature of Uncovery Response at .

Level 0.0uring Test IC2501 Blowdown 0 4-6 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-11 Response and a RIM Absolute Thermocouple at Level E Ouring Test IC2101 Blowdown 4-7 Comparison of a Fuel Pin Simulator Sheath Thermoccuple 4-12 Response and a RIM Absolute Thermocouple at level F g Ouring Test IC2101 Blowdown 4-8 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-13 Response and a RIM Absolute Thermocouple at level G Ouring Test IC2101 Blowdown 9'

4-9 Comparison of Collapsed Liquid Level Calculated from 4-14 Dif ferential Pr e.sure Transducers POE-T3(3) and FDE-T7(7) with t ,. Responses of the RIM Sensors (Levels B, E - Fo,t; Levels C, F - Slow; and levels 0, G - Signature of Uncovery) During -

a Test IC2501 Blowdown 4-10 Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-16 Response and a RIM Fast Sensor Response at level B Ouring Test IC2501 Reflood Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-17

) 4-11 Response and a RIM Slow Sensor Response at Level C Ouring Test IC2501 Reflood Comparison of a Fuel Pin Simulator Sheath Thermocouple 4-18 4-12 Response and a RIM Signature of Uncovery Response at a Level 0 During Test IC2501 Reflood Comparison of Collapsed Liquid Level Calculated from 4-20 4-13 Differential Pressure Transducers 90E-T3(3) and POE-T7(7) with the Responses of the RIM Sensors (Levels B, E - Fast; Levels C, F - Slow; and 0 Levels 0, G - Signature of Uncovery) During Test IC2501 Reflood l

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i viii 54,2.84011 O

q LIST OF ACRONYMS n ANO - Arkansas Nuclear One AP&L - Arkansas Pcwer & Light Company CDC - Control Data Corporation f) 00E - Department of Energy dp - Differential Pressure ETO - Engineering Technology Division O FCTF - Forc.ed Convection Test Facility FRS - Fuel Rod Simulators FSAR - Final Safety Analysis Report l'

IC - Incore ICC - Inadequate Core Cooling I.D. - Inside Diameter O - Idaho National Engineering Laboratory INEL .

LOCA - Loss of Coolant Accident LWR - Light Water Reactor ,

NRC - Nuclear Regulatory Commission 0.0. - Outside Diameter ORNL - Oak Ridge National Laboratory U

Pa!0 - Piping and Instrumentation Otagram PWR - Pressurized Water Reactor RELAPS - Reactor Linearized Analysis Program, Version 5

~

0 RIM - Radcal Inventory Meter RTO - Resistance Temperature Detector TEC - Technology for Energy Corporation Q

UH - Upper Head tx 54.0.84C11 o

A _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _

O Section 1 INTRODUCTION O

Technology for Energy Corporation (TEC) has contracted w'th Arkansas Power and Light (AP&L) Company to supply an inadequate cert cooling 0 (ICC) system for Arkansas Nuclear One (ANO), Units 1 and 2. TEC and APal designed and conducted an extensive experimental test program on the Radcal Inventory Meter (RIM) to verify ICC capability and compliance with O regulatory requirements, and to provide licensing suport and design data for the system hardware. .

A two-phase test program was conducted at the Oak Ridge National 9 ,

Laboratory (ORNL). Phase I utilized the atmospheric Air / Water Test .

F acili ty . The overall objectives of Phase I were to: .

rm

• Provide basic design data on the performance of various manometer / RIM assembly combinations.

• Select prototype manometer / RIM assembly configurations for addi-tional testing, e Demonstrate that the final prototype manometer / RIM assembly can 0 .

make level measurements in a variety of air / water mixtures and flows, and e Determine the domain of flow and void fraction boundary con-ditions under which the manometer / RIM assembly can provide a unambiguous ICC determination. '

Section 2 provides a detailed description of Phase I testing and a summary of the Air / Water Test Series results.

O Phase 11 utilized the pressurized-water Forced Convection Test Facil-ity (FCTF) at Oak Ridge. The FCTF is a typical reactor simulation V facility and has been used for several Nuclear Regulatory Commission 1-1 54.3.84011

.i

9 l-2 (NRC) programs. It has both blowdown and reflood capabilities with suf-ficient control and instrumentation to simulate a reactor under small break, loss-of-coolant (LOCA) conditions. Phase II testing was con-ducted in two parts:

e Upper Head Test Series and

. In-Core Test Series.

