NUREG/CR-2826, 'Experiment Data Report for Loft …Experiment L2-5 simulated a double-ended offset shear of a cold leg in the primary coolant system. The primary coolant pumps were

NUREG/CR-2826 1111111111111111111111111111111111 ~ 1111111111

EGG-2210 Distribution Category: R2

EXPERIMENT DATA REPORT FOR LOFT LARGE BREAK LOSS-OF-COOLANT EXPERIMENT L2-5

Paul D. Bayless Janice M. Divine

Published August 1982

EG&G Idaho, Inc. Idaho Falls, Idaho 83415

Prepared for the U.S. Nuclear Regulatory Commission

Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570

FIN No. A6043

\ ABSTRACT

Selected pertinent and uninterpreted data from the third nuclear large break loss-of-coolant experiment (Experiment L2-5)' conducted in the Loss-of-Fluid Test (LOFT) facility are presented. The LOFT facility is a 50-MW(t) pressurized water reactor (PWR) system with instruments that measure and provide data on the system thermal-hydraulic and nuclear conditions. The operation of the LOFT system is typical of large [ -1000 MW(e)rcommercial PWR operations.

Experiment L2-5 simulated a double-ended offset shear of a cold leg in the primary coolant system. The primary coolant pumps were tripped within 1 s after the break initiation, simulating a loss of site power. Consistent with the loss of power, the starting of the high- and low-pressure injection systems was delayed. The peak fuel rod cladding temperature achieved was 1078 ±'13 K. The emergency core cooling system re-covered the core and quenched the cladding. No evidence of·core damage was detected.

"

\

FIN No. A6043-LOFT Experimental Instrumentation

ii

SUMMARY

Experiment L2-5 was performed June 16, 1982, as part of the Loss-of-Fluid Test (LOFT) Experimental Program conducted by EG&G Idaho, Inc., for the U.S. Nuclear Regulatory Commission. Experiment L2-5 is part of the LOFT Power Ascension Experiment Series L2.

For the performance of Experiment L2-5, the LOFT facility was configured to simulate a double-ended 200070 cold leg break. The reactor scrammed and the primary coolant pumps were tripped and decoupled from their flywheels within 1 s after the break initiation. A rewet of the upper portion of the center fuel assembly began at approximately 12 s and ended at approximately 23 s. The injection of high- and low-pressure emergency core coolant (ECC) was delayed until approximately 24 and 37 s, respectively. The fuel rod peak cladding temperature of 1078 ± 13 K occurred at 28.47 ± 0.02 s. The cladding was quenched and the core re-covered within 70 s following the break initiation. The experiment was terminated after approximately 2 min.

iii

Following Experiment L2-5, the ECC injection was stopped to keep the water level below the reac-tor vessel nozzles. While monitoring the liquid level with upper plenum thermocouples, the core uncovered and heated up. The ECC injection was reinitiated and re-covered the core with liquid. Selected data from this heatup are included in this report.

Experiment L2-5 was initiated from the follow-ing primary coolant system initial conditions: hot leg temperature, 589.7 ± 1.6 K; cold leg temperature, 556.6 ± 4.0 K; hot leg pressure, 14.94 ± 0.06 MPa; and intact loop flow rate, 192.4 ± 7.8 kg/so The preexperiment power level was 36.0 ± 1.2 MW, with a maximum linear heat generation rate of 40.1 ± 3.0 kW/m.

Experiment L2-5 satisfied the specified objec-tives. This report presents data in the form of graphs in SI and British units. In conjunction with data obtained from direct measurement, selected computed variables are included to facilitate the analysis of the system thermal-hydraulic behavior.

ACKNOWLEDGMENTS

Appreciation is expressed to the Data Systems Branch, particularly to J. B. Marlow for preparation of the data plots. Appreciation is also expressed to the LOFT Data Analysis Branch, particularly to R. H. Averill for uncertainty analysis and instrument calibration. Special appreciation is expressed to G. Hammer for the technical editing.

IV

CONTENTS

ABSTRACT ii

SUMMARy.......................................................................... iii

ACKNOWLEDGMENTS.............................................................. iv

ACRONYMS ......................................................................... ix

1. INTRODUCTION ............................................................... .

1.1 LOFT Experimental Program Objectives ....................................... .

1.2 Experiment L2-S Objectives ................................................... 3

2. EXPERIMENTAL PROCEDURE AND INITIAL CONDITIONS ....................... 4

2.1 Experimental Procedure ...................................................... 4

2.2 Initial Conditions ............................................................ 6

3. DATA PRESENTATION......................................................... 12

4. REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 214

APPENDIX A-SYSTEM CONFIGURATION ........................................... 21S

APPENDIX B-MEASUREMENTS AND INSTRUMENTATION .......................... 221

APPENDIX C-PREEXPERIMENT PROCEDURES AND DATA CONSISTENCY CHECKS.. 313

1-1.

2-1.

2-2.

A-I.

B-1.

B-2.

B-3.

B-4.

B-S.

B-6.

FIGURES

LOFT piping schematic

LOFT power history prior to Experiment L2-S initiation ............... .

LOFT decay heat following Experiment L2-S initiation ................. .

LOFT major components .......................................... .

Relation of source and detectors to pipe for gamma densitometers ....... .

LOFT piping schematic with instrumentation ......................... .

LOFT thermal-hydraulic instrumentation for intact loop ............... .

LOFT thermal-hydraulic instrumentation for broken loop .............. .

LOFT blowdown suppression tank instrumentation .................... .

LOFT reactor vessel instrumentation ................................ .

v

2

4

6

218

223

226

228

229

230

231

B-7.

B-8.

B-9.

B-lO.

B-1 I.

B-12.

B-13.

B-14.

B-15.

B-16.

3S-1,2.

3S-3,4.

3S-5-12.

3S-13.

3M-I.

3M-2-12.

3M-13-2I.

LOFT reactor vessel upper plenum DTT, LE, and TE elevations ......... .

Cladding surface thermocouple locations for LOFT core ............... .

In-core thermocouple locations for center fuel assembly ................ .

LOFT pressurizer instrumentation .................................. .

LOFT steam generator instrumentation .............................. .

LOFT secondary coolant system instrumentation ...................... .

LOFT primary coolant pump instrumentation ........................ .

LOFT ECCS instrumentation-A train

LOFT ECCS instrumentation-B train

LOFT accumulator instrumentation ................................. .

Valve position

SHORT-TERM PLOTS (2 s or less)

Local heat generation rate ......................................... .

Pressure ........................................................ .

Power

Valve position

Fluid density

Fluid velocity

MEDIUM-TERM PLOTS (-5 to 30 s)

3M-22. Flow rate ............. " ......................................... .

3M-23-37. Momentum flux .................................................. .

3M-38, 39. Pump power .............. " ...................................... .

3M-40-45. Differential pressure .... ' ......................... ; .................. .

3M-46-56. Pressure ........................................................ .

3M-57-HX) Temperature .................................................... .

vi

232

233

234

235

236

237

238

239

240

241

61

62

63-66

67

69

69-74

75-79

79

80-87

87, 88

88-91

91-96

97-118

3L-l-l1.

3L-12-15.

3L-16-24.

3L-25,26.

3L-27-29.

3L-30-44.

3L-45-61.

3L-62-72.

3L-73.

3L-74-129.

3C-I-3, 3C-9-11.

Fluid density

LONG-TERM PLOTS (-20 to 120 s)

Displacement .................................................... .

Fluid velocity .................................................... .

Flow rate ....................................................... .

Liquid level ................. -.................................... .

Momentum flux .................................................. .

Differential pressure .............................................. .

Pressure ........................................................ .

Pump speed

Temperature

COMPUTED VARIABLES

Average density

3C-4-7, Mass flow rate ................................................... . 3C-12-15.

3C-8, 20. Density compensated liquid level .................................... .

3C-16-19. Liquid level bubble plots .......................................... .

3C-21. Fluid subcooling ................................................. .

3U-I-4.

3U-5, 6.

3U-7.

3U-8-13.

3R-l,2.

3R-3.

3R-4-18.

VARIABLES WITH UNCERTAINTY BANDS

Fluid density .................................................... .

Momentum flux .................................................. .

Pressure ........................................................ .

Temperature

Flow rate

POST -EXPERIMENT L2-5 PLOTS (150 to 450 s)

Pressure ........................................................ .

Temperature .................................................... .

vii

119-124

124-126

126-130

131

132, 133

133-140

141-149

149-154

155

155-183

185, 186 189, 190

186-188 190-192

188, 195

193, 194

195

197, 198

199

200

200-203

205

206

206-213

2-l.

2-2.

2-3.

2-4.

2-5.

2-6.

3-1.

3-2.

B-1.

B-2.

TABLES

Sequence of events for Experiment L2-5 ................................... .

Plant trips for Experiment L2-5 ........................................... .

Initial conditions for Experiment L2-5 ..................................... .

Linear heat generation rate prior to Experiment L2-5 ........................ .

Primary coolant temperatures at Experiment L2-5 initiation .................. .

Water chemistry results for Experiment L2-5 ............................... .

Measured variables for Experiment L2-5 ................................... .

Computed variables for Experiment L2-5

Nomenclature for LOFT instrumentation

5

7

7

9

10

11

14

55

227

Experiment L2-5 instrumentation list ....................................... 242

viii

ACC

BST

BWST

DAVDS

DTT

ECC

ECCS

ESF

HPIS

LOCA

LOCE

LOFT

LPIS

PCP

PCS

PWR

QOBV

RABV

RV

SCS

so

XRO

ACRONYMS

Accumulator

Blowdown suppression tank

Borated water storage tank

Data acquisition and visual display system

Drag disc-turbine transducer

Emergency core cooling or coolant

Emergency core cooling system

Engineered safety feature

High-pressure injection system

Loss-of-coolant accident

Loss-of-coolant experiment

Loss-of-Fluid Test

Low-pressure injection system

Primary coolant pump

Primary coolant system

Pressurized water reactor

Quick-opening blowdown valve

Reflood assist bypass valve

Reactor vessel

Secondary coolant system

Steam generator

Orifice

ix

EXPERIMENT DATA REPORT FOR LOFT LARGE BREAK LOSS-OF-COOLANT EXPERIMENT L2-5

1. INTRODUCTION

This report presents selected pertinent and uninterpreted data from Experiment L2-5, which was conducted in the Loss-of-Fluid Test (LOFT) facility on June 16, 1982. Experiment L2-5 was the third nuclear large break loss-of-coolant experiment (LOCE) performed at LOFT and simulated an offset shear of a primary coolant system cold leg pipe with an immediate primary coolant pump trip.

The LOFT facility is a 50-MW(t) pressurized water reactor (PWR) with instrumentation to measure and provide data on the thermal-hydraulic and nuclear conditions throughout the system. Operation of the LOFT system is typical of large [-1000 MW(e)] commercial PWR opera-tions. The LOFT facility consists of

1. A reactor vessel with a nuclear core

2. An intact loop with an active steam generator, pressurizer, and two primary coolant pumps connected in parallel

3. A broken loop with a simulated pump, simulated steam generator, and two quick-opening blowdown valve assemblies

4. A blowdown suppression system consisting of a header, suppression tank, and a spray system

5. An emergency core coolant (ECq injec-tion system consisting of two low-pressure injection system (LPIS) pumps, two high-pressure injection system (HPIS) pumps, and two accumulators.

Figure 1-1 presents the LOFT piping schematic. For additional information on the LOFT system, refer to Reference 1 and Appendix A of this report.

The data presented in this report are from 360 of the 629 instruments that provided data during

Experiment L2-5. Only the data considered perti-nent to the understanding of this experiment are presented. The data are in an uninterpreted but readily usable form for use by the nuclear com-munity in advance of detailed analysis and inter-pretation. The data, in the form of graphs in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.

Sections 1.1 and 1.2 state the LOFT Experimen-tal Program objectives and the Experiment L2-5 objectives, respectively. Section 2 summarizes the experimental procedure and initial conditions. Section 3 presents the data with supporting infor-mation for data interpretation. Appendix A describes the LOFT system configuration. Appen-dix B describes the LOFT instrumentation system and the methods of obtaining various measurements, and presents a list of instruments available for use in Experiment L2-5. Appendix C summarizes the preexperiment calibrations and the methods used to verify the consistency and accuracy of the data.

1.1 LOFT Experimental Program Objectives

The LOFT integrala test facility was designed to simulate the major components of a four-loop; commercial PWR, thereby producing data on the thermal, hydraulic, nuclear, and structural pro-cesses expected to occur during a loss-of-coolant accident (LOCA) in a PWR. Reference 1 describes the LOFT facility in detail. The specific objectives of the LOFT Experimental Program are to

a. The term "integral" is used to describe an experiment com-bining the nuclear, thermal, hydraulic, and structural processes occurring during a loss-of·coolant accident as distinguished from separate effects, nonnuclear, small-scale. and thermal· hydraulic experiments conducted for loss-of-coolant analysis.

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1. Provide data required to evaluate the ade-quacy of and to improve the analytical methods currently used to predict the response of large PWRs to postulated acci-dent conditions, the performance of engineered safety features (ESFs) with par-ticular emphasis on emergency core coolant systems (ECCS), and the quantitative margins of safety inherent in the per-formance of the ESFs

2. Identify and investigate any unexpected-event(s) or threshold(s) in the response of either the plant or the ESFs and develop analytical techniques that adequately describe and account for the unexpected behavior(s)

3. Evaluate and develop methods to prepare, operate, and recover systems and plant for and from reactor accident conditions

4. Identify and investigate methods by which reactor safety can be enhanced, with emphasis on the interaction of the operator with the plant.

1.2 Experiment L2-5 Objectives

The programmatic objectives of Experiment L2-5 are to

3

1. Provide experimental data to demonstrate that Appendix K2 assumptions result in a conservative prediction of peak clad temperature, even if core hydraulic condi-tions were to occur in a commercial reactor which precluded the early return to nucleate boiling (rewet)

2. Provide data to confirm that results from early LOFT large break experiments were not being significantly affected by external cladding thermocouples.

To support the programmatic objectives, the specific objectives of Experiment L2-5 are to

1. Determine if early core rewet occurs following a scaled LOFT 200% double-ended cold leg break with immediate primary coolant pump trip

2. Provide data on core thermal response which can be used to evaluate computer code predictions and to compare with acceptance criteria in 10 CFR 50.462

3. Determine system and core response during normal ECC reflood following the double-ended cold leg break transient

4. Evaluate cladding surface thermocouple effects during blowdown and reflood by comparing the responses of LOFT fuel bundle instrumentation.

2. EXPERIMENTAL PROCEDURE AND INITIAL CONDITIONS

This section summarizes the experimental pro-cedure and initial conditions recorded during Experiment L2-5.

2.1 Experimental Procedure

Initial reactor criticality occurred approxi-mately 54 h prior to experiment initiation. The power level reached 36 ± 2 MW at 28 h prior to Experiment L2-5 and was maintained at approx-imately that level until the experiment began. A plot of the power level versus time for the 60-h period prior to experiment initiation is given in Figure 2-1. These data are an average of the four power-range instruments. Adjustments to these instruments, based on secondary calorimetric calculations, are made as necessary at power levels of approximately 15, 25, and 37.5 MW.

Prior to initiating the experiment, a data acquisition and visual display system (DA VDS)3 calibration and a data integrity check were per-formed. During this period, the initial condition water samples were taken from the primary coolant system (peS), the secondary coolant

system (SCS), and the blowdown suppression tank (BST). Just prior to experiment initiation, the purification lines were closed, the BST recircula-tion pumps were turned on, the broken loop warmup recirculation flow was stopped, and heaters on the broken loop hot leg were turned off. The broken loop isolation valves were opened, and the pressurizer heaters were turned off.

The DA VDS was activated and started recording data -7 min prior to the experiment. The sequence of events for the experiment is pro-vided in Table 2-1. Figure 2-2 shows the decay heat during the experiment, which was calculated using the American Nuclear Society Standard 5.1.4

The experiment was initiated by opening the quick-opening blowdown valves in the broken loop hot and cold legs. The reactor scrammed on low pressure at 0.24 ± 0.01 s. The setpoints for this and other plant trips are presented in Table 2-2. Following the reactor scram, the operators tripped the primary coolant pumps at 0.94 ± 0.01 s. The pumps were not connected to their flywheels during the coastdown.

EXPERIMENT L2-5 40

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TIME BEFORE RUPTURE (h) Figure 2-1. LOFT power history prior to Experiment L2-5 initiation.

4

TABLE 2-1. SEQUENCE OF EVENTS FOR EXPERIMENT L2-5

Time After Experiment Initiation

Event

Experiment L2-5 initiated

Subcooled blowdown ended

Reactor scrammed

Cladding temperatures initially deviated from saturation

Primary coolant pumps tripped

Subcooled break flow ended (cold leg)

Partial rewet initiated

Pressurizer emptied

Accumulator A injection initiated

Partial rewet ended

HPIS injection initiated

Maximum cladding temperature reached

LPIS injection initiated

Accumulator emptied

Core cladding quenched

BST maximum pressure reached

LPIS injection terminated

a. The experiment was considered complete by this time.

5

(s)

0.0

0.043 ± 0.01

0.24 ± 0.01

0.91 ± 0.2

0.94 ± 0.01

3.4 ± 0.5

12.1 ± 1.0

15.4 ± 1.0

16.8 ± 0.1

22.7 ± 1.0

23.90 ± 0.02

28.47 ± 0.02

37.32 ± 0.02

49.6 ± 0.1

65 ± 2

72.5 ± 1.0

107.1 ± 0.4a

EXPERIMENT L2-5 2

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o 100 200 300 400 500 TIME AFTER RUPTURE (s)

Figure 2-2. LOFT decay heat following Experiment L2-5 initiation.