O Two separate test . series were required to simulate the df fferent upper head and in-core thermal-hydraulic boundary condition, in a nuclear reactor during a LOCA.

O ,

The objectives for both the Upper Head and In-core Test Series were to: ..

e Demonstrate that the selected prototype manometer / RIM -

assembly can supply accurate, reliable monitoring of liquid level in the upper head and upper plenum of a reactor; O

e Demonstrate that the selected prototype manometer / RIM assembly can supply accurate, reliable monitoring of the in-core liquid level under low power conditions; e Provide data to determine the boundary conditions (i.e.

.) depressurization rates, flow rates, repressurization rates, etc.) for accurate, reliable, above and in-core monitoring performance; e Confirm that the absolute temperature measurements provide a p reliable indication of above-core coolant temperature in an ICC event; e Provide data on how accurately a RIM ronitors fuel thermal performance; and O e Provide data to finalize the sensor geometry, sensor arrangement, and manometer design for ANO, Units 1 and 2.

Section 3 provides a detailed description of the Upper Head Test Series; U Section 4 describes the In-core Test Series. Each section also provides a summary of the appropriate test results.

54.3.84011 s.

,) .

1-3 Section 5 discusses the tested RIM compliance to regulatory require-n ments. Section 6 provides the results of the three-part RIM test program. The overall conclusions are that all three types of tested RIM ,

sensors meet or exceed the regulatory requirements. Any one sensor type or a combination of two or all three sensor types in conjunction with 1 the. tested manometer should:'

e Maintain their mechanical / electrical integrity, operability, and O performance under small break, loss-of-coolant events; e Respond accurately and reliably to both blowdown and reflood tran-sients and be usable as an ICC warning system when coupled to a data processing system; e Indicate inventory loss' or gain rates as well as inventory itself; ,

e Produce a predictable response; e Trend fuel clad temperatures (via absolute thermocouples); and C) e . Indicate fuel surface heat transfer conditions. .

The ' test data confirms that a complete, RIM-based ICC system in full compliance with regulatory requirements can be provided for ANO, Units 1 o .

and 2.

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54.5.84011~

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Section 2 AIR / WATER TEST SERIES 3

2.1 0'!ERALL OBJECTIVES OF THE AIR / WATER TEST SERIES The overall objectives of the Air / Water Test Series were to:

. Provide basic design data on the manometer / RIM assembly performance, o Demonstrate that the final prototype manometer / RIM assembly can make level measurements in a variety of air / water mixtures 3 and flows,.

. Obtain basic performance data, response time, and fill and drain rates of the manometer / RIM assembly, and

. Determine the domain of flow and void fraction boundary con-

' ditions under which the manometer / RIM assembly can provide unambiguous data.

2.2 AIR / WATER EXPERIMENTAL CONFIGURATION AND TEST MATRIX FOR KAN0 METER EQUALIZING PORT TESTING 3

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2.4 AIR / WATER EXPERIMENTAL CONFIGURATION AND TEST MATRIX FOR -

MANOMETER / RIM ASSEMBLY TESTING The air /w'ater testing of the manometer / RIM tube assembly was performed in the experimental f acility shcwn in Figure 2-2. Water and air were 3

metered ir.to a vertical test section that housed the RIM and its manom-eter. The test section was transparent to allow visual observations.

g The external manometer (shcwn in Figure 2-2) was designed so that when air was bubbled into the test section, no air was induced in the inter-nal ranometer.