A rewet of the upper portion of the center fuel assembly began at approximately 12 s and ended at approximately 23 s. Accumulator injection of ECC to the intact loop cold leg began at 16.8 ± 0.1 s. Delayed ECC injection from the HPIS and LPIS began at 23.90 ± 0.02 and 37.32 ± 0.02 s, respectively. The fuel rod peak cladding temperature of 1078 ± 13 K was attained at 28.47 ± 0.02 s. The cladding was quenched at 65 ± 2 s, following the core reflood. The LPIS injection was stopped at 107.1 ± 0.4 s, after the experiment was considered complete.

The BST pressure was automatically controlled by the spray system to simulate the containment back pressure expected during a LOCA in a commercial PWR.

Following Experiment L2-5, an attempt was made to keep the reactor vessel liquid level below the nozzles but above the core. This procedure is being considered for use during the recovery from Experiment L2-6. The liquid level was monitored using upper plenum thermocouples. At approx-imately 144 s, the HPIS was turned off. The core began to uncover and heat up at approximately 190 s; the upper plenum thermocouples gave no indication of decreasing level. The HPIS and LPIS injections were reinitiated at approximately

6

274 and 347 s, respectively. The ECC was directed to the lower plenum. The core was completely quenched by 430 s.

The DAVDS recorded approximately 15 min of data after the experiment was initiated. A voltage insertion calibration of the DA VDS was per-formed following the experiment.

2.2 Initial Conditions

The specified initial plant operating conditions (except for the linear heat generation rate) for Experiment L2-5 are presented in Table 2-3, along with the values measured immediately prior to experiment initiation. Table 2-4 gives the linear heat generation rate versus core height for three locations within the LOFT core prior to experi-ment initiation. The data for Table 2-4 were obtained from the traversing in~core probe system.

Table 2-5 gives the measured fluid temperatures of the PCS immediately prior to experiment initiation.

Table 2-6 specifies the required water chemistry for the PCS, the EST, and the SCS. In addition, the results of the water chemistry analyses are pre-sented for preexperiment conditions in these systems, and for postexperiment conditions in the BST.

TABLE 2-2. PLANT TRIPS FOR EXPERIMENT L2-5

Trip

Reactor

Low-pressure scram

Secondar:t: coolant sJ::stem

Main steam control valve Main steam control valve Main steam control valve Main steam control valve

open stop opening close stop closing

S . a

etp0l.nt

14.19 MPa

7.12 MPa 6.98 MPa 6.50 MPa 6.57 MPa

Measurement Location

Intact loop hot leg

Main steam line Main steam line Main steam line Main steam line

a. The trip may vary within the measurement uncertainty of the setpoint, which is typically ±0.2l MPa.

TABLE 2-3. INITIAL CONDITIONS FOR EXPERIMENT L2-5

Parameter Specified Value Measured Value

Primary Coolant System

Mass flow (kg/ s) 192.4 ± 7.8 Hot leg pressure (MPa) 14.95 ± 0.10 14.94 ± 0.06 Core liT (K) 35.8 ± 2.0 33.1 ± 4.3 a

Cold leg temperature (K) 556.6 ± 4.0 Hot leg temperature (K) 592 ± 2 589.7 ± 1. 6a

Boron concentration (ppm) 668 ± 15 \

Reactor Vessel

Power level (MW) 37.5 ± 1.0 36.0 ± 1.2 a

Maximum linear heat generation rate 40.1 ± 3.0 (kW/m) Control rod position (above full-in 1.372 ± 0.013 1. 376 ± 0.010 position) (m)

Pressurizer

Steam volume (m3§ 0.32 ± 0.02 Liquid volume (m ) 0.61 ± 0.02 Liquid temperature (K) 615.0 ± 0.3 Liquid level (m) 1.13 ± 0.18 1.14 ± 0.03

7

TABLE 2-3. (continued)

Parameter

Broken Loop

Cold leg temperature near reactor vessel (K)

Hot leg temperature near reactor vessel (K)

Steam Generator Secondary Side

Saturation temperature (K) Pressure (MPa) Mass flow (kg/s)

Suppression Tank

Liquid level (m) Liquid volume (m3) Gas volume (m3 ) Liquid temperature (K) Pressure (gas space)(MPa)

Accumulator A

Liquid level (m) Liquid volume (m3 ) Vapor volume (m3 ) Pressure (MPa) Liquid temperature (K) Boron concentration (ppm)

Borated Water Storage Tank

Liquid temperature (K) Boron concentration (ppm)

Specified Value

As c lose as practical to intact loop As close as practical to intact loop

1.27 ± 0.127

356 ± 5 0.08 ± 0.005

2.045 ± 0.025

4.2 ± 0.2 306 ± 3

303 ± 3

Measured Value

554.3 ± 4.2

561.9 ± 4.3

547.1 ± 0.6 5.85 ± 0.06 19.1 ± 0.4

1.41 ± 0.06 a

33.9 ± 2.1 51.7 ± 2.1

358.4 ± 3.0 0.097 ± 0.007 a

2.10 ± O.Ola 2.92 ± 0.01 0.84 ± 0.01 4.29 ± 0.06

303.2 ± 6.1 3239 ± 15

301.7 ± 6.1 3232 ± 15

a. Out of specification, but is not believed to significantly affect results.

8

TABLE 2-4. LINEAR HEAT GENERATION RATE PRIOR TO EXPERIMENT L2-5 (Reading Uncertainty ±7.6%)

Linear Heat Generation Rate for Core position

Position Height Above (kW/m) Core Bottom

(m) 1C7 5H8 5M3

0.152 9.78 16.95 16.73 0.292 19.03 32.32 31.9l 0.394 20.18 35.01 34.56 0.456 19.41 32.98 32.56

0.503 20.45 34.72 34.28 0.546 22.10 36.00 36.03 0.648 21. 78 35.48 35.51 0.749 20.98 33.24 33.67

0.846 18.70 29.61 30.00 0.886 16.90 26.78 27.12 0.953 17.05 26.05 27.36 1.054 15.93 24.15 24.44

1.181 12.84 19.45 19.68 1. 257 10.48 15.89 16.07 1.299 8.85 13 .41 13.57 1.359 7.61 11. 53 11.67

1.511 3.76 6.26 5.88 1.613 1.82 3.37 3.18 1.664 1.34 2.08 1. 94

9

TABLE 2-5. PRIMARY COOLANT TEMPERATURES AT EXPERIMENT L2-5 INITIATION

Measurement Temperature Location Identification (K)

Intact loop hot leg (near vessel) TE-PC-002B 589.5 ± 4.2

Intact loop steam generator outlet TE-SG-002 555.0 ± 4.0

Intact loop cold leg (near vessel) TE-PC-005 556.4 ± 4.3

Reactor vessel downcomer (Instrument Stalk 1) TE-lST-OOl 555.0 ± 4.0

Reactor vessel lower plenum TE-ILP-OOl 555.7 ± 4.0

Reactor vesse 1 upper plenum TE-lUP-OOl 598.8 ± 4.3 TE-4UP-001 581. 5 ± 4.2 TE-5UP-OlO 606.5 ± 4.3

Broken loop hot leg (near vessel) TE-BL-002B 561. 9 ± 4.3

Broken loop cold leg (near vessel) TE-BL-OOIB 554.3 ± 4.2

Intact loop pressurizer PE-PC-004 615.6 ± 0.7 (from saturation pressure)

10

TABL

E 2

-6.

WAT

ER

CHEM

ISTR

Y

RES

ULT

S FO

R EX

PER

IMEN

T L

2-S

Primar~ C

oo

lan

t S

yst

em

Blo

wdo

wn

Su

pp

ress

ion

Tan

k

Par

amet

er

pH

(eac

h at

298

K)

Co

nd

uct

ivit

y (~

mho/

cml)

(e

ach

at

298

K)

To

tal

gas

(c

m)/

kg

)

Dis

solv

ed

oxyg

en

(ppm

)

Ch

lori

de

(ppm

)

Un

dis

solv

ed

soli

ds

(ppm

)

Bor

on

(ppm

)

Flu

ori

de

(ppm

)

Hyd

roge

n (c

ml/

kg

)C

To

tal

gro

ss acti

vit

y

(pC

i/m

L)

Gro

ss

bet

a an

d ga

mm

a (~ci/mL)

131

1 (~

Ci/m

L)

135

1 (p

Ci/

mL

)

Sp

eci

fied

4.2

to

1

0.5

60

max

imum

100

max

imum

0.1

5

max

imum

1.0

max

imum

0.1

m

axim

llm

10

to

60

375

max

imum

0.1

7

max

imum

0.7

6

max

imum

Pre

exp

erim

enta

S

eecif

ied

5.8

3

4.2

to

1

0.5

2.7

1

60

max

imum

29

<0

.1

0.1

5

max

imum

<0

.5

1.0

max

imum

668

>

1050

<0

.02

0

.1

max

imum

16

0.0

05

5

0.0

05

5

0 0

a.

Sam

ple

tak

en u

pst

ream

fr

om

the

pri

mar

y co

ola

nt

syst

em

ion

ex

chan

ger

.

b.

Cat

ion

co

nd

ucti

vit

y.

c.

Pri

or

to d

ep

ress

uri

zati

on

.

Pre

exp

erim

ent

Po

stex

per

imen

t

4.9

1

5.0

1

12

.22

9

.71

<0

.1

<0

.1

<0

.5

<0

.5

3697

31

35

<0

.02

<

0.0

2

0.0

05

6

0 0

Sec

on

dar

y C

oo

lan

t S

yst

em

SJ>

ecif

ied

P

reex

J>er

imen

t

9.0

to

1

0.2

1

0.0

1

2 m

axim

umb

1.3

0.0

05

m

axim

um

0.0

04

0.1

5

max

imum

<

0.1

1.0

max

imum

3

6.4

9 x

10

-4

max

imum

0

3. DATA PRESENTATION

The data presented in this report are selected pertinent and uninterpreted thermal-hydraulic and nuclear data from LOFT Experiment L2-5. The experiment data have been divided into two categories, "Qualified" and "Failed." The "Qualified" designation was applied to measure-ments that have been found to be within the uncer-tainty of the instrument. The absence of a comment following the "Qualified" designation indicates that the data are valid (that is, within specified uncertainty bands) over the entire time span recorded. Restrictive statements accompany data that are invalid or questionable over a por-tion of the recorded time span. All the data pre-sented in this report are "Qualified". The plot captions contain only applicable restrictive state-ments; if no statement appears, the data are "Qualified". Data that are not presented are available from EG&G Idaho, Inc., upon special request. The checks on data consistency and instrument performance are discussed in detail in AppendixC. Any information concerning calibra-tion data may be received by contacting the LOFT Data Analysis Branch Manager.

The ,data were processed and are presented in graphical form in SI units. British units and accompanying tick marks are also included. Most of the ,data were collected at a rate of 50 samples per second. Short-term plots contain 125 orfewer points. Plots of longer time frames were reduced to 2000 or fewer points for ease of plotting. This was accomplished by dividing the time span into approximately 1000 constant increments ,and plot-ting only the minimum and maximum values in each increment. The resulting plot looks nearly identical to a plot produced by plotting every point because of the finite resolution of the plotting device.

Uncertainties for experimental measurements and com uted variables are of the form

B) + (M x RD/100)2, where B is the bias (offset) uncertainty, RD, is the percentage-of-reading uncertainty, and M is the measurement reading at a particular time. The uncertainties sup-plied on the plots were calculated for M equal to the maximum data value to ensure that the uncer-tainties are conservative. Uncertainties for process instruments are of the form ± RG/100, where RG is a percentage-of-range uncertainty. The values B, RD, and RG were calculated at the 951170 ,con-

12

fidence level. Uncertainty values are presented in Table B-2 of Appendix B and on each plot.

Uncertainty bands on selected measurements are presented for ease in code comparison. The uncertainties are fixed values calculated at the upper range of the recorded data so as to be con-servative. On certain plots, the uncertainty band may exceed a physical limit, such as a density below zero. This is a result of the plotting software and does not represent a real phenomenon.

The design ranges of the instruments are also presented on each plot. In some cases, the instru-ment range exceeds its design range. Computed variables were calculated from several measure-ments and thus do not have a design range.

Table 3-1 lists the Experiment L2-5 measure-ments that provided the data presented in this report and gives the detector location and the data figure numbers. In addition, this table contains a "Comments" column which gives information pertaining to the qualification of the data. A list of instruments available for Experiment L2-5 is included in Table B-2.

Table 3-2 lists the variables that were computed from other measurements and geometrical con-stants. This table also gives the equations used to compute these variables, the data figure number, and comments which reflect on the usefulness of the data.

The data are divided into six major sections with .the individual plots in each section being presented in alphanumeric order to facilitate com-parison and location of desired variables. These data sections include:

1. Experiment L2-5 MeasuredVariables~ Short- ' Term Plots (2 s or less), Figures 3S-1 through 3S-13

2. Experiment L2-5 Measured Variables, Medium-Term Plots (-5 to 30 s), Figures 3M-1 through 3M-100

3. Experiment L2-S Measured Variables, Long-Term Plots (-20 to 120 s), Figures 3L-l through 3L-129

4. Experiment L2-S Computed Variables, Figures 3C-l through 3C-21

13

S. Experiment L2-S Variables with Uncertainty Bands, Figures 3U-l through 3U-13

6. Post-Experiment L2-S Measured Variables (1S0 to 4S0 s), Figures 3R-l through 3R-18.

TABLE 3-1. MEASURED VARIABLES FOR EXPERIMENT L2-5

Variable, System, and Detector

VALVE OPENING

Secondary Coolant System

CV-P004-0l0

Broken Loop

CV-P138-001

CV-P138-0l5

DENSITY

Broken Loop

DE-BL-OOIA

DE-BL-001B

DE-BL-OOIC

DE-BL-002A

Location

Main steam control valve.

Quick-opening blowdown valve (QOBV) in cold leg.

QOBV 1n hot leg.

Cold leg at drag disc-turbine transducer (DTT) flange. Beam A 1S 14° 21 min from Beam B [clockwise (CW looking toward reactor vessel (RV)].

Cold leg at DTT flange. Beam B 1S through centerline of pipe 45° from vertical [counterclockwise (CCW) looking toward RV].

Cold leg at DTT flange. Beam C 1S 22° 7 min from Beam B (CCW looking toward RV).

Hot leg at DTT flange. Beam A is 14° 21 min from Beam B (CCW looking toward RV).

14

Figure Number

3M-l

3S-l

3s-2

3M-2 3L-l

3M-3 3L-2 3U-l

3M-4 3L-3

3M-5 3L-4 3U-2

Comments

Qualified.

Qualified, except for spurious spikes.


Qualified.

Qualified.

Qualified.

Qualified.



DENSITY (continued)

Broken Loop (continued)

DE-BL-002C

Intact Loop

DE-PC-001A

DE-PC-001B

DE-PC-001C

DE-PC-002A

DE-PC-002B

DE-pe-002C

Location

Hot leg at DTT flange. Beam C is 22° 7 min from Beam B (CW looking toward RV).

Cold leg at DTT flange. Beam A ~s 14° 21 min from Beam B (CW looking away from RV).

Cold leg at DTT flange. Beam B through centerline of pipe 45° from vertical (CCW looking away from RV) .

Cold leg at DTT flange. Beam C is 22° 7 min from Beam B (CCW looking away from RV).

Hot leg at DTT flange. Beam A is 14° 21 min from Beam B (CW looking away from RV).

Hot leg at DTT flange. Beam B through centerline of pipe 45° from vertical (CCW looking away from RV).

Hot leg at DTT flange. Beam C ~s 22° 7 min from Beam B (CCW looking away from RV).

15

Figure Number

3M-6 3L-5

3M-7 3L-6

3M-8 3L-7 3u-3

3M-9 3L-8

3M-10 3L-9

3M-ll 3L-10 3U-4

3M-12 3L-ll

Comments


Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified,except for spurious spikes.



FUEL ASSEMBLY DISPLACEMENT

Assembly 5

DIE-5Gl3-01

DIE-5H03-0l

DIE-5Il3-01

DIE-5UP-002

FLUID VELOCITY

Intact Loop

FE-PC-OOlA

FE-PC-OOlB

FE-PC-OOlC

FE-PC-002A

FE-PC-002B

Location

Fuel rod at Row G, Column 13 of Fuel Assembly 5.

Fuel rod at Row H, Column 3 of Fuel Assembly 5.

Fuel rod at Row I, Column 13 of Fue 1 Assembly 5.

At top center of Fuel Assembly 5.

Cold leg DTT horizontal flange on west side of pipe.

Cold leg DTT horizontal flange at center of pipe.

Cold leg DTT horizontal flange on east side of pipe.

Hot leg DTT flange at bottom of pipe.

Hot leg DTT flange at middle of pipe.

16

Figure Number

3L-12

3L-13

3L-14

3L-15

3M-l3 3L-16

3M-14 3L-17

3M-15 3L-18

3M-16 3L-19

3M-17 3L-20

Comments

Qualified, magnitude uncertain.




Qualified, flow direction not indicated.







FLUID VELOCITY (continued)

Intact Loop (continued)

FE-pe-002C

Reactor Vessel

FE-1ST-DOl

FE-IST-002

FE-5LP-OOl

FE-SUP-DOl

FLOW RATE


FT-P004-72-2

Emergency Core Coo ling System

FT-P120-085

Location

Hot leg DTT flange at top of pipe.

Downcomer Stalk 1.

Downcomer Stalk 1.

Lower end box of Fuel Assembly 5.

Above upper end box of Fuel Assembly 5.

Flow out of main feedwater pump.

Low-pressure injection system (LPIS) Pump A discharge.