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2.5.1 Results and Conclusions for AW2100

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T Section 3 UPPER HEAD TEST SERIES 3.1 OVERALL OBJECTIVES OF THE UPPER HEAD TEST SERIES f

The overall qbjectives of the Upper Head Test Series were to:

. Demonstrate that the prototype manometer / RIM assemoiy can y supply measurements to provide ef fective ICC monitoring of the upper head and upper plenum of the reactor,

. Provide data to, determine the domain of the beundary c:n-ditions [i.e., depressurization rates (break size), initial flow rate sensitivity, and refill repressurization rates] of unam-biguous manometer / RIM assembly ICC monitoring performance,

. Confirm that the manometer / RIM assembly absolute temperature measurement provides a good indication of coolant temperature above the core in an ICC event, and

. Provide data to select the optimum sen'sor types and arrange-ments in the manometer / RIM assembly for ANO, Units 1 and 2.

u 3.2 UPPER HEAD EXPERIMENTAL CONFIGURATION AND TEST MATRIX Depressurization tests of the RIM were conducted in the ORNL FCTF, which

) can simulate a large PWR during a small brea'< event. The test facility is a high-pressure, high-temperature, forced-circulation water loop con-figured as shown in Figure 3-1. The loop can be operated at tem-peratures and pressures up to 650 F and 2250 psig, with a water flow through the test section of up to 50 gpm at variable test-section pcwer inputs of up to about 30 kW.

The FCTF is a typical blowdown test facility composed of a circulating pump (with bypass for flow control), a test section, pressurizer, aeat exchanger, and blowdown line connected to the test section. The test 3-1 54.4.84011

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3-3 section was configured with the inlet piping connected near the bottom of the test section (i.e., no internal downcomer was simulated). The .

blowdown line was connected to the top of the test section to simulate hot leg break.s. Two rupture disks with a nitrogen buf fer were used to create primary system breaks. An orifice assembly downstream of the rupture disks determined the break size.

The FCTF has the necessary instrumentation to monitor a small break LOCAs The major instruments monitoring the loop and test section are shown in Figures 3-2 and 3-3. The following standard instrument designations are used:

PE - Pressure POE - Dif ferential Pressure r

TE - Temperature FE - Flow.

The FCTF data acquisition system records 135 instrument signals every 0.025 seconds.

In the Upper Head Test Series, four manceeter/ RIM assemblies were tested in a bundle configuration as shown in Figure 3-4 This simultaneous testing allowed dire'ct comparison of sensor types and chamber variations during the testing sequence and enabled a smaller number of tests to

'~ determine the most effective manometer / RIM assembly design to be util-ized in ANO, Units 1 and 2.

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B

Tabla 3-1 SLA4 MARY OF UPPER llEAD TEST SERIES SCtJSOR ARRAtCCHEf4T (5 - Stos, F - Fast, SU - Signature of Uncovory)

_ __.___..____._ __._._________ __ m , ,

_ =___

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1. froJ S _

Rat 2 Rof 3 ,

Approximaru Appro.imasu Approximato Approx 1mato Approximato Cas Gap C o l.1 Junctim dos Gap Gas Gap Cold Junction Cold Junction Hof Junctica Cold Junction t un.g e t.

Elevarlon a Sonsor Elevatico a Longth Sun sor Etuvattoi*

tipper Host Elevation

• Sonsor Etovation* Longth Sonsor (In Typu itt) (In)

(In) _Tyy> (ft) Typo (ffl Lt on.1 t o L6vot (f11 Typo (ft) 4.

.=

• luru is i t.u conterlino of the stelnl6ss sfco! Lund i o ground pla to.

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3-11 I

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') 3.3 UPPER HEAD RES,ULTS AND CONCLUSIONS 3.3.1 Basic Resconse Patterns During Blowdown The fundamental phenomenon in the test section during blowdown is a loss of inventary frca a two-phase regime covered by single-phase stelm. The primary parameter is rate-of-loss of inventory. The RIMS are separated from the test section mixture by the manometers which permit water -

3 to ficw into the instrument region while inhibiting steam entrance.

This construction provides a better indication of water inventory with the mixture quality inside the manometer during blowdown being primarily a function of depressurization rate.

The respcase of each sensor type (slow, fast, and signature of uncovery) to loss of inventory is indicated in Figures 3-7 through 3-9. (As with all unfiltered experimental data, these figures have noise spikes that should be disregarded.)

)

Figure 3-7 shows the response of a slow sensor to a medium rate, loss-of-inventory case. At this rate, the dif ferent time constants of the differential thermocouple junctions and the decreasing absolute

)

54.2.84011

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3.3.2 Ci f feren-i 31 Pressure Transducer Cortc 2ct sens During Bicwdown 54.3.22011

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FOR SL:'; :.0 FAST SE.'ISORS USI.'iG O!FFERE.'ITI AL PRESSURE TRA iSOUCERS AS THE BASIS FO?. COLLA?SEO LIQut0 LE'lEL SE.'ISOR CROSSI.IG TIMES Slow Sensors Fast Sensors Mi ni mum Maximum Mi ni mum Average level Maximum Delay Time Fall Rates' Delay Time Delay Time Delay Time Tes: (5)

Num'cer (ft/ min) (s) (s) (s)

Sa.1.8a011

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4 3.3.3 Basic Resconse Patterns Durino Reflood 54.3.82011

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F 3-29 Table 3 4 TEST SERIES OEl.AY TIME 5 UMT:L IN: 7tATI0ri 0F REC 0VERY SIGilAL DURING UDPER HEA FOR SLOW A.3 FAST SENSORS USING O!FFERENTI AL PRESSURE TRA:IS00CERS AS THE BASIS FOR COLLAPSED Lt00iG LEVEL SENSCR CROSS!:iG T!'1E5 s

Slow Sensors Fas: S en s.1e s Average level Maximum Mi ni mum Ma xi mum Minimum Test Fall Rates

• Delay Time Delay Time Delay Time Delay Time ilumoer (ft/ min) (s) (s) (s) (s)

• Calculated from the pretest calibrated POE-T7 differential pressure trans-ducer output.

54.1.84011

. - 1.'v 5

9 0

0 54.3.84011

r Section 4 IN-CORE TEST SERIES 4.1 0'lE?,ALL OBJECTI'/ES OF THE IN-CORE TEST SERIES Ine overall cpjectives of the In-core Test Series were to:

. Demonstrate that the prototype RIM sensors can supply ceasure-ments to provide effective ICC monitoring of the reactor core under Icw-power conditions,

. Provida data to determine the boundary concitions on unam:f gucus RIM ICC monitoring performance - depressurization rates (break size), initial flow rate sensitivity, and refill .repressurization,

. Confirm that the absolute temperature measurement provides a gcod indication of ccolant temperature above the core in an ICC event, and obtain data on how closely the RIM reflects fuel

• enermal performance, and

. Provide data to select the optimum sensor types and arrangements in the RIM probe for ANO, Units 1 and 2.

A.2 IN-CORE EXPERIMEllTAL CONFIGURATION AND TEST MATRIX 4-1 52.3.320t1 l -

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46 4.3 IN-CORE RESULTS AND CONCLUSIONS 4.3.1 FPS Sheath Thermoccuole Comoarisons Durina B1cwdown 4 .

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4.3.2 Differential Pressure Transducer comoarisons During Sicwdown 54.2.84011 l

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4 Sec-i2n 5 REGUL.ATO?.Y REQUIRE.ME.'IT5 CCid?LI.17tCE There are two major documents wf':n nica .ne TEC ICC mcni : ring system

.,a. . .*ction ,.lan

( 1 ) .,!L,R n- un -w .-. , ,. . siass'rtcatrco c.

must comply:

Requirements 0 and (E) Regulat:ry Gu':e L.9', " Ins rumentaden far Light '4ater-Cooled fluclear ?cwer ?iants to Assess Piant anc Environs Conditiens Ouring and Foi!cwing an 2:cicent." ine es  ::r: gram described in this documer. does not address all of tae requirements in these documentsc ' acause some of the requirements are related to items

)

other than system performance. The following sections address directly those requirements related to sys em .de 'ccmance wi .h which this tes:

4 i report shows ccepliance and indicate hcw -he TEC ICC monitoring system comolies totally with 1:o-h d: uments.

4 5.1 COMPLIANCE '4ITH SECTICM !!.F.? CF NURE3-0737 The following classification of requirements are from Se: tion !!.F.2, "Instrumentaticn for Detection of Inadequate Core Ccciing," of NUREG-0737.