17

Figure Number

3M-18 3L-21

3M-19

3L-22

3M-20 3L-23

3M-21 3L-24

3M-22

3L-25

Comments



Qualified, flow direction not indicated, unexplained noise.



Qualified.


TABLE 3-1. .(continued)

Variable, Sys tern, and Detector

FLOW RATE (continued)

Emergency Core Cooling System (continued

FT-P128-l04

LIQUID LEVEL

Emergency Core Cooling System

LE-ECC-OlA

LIT-P120-044

Blowdown Sup-pression Tank

LT-P138-033

LT-P138-058

MOMENTUM FLUX

Broken Loop

ME-BL-OOlA

ME-BL-OOlC

ME-BL-OOlD

Location

High-pressure injection system (HPIS) Pump A discharge.

Accumulator A.

Accumulator A.

Blowdown suppression tank (BST) level on north end of tank.

BST level on south end of tank.

Cold leg DTT flange at bottom of pipe, high range.

. C91d leg DTT flaI1ge at top of pipe, high range.

Cold leg DTT flange at bottom of pipe, low range.

18

Figure Number

3L-26 3R-2

3L-27

3L-27

3L-28

3L-29

3M-23 3U-5

3M-24

3M-25 3L-30

Comments

Qualified.

Qualified.

Qualified, pressure sensitive after tank emptied.

Qualified.

Qualified.

Qualified.

. Q.ualif~ed.

Qualified, narrow range instrument.



MOMENTUM FLUX (continued)


NE-BL-001E

ME-BL-001F

ME-BL-002A

ME-BL-002B

ME-BL-002C

ME-BL-002D

ME-BL-002E

ME-BL-002F

Intact Loop

ME-PC-OOlB

ME-PC-OOIC

ME-PC-002A

Location

Cold leg DTT flange at middle of p~pe, low range.

Cold leg DTT flange at top of pipe, low range.

Hot leg DTT flange at bottom of pipe, high range.

Hot leg DTT flange at center of pipe, high range.

Hot leg DTT flange at top of pipe, high range.

Hot leg DTT flange at bottom of pipe, low range.

Hot leg DTT flange at center of pipe, low range.

Hot leg DTT flange at top of pipe, low range.

Cold leg horizontal DTT flange at center of pipe.

Cold leg horizontal DTT flange on east side of pipe.


19

Figure Number

3M-26 3L-3l

3M-27 3L-32

3M-28 3L-33

3M-29 3L-34 3U-6

3M-30 3L-35

3L-36

3L-37

3L-38

3M-3l 3L-39

3M-32 3L-40

3M-33 3L-4l

Comments



Qualified.

Qualified.

Qualified.

Qua 1 i fied after 20 s.

Qualified after 20 s.

Qualified after 20 s.

Qualified.

Qualified.

Qua 1 i fied.


Variable, System, and Figure Detector Location Number Comments

MOMENTUM FLUX (continued)

Intact Loop (continued)

ME-PC-002B Hot leg DTT flange at 3M-34 Qualified. middle of pipe. 3L-42

Reactor Vessel

ME-1ST-00l Downcomer Stalk I, 3M-35 Qualified. 1.16 m above RV bottom.

ME-5LP-002 Fuel Assembly 5, lower 3M-36 Qualified. end box. 3L-43

ME-5UP-OOI Fuel Assembly 5 above 3M-37 Qualified. upper end box. 3L-44

NEUTRON DETECTION

Reactor Vessel

NE-2H08-26 Neutron detector ~n Fuel 3S-3 Qualified, magnitude Assembly 2. uncertain.

NE-4H08-26 Neutron detector ~n Fuel 3S-3 Qualified, magnitude Assembly 4. uncertain.

NE-SD08-11 Neutron detector ~n Fuel 3S-4 Qualified, magnitude Assembly 5. uncertain.

NE-5DOB-27 Neutron detector ~n Fuel 3S-3 Qualified, magnitude Assembly S. 3S-4 uncertain.

NE-5D08-44 Neutron detector ~n Fuel 3S-4 Qualified, magnitude Assembly 5. uncertain.

... ','," NE-5D08-61 Neutron detector ~n' Fue:l " '38.,...4, ,'Qualified, , magnitude Assembly S. uncertain.

NE-6HOB-26 Neutron detector ~n Fuel 3S-3 Qualified, magnitude Assembly 6. uncertain.

20



ELECTRICAL POWER

Intact Loop

PCP-l-P

PCP-2-P

DIFFERENTIAL PRESSURE

Broken Loop

PdE-BL-OOl

PdE-BL-002

PdE-BL-003

PdE-BL-004

PdE-BL-005

PdE-BL-006

PdE-BL-007

PdE-BL-008

PdE-BL-009

Location

Primary coolant pump (PCP) 1.

PCP-2.

Hot leg across 14- to 5-in. contraction.

Cold leg across 14- to 5-in. contraction.

Cold leg across break plane.

Hot leg across break plane.

Hot leg across pump simulator.

Hot leg across steam generator (SG) simulator outlet flange.

Hot leg across SG simulator.

Hot leg across SG simulator inlet flange.

From 14- to 5-in. contraction to middle of 5-in. pipe.

21

Figure Number

3M-38

3M-39

3L-45

3L-46

3L-47

3L-48

3L-49

3L-50

3L-5l

3L-52

3L-53

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified, no other measurement for direct comparison.

Qualified.

Qualified.


Qualified.

Qualified.



DIFFERENTIAL PRESSURE (continued)


PdE-BL-OlO

PdE-BL-Oll

PdE-BL-012

Intact Loop

PdE-PC-OOl

PdE-PC-002

PdE-PC-003

PdE-PC-005

PdE-PC-006

PdT-P139-030

Location

From middle of 5-in. pipe to break plane.

Pump simulator outlet to PE-BL-003.

From PE-BL-003 to break p lane inlet.

Cold leg across PCPs.

Across SG.

Hot leg piping, RV to SG inlet.

Cold leg piping, PCPs to RV nozzle.

RV outlet to inlet.

Across RV just beyond intact loop inlet and outlet nozzles.

22

Figure Number

3L-54

3L-55

3L-56

3M-40 3L-57

3M-4l 3L-58

3M-42 3L-59

3M-43 3L-60

3M-44 3L-6l

3M-45

Comments

Qualified, narrow range instrument, good after 20 s.

Qualified, shares tap with PdE-BL-012, may have common line problems.

Qualified, shares tap with PdE-BL-Oll, may have common line problems.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified, un~directional instrument.



PRESSURE

Broken Loop

PE-BL-OOI

PE-BL-002

PE-BL-004

PE-BL-006

PE-BL-008

Intact Loop

PE-PC-OOI

PE-PC-002

PE-PC-004

PE-PC-005

PE-PC-006


PE-SGS-OOI

Location

Cold leg at DTT fJange.

Hot leg at DTT flange.

Cold leg at inlet of spool piece.

Hot leg at outlet of S9.

Cold leg downstream of break plane.

Cold leg at DTT flange.

Hot leg at DTT flange.

Pressurizer vapor space.

Reference pressure between SG outlet and PCP inlet.

Reference pressure between SG outlet and PCP inlet.

SG dome pressure.

23

Figure Number

3S-5 3M-46 3L-62

3S-6 3M-47 3L-63

3S-7 3L-62

3S-8 3L-63

3S-9 3L-62

3S-l0 3M-48 3L-64

3S-ll 3M-49 3L-65

3M-50

3M-51

3L-66

3L-67

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.



PRESSURE (continued)

Blowdown Sup-pression System

PE-SV-003

PE-SV-014

PE-SV-018

PE-SV-055

PE-SV-060

Reactor Vessel

PE-lST-OOlA

PE-lST-003A

PE-lUP-001A

PE-lUP-OOlAl


PT-P004-0l0A

Location

BST across from Downcomer 1 (south end), 157.5 0 from top vertical (CW looking north).

BST header above Downcomer 4, 327 0

from top vertical (CW looking north).

BST header above Downcomer 1.

BST bottom under Downcomer 3.

BST top above Down-comer 1.

Downcomer Stalk 1, 0.62 m above RV bottom.

Downcomer Stalk 1, 5.32 m above RV bottom.

Above Fuel Assembly 1 upper end box.

Above Fuel Assembly 1 upper end box.

In 10-in. line from SG.

24

Figure Number

3L-68

3L-68

3M-52

3M-52

3L-68

3M-53

3L-69

3M-54 3U-7

3S-12 3L-70 3R-3

3M-55

Comments

Qual i fied.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.



PRESSURE (continued)

Emergency Core Cooling System

PT-P120-043

Intact Loop

PT-P139-002

PT-P139-003

PT-P139-004

PT-P139-05-1

REACTIVITY

Reactor Vessel

RE-T-77-1A2

R E-T- 77 - 2A2

RE-T-77-3A2

Location

Accumulator A.

Hot leg at venturi on bottom.

Hot leg at venturi on left side looking toward SG.

Hot leg at venturi on right side looking toward SG.