1. Recuirement: " Design of new instrumentation shculd provide an unambiguous indicatica of *CC. This may recut e new measure-ments or a synthesis of existing measurements which meet design criteria (item 7)."

r-Comoliance:

?

t t

2. Recuirement: "The evaluation i s to include reactor-water-level indication."

1

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. -54.3.84011 1

i, y * , m-,r ,..yr---- ,_e _, , , . ,m ..,,y nm-, --% .,--,-r-,. ,,,,,-w,e, - - - - , . - ,s.,.,-w-y-- ,,--w-,.,v-mw ---,.,,..,wr on- ,,w+,3

5-2 Cemcliance:

3. Recuirement: " Licensees and applicants are required to pro-vide tne necessary design analysis to support the pecoosed final instrumentation system for inadequate core cooling and to evaluate the merits of various instruments to monitor water level and to menitor other parameters indicative of core-ccoling conditions." .

Comolience:

4. Recuirement: "The indication of ICC must be unambiguous in

na: i: sacuid have the following properties: (a) It must indica e the existence of inadequate core ' cooling caused by varicus phencmena (i .e., high-void fraction-pumped flow as well as stagnant bcil-off), and (b) It must not erroneously indica:e (CC cecause of the presence of an unrelated phencmenon."

Ccmciiance:

(a) 54.3.82011

5-2

.s (b)

5. Recuirement: "The indication mus give ac /anced warning of the approacn of !CC."

Comoliance:

e

6. Reouirement: "The indication must cover the full range from normal operation to complete' core uncovery. For example, water-level instrumentation may ' ce chosen to provide advanced warning of two-phase level drop to the top of the core and could be supplemented by other indicators such as in-core and core-exit thermocouples provided that the indicated tem-peratures can be correlated to provide indication of the existence of ICC and to infer the ex ent of core uncovery.

Alternatively, full-range level instrucentation to the bottom of the core may be employed in conjunction with other diverse indicators such as core-exit thermoccuoles to preclude misin-terpretation due to any inherent deficiencies or inaccuracies in the measurement system selected."

54.2.84011

i 3.a Comoliance:

7. Recutrement- "A l l instrumentation in the final ICC system must :e evaluated for conformance to Appendix 3. Desien and Qualification Criteria for Accident Monitoring Instrumentaticn.

as clarified or mocitied by the provisions of items d anc 9 that follow. This is a new requirement."

Cccoiiance:

6. Recuirement: "If a computer is provided to peccess liquid-level signals for display, seismic qualification is not required for the computer and associated hardware beycnd the isolator or input buffer at a location accessible for main-tenance following an accident. The single-f ailure criteria of item 2, Appendix 3, need not apply to the channal beyond the isolation device if it :is designed to provide 99f. availability with respect to functional capability for liquid-level display. The display and associated hardware beycnd the iso- ,

lation device need not be Class lE. but shculd be energized from a high-reliability pcwer source which is battery bac'<ed.

The quality assurance provisions cited in Appendix 3, item 3, need not apply to this portion of the instrumentati,cn system.

This is a new requirement."

Comoliance:

9. Recuirement: "Incore thermocouples located at the core exit or at discrete axial levels of the ICC monitoring system and which are part of the monitoring system should be evaluated for conformity with Attachment 1, Design and Qualification Criteria for PWR Incore Thermocouples, which is a new requirement."

Como 1 i ance_:

Sa.2.8 a011

5-5

10. Recuirement: "The types and locations of displays acc alarms snould be determined by performing a human-f actors analysi s tadfag into consideration: (a} tne use of > this informa.icn by an cperator during both normal and abnormal plant c:ncitions, (b) integration into emergency procedures, (c) integration into cperator training, and (d) other alarms during emergency and need for prioritization of alarms."

Comoliance:

5.2 COMPL(ANCE WITH REGULATORY GUIDE 1.97 Althcugh not adcressed directly in this test progr2m, the TEC ICC system will meet the requirements of Regulatory Guide 1.97. Other quali fica-The folicwing tion program reports are required to document compliance.

is included to give an overview of how the TEC ICC monitoring system will comply with the Design and Qualification Criteria for Instrumentation given in Table 1 (Category 1) of Regulatory Guide 1.97.

1. Eauioment Quali fication Requirement: "The instrumentation should be qualified in accordance with Regulatory Guide 1.89, Qualification of Class IE Equipment for Nuclear Power Plants, and the metnocology described in NUREG-0588, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment _.