Pressurizer, 1.88 m above bottom (vapor space).

Power range, Channel A level.

Power range, Channel B leve 1.

Power range, Channel C leve 1.

25

Figure Number

3L-71

3M-56

3L-72

3L-72

3M-50

3S-13

3S-13

38-13

Comments


Qualified, except for spurious spikes, response limited during subcooled blowdown.



Qualified.

Qualified.

Qualified.

Qualified.



PUMP SPEED

Intact Loop

RPE-PC-OOl

RPE-PC-002

TEMPERATURE

Reactor Vessel

TC-5C07-27

TC-5D07-27

TC-5D09-27

TC-5D10-27

Broken Loop

TE-BL-001A

TE-BL-001B

Location

PCP-1.

PCP-2.

Centerline of Fuel Assembly 5, Row C, Column 7 at 0.69 m above bottom of fuel rod.

Centerline of Fuel Assembly 5, Row D, Column 7 at 0.69 m above bottom of fuel rod.



Cold leg DTT flange at bottom of pipe.

Cold leg DTT flange at middle of pipe.

26

Figure Number

3L-73

3L-73

3M-57 3L-74 3R-4

3M-58 3U-8

3M-57 3L-74 3R-4

3M-57

3M-59 3L-75

3M-59 3L-75

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified, possible hot wall effects.




TEMPERATURE (continued)


TE-BL-OOIC

TE-BL-002B

Intact Loop

TE-PC-OOIA

TE-PC-OOIB

TE-PC-OOIC

TE-PC-002A

TE-PC-002B

TE-PC-002C

TE-PC-005

TE-PC-009

TE-PC-OIO

TE-PC-Oll

Location

Cold leg DTT flange at top of pipe.


Cold leg DTT horizontal flange on west side of pipe.

Cold leg DTT horizontal flange at center of pipe.

Cold leg DTT horizontal flange on east side of pipe.



Hot leg DTT flange at top of pipe.

Next to bottom of emergency core coolant (ECC) Rake 1.

Next to bottom of ECC Rake 2.

Next to top of ECC Rake 2.

Top of ECC Rake 2.

27

Figure Number

3M-59 3L-75

3M-60 3L-76

3M-6l 3L-77

3M-6l 3L-77

3M-6l 3L-77

3M-62 3L-78

3M-62 3L-78

3M-62 3L-78

3L-79

3M-63 3L-79

3M-63

3M-63

Comments
















Emeq?ency Core Coohng System

TE-P120-04l

Intact Loop

TE-P139-0l9

TE-P139-020

TE-P139-20-l

TE-SG-OOl

TE-SG-001A

TE-SG-002

TE-SG-002A


TE-SG-003

Location

Accumulator A.

Pressurizer vapor space, 0.86 m above heater rods.

Pressurizer liquid volume, 0.36 m above heater rods.

Pressurizer liquid volume.

SG inlet plenum.

SG inlet plenum.

SG outlet plenum.

SG outlet plenum.

SG secondary side down-comer, 0.25 m above top of tube sheet.

28

Figure Number

3L-80

3M-64

3M-64

3L-8l

3M-65

3L-82

3M-65

3L-82

3L-83

Comments

Qualified.

Qualified, hot wall effects and limited time response.

Qualified, hot wall effects and limited time response.

Qualified, hot'wall effects and limited time response.

Qualified, possible hot wall effects after 40 s.




Qualified.




Secondary Coolant System (continued)

TE-SG-005

Blowdown Suppression System

TE-SV-OOl

TE-SV-002

TE-SV-003

TE-SV-004

TE-SV-006

TE-SV-007

Location

SG secondary side down-comer, 2.92 m above top of tube sheet.

BST, 0.3 m north of Downcomer 1, 0.53 m east of tank centerline, 2.72 m from tank bottom.






29

Figure Number

3L-83

3L-84

3L-84

3L-84

3L-84

3L-85

3M-66 3L-86

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.




Blowdown Suppression System (cont inued)

TE-SV-008

TE-SV-009

TE-SV-OlO

TE-SV-Oll

Reactor Vessel

TE-lAll-030

TE-lBlO-037

TE-lBll-028,

Location





Cladding on Fuel Assembly 1, Row A, Column 11, 0.76 m above bottom of fuel rod.

Cladd:i,ng on Fuel Assembly 1, Row B, Column 10, 0.94 m above bottom of fuel rod~

Cladding on Fuel Assembly 1, Row B, Column 11, at 0.71 m above bottom of fuel rod.

30

Figure Number

3L-86

3M-66 3L-86

3M-66 3L-86

3M-66 3L-85

3M-67

3L-87

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qua li fied.




Reactor Vessel (continued)

TE-lBll-032

TE-lB12-026

TE-lCll-021

TE-lCll-039

TE-lF07-0l5

TE-lF07-021

TE-lF07-026

TE-lF07-030

TE-lLP-OOl

Location

Cladding on Fuel Assembly 1, Row B, Column 11, at 0.81 m above bottom of fuel rod.

Cladding on Fuel Assembly 1, Row B, Column 12, 0.66 m above bottom of fuel rod.

Cladding on Fuel Assembly 1, Row C, Column 11, 0.53 m above bottom of fuel rod.

Cladding on Fuel Assembly 1, Row C, Column 11, 0.99 m above bottom of fuel rod.

Fuel Assembly 1, Row F, Column 7, 0.38 m above bottom of fuel rod.




Fuel Assembly 1, lower end box.

31

Figure Number

3L-87

3L-87

3M-67

3M-67

3L-88 3R-5

3L-88 3R-5

3L-88 3R-5

3L-88 3R-5

3M-68

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-lLP-002

TE-IST-OOl

TE-IST-002

TE-IST-003

TE-1ST-004

TE-IST-005

TE-1ST-006

TE-IST-008

TE-IST-009

TE-IST-OIO

TE-IST-Oll

TE-IST-012

TE-IST-013

Location


Downcomer Stalk 1, ,4.8 m from RV bottom.

Downcomer Stalk 1, 4.2 m from RV bottom.











32

Figure Number

3L-89 3R-6

3M-69 3L-90

3L-90

3L-90

3M-69 3L-90

3L-91

3L-91

3L-91

3L-92

3L-92

3M-69

3L-92

3L-92

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-1ST-014

TE-1ST-015

TE-1UP-00l

TE-1UP-002

TE-1UP-006

TE-1UP-007

TE-2E08-0ll

TE-2E08-030

TE-2E08-045

TE-2F07-0l5

Location

Downcomer Stalk 1, 1.17 m from RV bottom (inside of DTT).

Downcomer Stalk 1, 1 m from RV bottom (inside of DTT).

Fuel Assembly 1, upper end box.


Fuel Assembly 1, support column.


Cladding on Fuel Assembly 2, Row E, Column 8 at 0.28 m above bottom of fuel rod.



Cladding on Fuel Assembly 2, Row F, Column 7 at 0.38 m above bottom of fuel rod.

33

Figure Number

3L-9l

3M-69

3M-70

3L-93 3R-7

3L-94

3L-94

3M-71

3M-71

3M-71

3M-72

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-2F07-037 Cladding on Fuel 3M-72 Qualified. Assembly 2, Row F, Column 7 at 0.94 m above bottom of fuel rod.




TE-2F09-04l Cladding on Fuel 3M-73 Qualified. Assembly 2, Row F, Column 9 at 1.04 m above bottom of fuel rod.

TE-2G08-02l Cladding on Fuel 3M-73 Qualified. Assembly 2, Row G, Column 8 at 0.53 m above bottom of fuel rod.

TE-2G08-039 Cladding on Fuel 3M-73 Qualified. Assembly 2, Row G, Column 8 at 0.99 m above bottom of fuel rod.

TE-2G14-0ll Cladding on Fuel 3L-95 Qualified. Assembly 2, Row G, 3R-8 Column 14 at 0.28 m above bottom of fuel rod.

34





TE-2G14-030 Cladding on Fuel 3L-95 Qualified. Assembly 2, Row G, 3R-8 Column 14 at 0.76 m above bottom of fuel rod.

TE-2G14-045 Cladding on Fuel 3L-95 Qualified. Assembly 2, Row G, 3R-8 Column 14 at 1.14 m above bottom of fuel rod.

TE-2H02-028 Cladding on Fuel 3M-74 Qualified. Assembly 2, Row H, 3L-96 Column 2 at 0.71 m above bottom of fuel rod.

TE-2H08-039 Guide tube for fuel 3M-75 Qualified. Assembly 2, Row H, 3L-97 Column 8 at 0.99 m above bottom of guide tube.

TE-2H13-02l Cladding on Fuel 3L-98 Qualified. Assembly 2, Row H, Column 13 at 0.53 m above bottom of fuel rod.

TE-2H13-049 Cladding on Fuel 3L-98 Qualified. Assembly 2, Row H, Column 13 at 1.24 m above bottom of fuel rod.