Instrumentation whose ranges are required to extend beycnd those ranges calculated in the most severe design basis acci-dent event for a given variable should be quali fied using the guidance provided in Paragraph 6.3.6 of ANSI 4.5.

54.2.84011 .

5-i Quali'ication aoplies to the complete instrumentation channel feca sensor to display where tne display is a direct-indicating meter or recording device. I f the instrumentation channel signal is to be used in a computer-based display, recording, or diagnostic program, qualification applies from the sensor up to and including tne channel isolation device.

Ine seismic portion of qualification should be in accordance witn Regulatory Guide 1.100, Seismic Cuali fication of Electric Ecuiement for Nuclear Pcwer Plants. [nstrumentation snculd continue to read witnin tne required accuracy folicwing, but not 'necessarily during a safe shutdcwn e a -thcuak e . "

Comoliance:

2. Redundancy Recuirecent: "No single Failure within either the accident-men taring instrumentation, its auxiliary supporting features, or its pcwer sources concurrent with the failures that are a concition or result of a specific accident shculd prevent the operators from being presented the information necessary for them to determine the safety status of the plant and to bring the plant to and ' maintain it in a safe condition following that accident. Where f ailure of one accident-monitoring chan-nel results in information ambiguity (that is, the redundant displays disagree) that could lead operators to defeat or fail to accomplish a required safety function, additional infor-mation should be provided to allow the operators to deduce the actual conditions in the plant. This may be accomplished by providing additional independent channels of information of the same variable (addition of an identical channel) or by providing an independent channel to monitor a different variable that bears a known relationship to the multiple chan-nels (addition of a diverse channel). Redundant or diverse channels should be electrically independent and physically secarated fecm each other and from equipment not classified important to safety in accordance with Regulatory Guide 1.75, Physical Indeoendence of Electric Systems, up to and l

5a.'. 32011 1

5-7 inclucing any isolation device. Within each redundant divi-sion of a safety system, redundant monitoring channels are not needed except for steam generator level instru.Tentation in two-lcop plants."

Comoliance: 1 is ,

3. Power Sucoly Recuirement: "The instrumentation should be energized from station standby power sources as provided in Regulatory Guide 1.32, Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants, and should be backed up by catteries wnere T.c.T.entary interruption is not tolerable."

Comoliance:

4. Channel Availability Recufrement: "The instrumentation channel should be available prior to an accident except as provided in Paragraph J.11, Exceotion, as defined in IEEE Std 279-1971, Criteria for Protection Systems for Nuclear Power Generatino Stations, or as specified in the technical specifications."

Comoliance:

l i

54.1.84011 l

5-3

5. Quali v Assurance-Requirere,c- "The rec:cmenda-icns of the fc;lcwing re;ulatory gdices :e .aining to quali y assuracce saduid be fcilcwed:

• Regulatory Guide 1.23 - Quali ty Assurance Procram Recu'rements (0esten and Cons ruc t on )

e Regulatory Guide 1.30 - Quality Assurance Recuiremen s for (Safety Guide 30) cne installa icn. inscec ica, and Tes ina of instrumentation and Electric Ecutament

• Regulatcry Guide !.38 - Quali y- Assurance Recuirements for Pacx ac:nc. Sn:cc:ng. Recet ving, Storage, and Hancling of items for Water-Ccolec Nuclear Pcwer Plants

• Regulatory Guice 1.53 - Qual : #ication of Nuclear ?cwer Pian- inscec icn. Examinat:an, and '

Tes inc ?ersonnel o Regulatory Guide 1.52 - Quali ty Assurance Recuirements for Design of auclear ?cwer ?lancs e Regulatory Guide 1.38 - Collec-icn. 5 crage. and Maintenance of Nuciear ?cwer ?lan- Quality Assurance Recorcs

• Regulatcry Guide 1.!23- Quali y Assurance Recuire.mer.is for

-Ccatra; cf ?racurement of items and Servi es for Nuclear Pcwer ?lants

• Regulatcry Guide 1. lad- Auditine of Quality Assurance Programs for Nuclear Pcwer Plants

. Regulatory Guide 1.146- Qualification of Quality Assurance Procram Auc1t Personnel for Nuclear Pcwer ? l ants Reference to the above regulatory guides (except Regulatory Guides 1.30 and 1.38) is being made pending issuance of a revisicn to Regulatory Guide 1.29 that is under development (Task RS 002-5) and that will endorse ANS!/ASME NQA-1-1979, Quality Assurance Procram Recuirements for Nuclear Pcwer i Plant.