TE-2H14-028 Cladding on Fuel 3L-98 Qualified. Assembly 2, Row H, Column 14 at 0.71 m above bottom of fuel rod.

35





TE-2H14-032

TE-2HlS-026

TE-2HlS-041

TE-2Il4-021

TE-2114-039

TE-2LP-00I

TE-2UP-00I

TE-2UP-002

TE-2UP-004

Location ------

Cladding on Fuel Assembly 2, Row H, Column 14 at 0.81 m above bottom of fuel rod.

Cladding on Fuel Assembly 2, Row H, Column IS at 0.66 m above bottom of fuel rod.

Cladding on Fuel Assembly 2, Row H, Column IS at 1.04 m above bottom of fuel rod.

Cladding on Fuel Assembly 2, Row I, Column 14 at 0.S3 m above bottom of fuel rod.

Cladding on Fuel Assembly 2, Row I, Column 14 at 0.99 m above bottom of fuel rod.





36

Figure Number

3L-98

3L-99

3L-99

3L-99

3L-99

3M-68

3M-70

3L-93 3R-7

3L-IOO

Comments ---

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-2UP-005

TE-3AII-030

TE-3BIO-037

TE-3Bll-028

TE-3Bll-032

TE-3B12-026

TE-3Cll-021

TE-3Cll-039

TE-3F07-015

Location


Cladding on Fuel Assembly 3, Row A, Column 11 at 0.76 m above bottom of fuel rod.

Cladding on Fuel Assembly 3, Row B, Column 10 at 0.94 m above bottom of fuel rod.




Cladding on Fuel Assembly 3, Row C, Column 11 at 0.53 m above bottom of fuel rod.

Cladding on Fuel Assembly 3, Row C, Column 11 at 0.99 m above bottom of fuel rod.

Cladding on Fuel Assembly 3, Row F, Column 7 at 0.38 m above bottom of fuel rod.

37

Figure Number

3L-IOO

3L-IOI 3R-9

3M-76

3M-74 3M-76 3L-96

3M-76

3M-76

3L-IOI 3R-9

3L-IOI 3R-9

3M-77

C ommen t_,,--s __

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-3F07-02l Cladding on Fuel 3M-77 Qualified. Assembly 3, Row F, Column 7 at 0.53 m above bottom of fuel rod.



TE-3LP-00l Fuel Assembly 3, lower 3L-102 Qualified. end-box.

TE-31P-002 Fuel Assembly 3, lower 3L-102 Qualified. end box.

TE-3UP-00l Fuel Assembly 3, upper end 3M-70 Qualified. box.

TE-3UP-008 1iquid level transducer 31-103 Qua lified. above Fuel Assembly 3.

TE-3UP-010 Liquid level transducer 3L-I03 Qualified. above Fuel Assembly 3.

TE-3UP-Oll Liquid level transducer 31-103 Qualified. above Fuel Assembly 3.

TE-3UP-012 Liquid level transducer 31-103 Qualified. above Fuel Assembly 3.

38





TE-3UP-013 Liquid level transducer 3L-104 Qualified. above Fuel Assembly 3.




TE-4E08-0ll Cladding on Fuel 3L-105 Qualified. Assembly 4, Row E, 3R-10 Column 8 at 0.28 m above bottom of fuel rod.

TE-4E08-030 Cladding on Fuel 3L-I05 Qualified. Assembly 4, Row E, 3R-IO Column 8 at 0.76 m above bottom of fue 1 rod.

TE-4E08-045 Cladding on Fuel 3L-105 Qualified. Assembly 4, Row E, 3R-10 Column 8 at 1.14 m above bottom of fuel rod.

TE-4F07-015 Cladding on Fuel 3L-I06 Qualified. Assembly 4, Row F, Column 7 at 0.38 m above bottom of fuel rod.

TE-4F07-037 Cladding on Fuel 3L-106 Qualified. Assembly 4, Row F, Column 7 at 0.94 m above bottom of fuel rod.

39





TE-4F08-028 Cladding on Fuel 3L-106 Qualified. Assembly 4, Row F, Column 8 at 0.71 m above bottom of fuel rod.

TE-4F08-032 Cladding on Fuel 3L-I06 Qualified. Assembly 4, Row F, Column 8 at 0.81 m above bottom of fuel rod.

TE-4F09-026 Cladding on Fuel 3L.:...I07 Qualified. Assembly 4, Row F, Column 9 at 0.66 m above bottom of fuel rod.

TE-4F09-04l Cladding on Fuel 3L-107 Qualified. Assembly 4, Row F, Column 9 at 1.04 m above bottom of fuel rod.

TE-4G02-030 Cladding on Fuel Assembly 4, 3M-78 Qualified. Row G, Column 2 at 0.76 m above bottom of fuel rod.

TE-4G08-02l Cladding on Fuel 3L-107 Qualified. Assembly 4, Row G, Column 8 at 0.53 m above bottom of fuel rod.

TE-4G08-039 Cladding on Fuel 3L-107 Qualified. Assembly 4, Row G, Column 8 at 0.99 m above bottom of fuel rod.

TE-4H01-037 Cladding on Fuel 3M-78 Qualified. Assembly 4, Row H, Column 1 at 0.94 m above bottom of fuel rod.

40








TE-4H14-028 Cladding on Fuel 3M-74 Qualified. Assembly 4, Row H, 3L-96 Column 14 at 0.71 m above bottom of fuel rod.

TE-4102-02l Cladding on Fuel Assembly 4, 3M-79 Qualified. Row I, Column 2 at 0.53 m above bottom of fuel rod.

TE-4102-039 Cladding on Fuel Assembly 4, 3M-79 Qualified. Row I, Column 2 at 0.99 m above bottom of fuel rod.

TE-4LP-00I Fuel Assembly 4, lower 3M-80 Qualified. end box.

TE-4LP-003 Fuel Assembly 4, lower 3M-80 Qualified. end box.

TE-4UP-OOl Fuel Assembly 4, upper 3M-70 Qualified. end box.

41

TAB1E 3-1. (continued)




TE-4UP-002

TE-4UP-004

TE-4UP-005

TE-5C06-024

TE-5C07-027

TE-5C07-03l

TE-5C07-43.8

TE-5D06-027

TE-5D06-03l

1ocation




Guide tube for Fuel Assembly 5, Row C, Column 6 at 0.61 m above bottom of guide tube.

Figure Number

31-93 3R-7

31-108

31-108

3M-8l 31-109

Cladding on Fuel Assembly 5, 3M-82 Row C, Column 7 at 0.69 m above bottom of fuel rod.

Cladding on Fuel Assembly 5, 3M-82 Row C, Column 7 at 0.79 m above bottom of fuel rod.

Cladding on Fuel 3M-82 Assembly 5, Row C, Column 7 at 1.11 m above bottom of fuel rod.

Cladding on Fuel 31-110 Assembly 5, Row D, Column 6 at 0.69 m above bottom of fuel rod.

Cladding on Fuel 31-110 Assembly 5, Row D, Column 6 at 0.79 m above bottom of fuel rod.

42

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.




Reactor Vessel ~continued)

TE-5D06-43.8 Cladding on Fuel 3L-IIO Qualified. Assembly 5, Row D, Column 6 at 1.11 m above bottom of fuel rod.

TE-5D07-027 Cladding on Fuel 3M-58 Qua lified. Assembly 5, Row D, 3M-83 Column 7 at 0.69 m above bottom of fuel rod.

TE-5D07-031 Cladding on Fuel 3M-83 Qualified. Assembly 5, Row D, Column 7 at 0.79 m above bottom of fuel rod.

TE-5D07-43.8 Cladding on Fuel 3M-83 Qualified. Assembly 5, Row D, Column 7 at 1. 11 m above bottom of fuel rod.

TE-5F03-024 Guide tube for Fuel 3M-8l Qualif ied. Assembly 5, Row F, 3L-I09 Column 3 at 0.61 m above bottom of guide tube.

TE-5F04-0l5 Cladding on Fuel 3M-84 Qualified. Assembly 5, Row F, Column 4 at 0.38 m above bottom of fuel rod.


43






TE-5F04-062 Cladding on Fuel 3M-84 Qualified. Assembly 5, Row F, Column 4 at 1. 57 m above bottom of fuel rod.

TE-5F08-026 Cladding on Fuel Assembly 5, 3M-85 Qualified. Row F, Column 8 at 0.66 m 3L-11l above bottom of fuel rod. 3U-9

3R-ll

TE-5G06-0ll Cladding on Fuel Assembly 5, 3M-86 Qualified. Row G, Column 6 at 0.28 m 3L-112 above bottom of fuel rod. 3R-12

TE-5G06-030 Cladding on Fuel Assembly 5, 3M-86 Qualified. Row G, Column 6 at 0.76 m 3L-112 above bottom of fuel rod. 3R-12

TE-5G06-045 Cladding on Fuel Assembly 5, 3M-86 Qualified. Row G, Column 6 at 1.14 m 3L-112 above bottom of fuel rod. 3R-12

TE-5G06-062 Cladding on Fuel Assembly 5, 3M-86 Qualified. Row G, Column 6 at 1. 57 m 3L-112 above bottom of fuel rod. 3U-lO

3R-12

TE-5H05-002 Cladding on Fuel 3M-87 Qualified. Assembly 5, Row H, 3L-113 Column 5 at 0.05 m a,bove 3R-13 bottom of fuel rod.

44

TAB1E 3-1. (continued)

Variable, System, and Figure Detector 10cation Number Comments ----



TE-5H05-015 Cladding on Fuel 3M-87 Qualified. Assembly 5, Row H, 31-113 Column 5 at 0.38 m above 3R-13 bottom of fuel rod.

TE-5H05-049 Cladding on Fuel 3M-87 Qua li fied. Assembly 5, Row H, 31-113 Column 5 at 1.24 m above 3R-13 bottom of fuel rod.

TE-5H06-024 Cladding on Fuel Assembly 5, 3M-88 Qualified. Row H, Column 6 at 0.61 m 31-114 above bottom of fuel rod. 3R-14

TE-5H06-028 Cladding on Fuel Assembly 5, 3M-74 Qualified. Row H, Column 6 at 0.71 m 3M-88 above bottom of fuel rod. 31-96

31-114 3R-14

TE-5H06-032 Cladding on Fuel Assembly 5, 3M-88 Qualified. Row H, Column 6 at 0.81 m 31-114 above bottom of fuel rod. 3U-ll

3R-14

TE-5H06-037 Cladding on Fuel Assembly 5, 3M-88 Qualified. Row H, Column 6 at 0.94 m 31-114 above bottom of fuel rod. 3R-14

TE-5H07-008 Cladding on Fuel 3M-89 Qualified. Assembly 5, Row H, 31-115 Column 7 at 0.20 m above bottom of fuel rod.

TE-5H07-026 Cladding on Fuel 3M-89 Qualified. Assembly 5, Row H, 31-115 Column 7 at 0.66 m above bottom of fuel rod.

45





TE-5H07-04l

TE-5H07-058

TE-5I04-027

TE-5I04-43.8

TE-5I06-005

TE-5I06-02l

TE-5I06-039

TE-5I06-054

Location








Cladding on Fuel Assembly 5, Row I, Column 6 at 1.37 ~ above bottom of fuel rod.

46

Figure Number

3M-89 3L-115

3M-89 3L-115

3L-116

3L-116

3M-90 3L-11 7 3U-12

3M-90 3L-117

3M-90 3L-117

3M-90 3L-117

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.





TE-5J03-024

TE-5J04-005

TE-5J04-02l

TE-5J04-039

TE-5J04-054

TE-5J08-026

TE-5LP-001

TE-5LP-002

TE-5L06-026

Location

Guide tube for Fuel Assembly 5, Row J, Column 3 at 0.61 m above bottom of guide tube.

Cladding on Fuel Assembly 5, Row J, Column 4 at 0.13 m above bottom of fuel rod.







Cladding on Fuel Assembly 5, Row L, Column 6 at 0.66 m above bottom of fuel rod.

47

Figure Number

3M-8l 3L-l09

3L-118

3L-118

3L-118

3L-118

3M-9l 3L-119

3M-68

3L-89 3R-6

3L-120

Comments

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.


Variable, System, and Figure Detector Location Number Comments ---



TE-5L07-43.8 Cladding on Fuel 3L-120 Qualified. Assembly 5, Row L, Column 7 at 1.11 m above bottom of fuel rod.

TE-5L08-0ll Guide tube for Fuel 3M-92 Qualified. Assembly 5, Row L, Column 8 3L-12l at 0.28 m above bottom of 3R-15 guide tube.

TE-5L08-024 Guide tube for Fuel 3M-92 Qualified. Assembly 5, Row L, Column 8 3L-121 at 0.61 m above bottom of 3R-15 guide tube.

TE-5L08-039 Guide tube for Fuel 3M-92 Qualified. Assembly 5, Row L, Column 8 3L-12l at 0.99 m above bottom of 3R-15 guide tube.

TE-5L08-045 Guide tube for Fuel 3M-92 Qualified. Assembly 5, Row L, Column 8 3L-12l at 1.14 m above bottom of 3R-15 guide tube.

TE-5M06-024 Guide tube for Fuel 3M-8l Qualified. Assembly 5, Row M, 3L-109 Column 6 at 0.61 m above bottom of guide tube.

TE-5M07-0l5 Cladding on Fuel 3M-93 Qualified. Assembly 5, Row M, Column 7 at 0.38 m above bottom of fuel rod.

TE-5M07-026 Cladding on Fuel 3M:"93 Qualified. Assembly 5 , Row M, Column 7 at 0.66 m above bottom of fuel rod.

48

TABLE 3-1. ( c on t i nued )




TE-5M07-032 Cladding on Fuel 3M-93 Qualified. Assembly 5, Row M, Column 7 at O.Bl m above bottom of fuel rod.

TE-5M07-062 Cladding on Fuel 3M-93 Qualified. Assembly 5, Row M, Column 7 at 1. 57 m above bottom of fuel rod.

TE-5UP-003 Fuel Assembly 5, upper 3L-122 Qualified. end box.

TE-5UP-004 Fuel Assembly 5, upper 3L-122 Qualified. end box. 3R-16

TE-5UP-OIO Fuel Assembly 5, upper 3L-122 Qualified. end box. 3R-16

TE-5UP-Oll Fuel Assembly 5, upper 3L-122 Qualified. end box. 3R-16

TE-5UP-013 Fuel Assembly 5, upper 3M-94 Qualified. end box.




TE-6G02-030 Cladding on Fuel 3L-123 Qualified. Assembly 6, Row G, Column 2 at 0.76 m above bottom of fuel rod.

49





TE-6G14-011

TE-6G14-030

TE-6G14-045

TE-6HOl-037

TE-6H02-028

TE-6H02-032

TE-6H03-026

TE-6H13-0l5

Location Figure Number

Cladding on Fuel Assembly 6, 3M-95 Row G, Column 14 at 0.28 m above bottom of fuel rod.



Cladding on Fuel 3L-123 Assembly 6, Row H, Column 1 at 0.94 m above bottom of fuel rod.



Cladding on Fuel 3L-124 Assembly 6, Row H, 3R-17 Column 3 at 0.66 m above bottom of fuel rod.

Cladding on Fuel 3M-96 Assembly 6, Row H, Column 13 at 0.38 m above bottom of fuel rod.

50

Comments


Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.

Qualified.








TE-6H15-026 Cladding on Fue 1 3M-97 Qualified. Assembly 6, Row H, Column 15 at 0.66 m above bottom of fuel rod.

TE-6H15-04l Cladding on Fuel 3M-97 Qualified. Assembly 6, Row H, Column 15 at 1.04 m above bottom of fuel rod.

TE-6I02-02l Cladding on Fuel 3L-124 Qualified. Assembly 6, Row I, 3R-17 Column 2 at 0.53 m above bottom of fuel rod.

TE-6I02-039 Cladding on Fuel 3L-124 Qualified. Assembly 6, Row I, 3R-17 Column 2 at 0.99 m above bottom of fuel rod.

51





TE-6Il4-021 Cladding on Fuel 3M-97 Qualified. Assembly 6, Row I, Column 14 at 0.53 m above bottom of fuel rod.

TE-6Il4-039 Cladding on Fuel 3M-97 Qual ified. Assembly 6, Row I, Column 14 at 0.99 m above bottom of fuel rod.

TE-6LP-001 Fuel Assembly 6, lower 3L-125 Qua 1 i fied. end box.

TE-6LP-002 Fuel Assembly 6, lower 3L-89 Qualified. end box. 3R-6

TE-6LP-003 Fuel Assembly 6, lower 3L-125 Qualified. end box.




TE-6UP-004 Fuel Assembly 6, 3L-126 Qualified. support column.

TE-6UP-005 Fuel Assembly 6, .3L-126 , Qualified. support column.

52

TAB1E 3-l, (continued)

Variable, System, and Figure Detector 1ocation Number Comments



TF-5F08-26 Pellet at Fuel Assembly 5, 3M-85 Qualified. Row F, Column 8 at 0.66 m 3M-99 above bottom of fuel rod. 31-111

3U-13 3R-ll

TF-5Fl2-26 Pe llet at Fuel 3M-99 Qualified. Assembly 5, Row F, 31-127 Col1:lmn 12 at 0.66 m above bottom of fuel rod.

TF-5H10-26 Pe llet at Fuel 3M-99 Qualified. Assembly 5, Row H, 31-127 Column 10 at 0.66 m above bottom of fuel rod.

TF-5IlO-26 Pellet at Fuel 3M-99 Qualified. Assembly 5, Row I, 31-127 Column 10 at 0.66 m abov

Documents

NUREG/CR-2826, 'Experiment Data Report for Loft …Experiment L2-5 simulated a double-ended offset shear of a cold leg in the primary coolant system. The primary coolant pumps were