54.3.820l!

..,---v-. .n _,,-,,r__ ,_ .~..m., .-_,,,_m__- ,_ , _ - - _ ,,.,-.m --,..,m.., ,,__,-__-_c_. , , , , , -

5-9 Comoliance:

.s .

6. Disolay and Recording Recuirement: "Continucus real-time disclay shculd be oro-vicec. ine indication may be en a dial, digital cisolay, CRT, or stripchar recorder.

Recorcing of instrumentation readout informaticn sh:uld be provided for at least cne redundant channel.

If the direct and immediate trend or trensient infccmation is essential for cperator information or action, tne recceding should be continucusly available on reduncan: cetica:ed recor-ders. Otherwise, it may be continucusly updated, s:cred in ccmouter tremory, and displayed on demand. Intermittent dis'plays such as data icggers and scanning recceders may be usec if no significant transient response inrcrmauen is likely to ce los: c'y such devices."

Comoiiance:

7. Rance Recuirement: "I f two or more instruments are needed to cover a particular range, overlapping "of instrument span shculd be provided. If the required range of monitoring instrumentation results in a loss of instrumentation sensitivity in the normal operating range, separate instruments should be used."

54.2.84011

.y.

f 4 .,

5-10 Comoliance:

,a t% ,

S. Ecuiccent Identification Recuirement:. '" Types I, B, and C instruments designed as Categories ! and 2.should be specifically ' identified with a commen designation on the control panels so' that the operator

- can easily discern that they are intended for use under acci-dent conditions."

_Comoli ance:

9. Interfaces Recuirement: "The transmission of signals for cther use should ce through -isolation. devices that are designated as part of the -monitoring instrumentation and that meet the pro-visions of this document."

Cocaliance:

54.1.84011 w

,,.ge,. %

I 5-11

10. Servicino, Testina, and Calibrations Recuirement: " Servicing, testing, and calibration programs snculd be specified to maintain the capability of the moni-taring instrumentation, if the required interval between testing is less than the normal time interval between plant snutdowns, a capability for testing during pcwer operation shedid be provided. -

'4henever means for removing channels from service are included in the design, the design should facilitate administrative control of the , access to such removal means.

The design should facilitate administrative control of the access to all setpoint adjustments, module calibration adjust-ments, and test points.

Periodic checking, testing, calibration, and calibration veri-fication should be in accordance with the applicable portions of Regulatory Guide 1.118, Periodic Testina of Electric Power and Protection Systems, pertaining to testing of instrument cnannels. (Note: Response time testing not usually needed.)

Ine isolation of the isolation device should be such that it wccid be accessible for maintenance during accident conditions."

Cemcliance:

54.2.32011

r 5-12

11. Human Factors Recuirement: "The instrumentation should be designec to f acil-teate ne recognition, location, replacement, repair, or adjustment of mal functioning components. It is designed to be highly reliable with minimal repair or adjustment. Faults are readily identified through the sensor functional chec'<s and toe'0A3 se: f-diagros .ic sof tware. The OAS modules and equip-ment casine. are cesigned for easy replacement or repair."

Comoliance:

12. Direc- Measurement Recuireme  : "To the extent practicable, monitoring instru-menta.ica inpu s should be from sensors that directly measure the desired variables. An indirect measurement should be made only when it can be shcwn by analysis to provide unamoiguous informaticn."

Como ! i an ce :

54.3.31011

1 Section 6 OVERALL CONCLUSIONS The besactn of tne parameter soace in the Air / Water, Upper Head, and In-core Tes; Series was significant. Variations in blowdown rate, reflood rate, initia? temoerature, and initial flow were included. Furthermore, three sensor types and three chamber length variations within two of the senscr types were tested. The overall conclusions are:

. All RIM probes maintained their mechanical integri ty, operabili ty ,

and performance throughout the tests,

. All RIM sensor types respond well to blowdown and reflood transients and could be utilized as ICC warning devices with relatively simple type-specific data processing, e Inventory loss or gain rate can be determined in addition to inventory, e inere is no practical dif ference in response of RIM rods con-taining di f ferent numbers of sensor locations

. The response of the sensors is predictable, including variations in absolute temperature and flow, e Absolute thermoccuples in the RIM rods can be used to trend fuel clad temperature, and

. RIM sensors in the instrument guide tube can be used to indi-cate fuel surface heat transfer conditions.

All the sensors tested meet the NRC Regulatory Requirements on perfor-mance (Section 5). The "best" sensor design can, therefore, be selected from all the types tested on the basis of optimizing the combination of performance parameters for a particular application. The performance parameters to be considered are:

6-1 54.2.84011 l

6-2 Tracking Collaosed Licuid Level: - Ine capability of the sensor to respond dramatically and quickly to the passage of a liquid / vapor interface.

Solashing Sensitivity: - The capability of the sensor to maintain a stable uncovered alarm state under surface splashing phenomena.

Sicnal Ocubling Time: - The time it takes for the signal to double in magnitude af ter uncovery. This is the alarm generation time delay (fast and slow sensors) af ter liquid level passage.

Uncovery (310wdcwn) Signal / Initial Signal: The ratio of the dry output signal to the initial wet signal. The greater the ratio, the more obvious the uncovered state and the easier it is to interpret.

Recovery (Reflood) Signal / Initial Signal: The ratio of the wet output signal af ter the sensor has been dry to the initial wet signal. After having gone through a blowdown and reflood tran-sient, the temperature'of the sensor will be decreased and this ratio is an indication of how closely the final wet state approaches the pre-transient wet state.

Maanitude of Initial Signal: The larger the initial signal, the easier it is to process and the less the uncertainty (%) in its magnitude.

54.1.84011

6-3 Accuracy as a Rate Monitor: The capability of a sensor to be used as a rate of level fall or rate of level rise meter. This capabi-lity wculd alicw an operator to calculate the amount of time he had to take action before ICC occurred or to calculate the amount of s ,

time it would take to reflocd a portion of the vessel.

Absolute Temcerature Sensitivity: The change in the output signal due to changes in absolute temperature. An instrument which was very sensitive could give unreliable information in temperature transients. The worst effect on any RIM sensor type is about 27%

of signal.

Flow Sensitivity: The change in the output signal due to changes in flow. An instrument which was very flow sensitive could give unreliable information in flow transients. The flow sensitivity of the RIM sensors is that which is related to flow-induced changes in heat transfer coefficient. These changes are orders of magnitude smaller than those related to uncovery from a wet state.

Since all the sensor variations tested meet the regulatory requirements, only a relative scale is needed for optimization. Best in a performance parameter category is indicated by a 1 and worst by a 3. Utilizing all the data from the tests and this relative scale, the comparison of the performance of the sensor types is presented in Table 6-1. The compari-son of the performance of the chamber lengths is presented in Table 6-2.

The categories are ordered in importance from the most important at the top to the least important at the bottom of the tables. Based on 54.3.84011

V ia Iable 5-l PERFOR.MAtlCE OF SE.'ISOR TYPES (t = 3est, 2 = Middle, 3 = Worst)

Signature Category Sicw Fast of Uncovery Tracking Collapsed Liquid Level Splashing Sensitivity Signal Doubling Time Uncovery (Blowdown) Signal / Initial Signal Recovery (Reflood) Signal / Initial Signal ,

Magnitude of Initial Signal Accuracy as a Rate Monitor Absolute Temperature Sensitivity Flow Sensitivity 54.1.8a011

6-5 Table 6-2 s

PERFORMA.' ICE OF CHAMBER LENGTHS (i = Sest, 2 = Middle, 3 = Wors t) s .

Length (inches)

Cat egory 0.75 1.00 1.25 Tracking Collapsed Liquid level Splashing Sensitivity Signal Ocubling Time Uncovery (31cwdown) Signal / Initial Signal Recovery (Reflood) S'ignal/ Initial Signal .

Magnitude of initial Signal Accuracy as a Rate Monitor Absolute Temeerature Sensitivity Ficw Sensitivity i

Sa.l.3a011

6-6 I

54.3,84011 i

t