ML19309A507

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In-plant Safety Relief Valve Test Plan
ML19309A507
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 01/31/1980
From:
NUTECH ENGINEERS, INC.
To:
Shared Package
ML19309A468 List:
References
NPL-01-008, NPL-1-8, NUDOCS 8003310374
Download: ML19309A507 (100)
v • d • e


Text

Controlled Copy MPL-01-008 I

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GRAND GULF IN-PLANT SAFETY RELIEF VALVE TEST

- TEST PLAN -

REV. 0 l

I Prepared for:

MISSISSIPPI POWER AND LIGHT COMPANY I Prepared by:

NUTECH Proj ect Approval: [] [wm W. J. McConaghy N#

I NUTECH Approval and Release: yII//j>,

  1. A. ).I'Ifeb(f f , C Date: bO

, g g310374 nutech

I REVISION CONTROL SHEET i

REPORT NUMBER: FIPL- 08

SUBJECT:

Grand Gulf In-Plant Safety I Relief Valve Test - Test Procedure 1

I L. A. Conrad Technical Leader g[/6 NAME/ TITLE INITIAL A. F.

Deardorff,

P.E. a Engineering Manager Mb N/JIE/ TITLE INITIAL I PRE- ACCURACY CRITERIA REV PRE-PARED ACCURACY OECK CRITERIA OECK PAGE REV PARED OECK OECK PAGE I li- 0 I67C T~O N/N A 0 [86- @ b iv A h /L A-5 1 0 1-2 2 0 2-3 I 3 3-5 0

I 4 4-24 0

S 0 I 5-18 y u 27 6-1 0 f(jc g x i

QEP-001.1-00 l

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I MPL-01-008 I TABLE OF CONTENTS Page LIST OF TABLES............................................ 111 LIST OF FIGURES............................................ iv 1.0 1NTRODUcT10N......................................i.,

l 2.0

SUMMARY

.......................................... 2.1 1

3.0 TEST OBJECTIVES.................................. 3.1 3 .1 Safety Relief Valve Discharge Line Loads.... 3.2 3.2 Suppression Pool Pressure Loads............. 3.3 3.3 Quencher Support Loads...................... 3.4 3.4 Submerged Structure Loads................... 3.4 I 3.5 Pool Thermal Mixing Data.................... 3.5 4.0 TEST INSTRUMENTATION............................. 4.1 4.1 Required Instrumentation.................... 4.1 4.2 Data Acquisition System..................... 4.6 4.3 Assurance of Instrumentation Integrity...... 4.7 4.4 SRV Discharge Line Air Bleed System......... 4.8 5.0 1ESTS............................................ 5.i g

5 .1 Test Matrix and Schedule.................... 5.1 5.2 Criteria for Test Operations................ 5.5 5.3 On-Site Data Evaluation..................... 5.6 5.4 Reporting Results........................... 5.9

6.0 REFERENCES

....................................... 6.1 APPENDIX A - REQUIRED INSTRUMENTATION......................A.0 u nutech

I MPL-01-008 I LIST OF TABLES I

Table Page '

4-1 Pressure Sensor Locations and Response Ranges...... 4.9 4-2 Strain Gage Locations and Response Ranges.......... 4.11 4-3 Temperature Sensor Locations and Response Ranges... 4.14 4-4 Sensor Environmental conditions.................... 4.15 5-1 Test Matrix........................................ 5.12 5-2 Test Matrix - Definition of Abbreviations and...... 5.14 ,

Footnotes  !

5-3 Multiplier (t) for Calculation of 95-95............ 5.17 iI Pressure Load I

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111

I MPL-01-008 LIST OF FIGURES I Figure Page I 2-1 Grand Gulf Pressure Suppression Containment........ 2.3 4-1 Suppression Pool Pressure Sensors - Plan View...... 4.16 4-2 I Suppression Pool Pressure Sensors - ............... 4.17 Elevation View 4-3 SRV Discharge Line V12 Pressure Sensors............ 4.18 4-4 Suppression Pool Strain Gages - Plan View.......... 4.19 4-5 Suppression Pool Strain Gages - Elevation View..... 4.20 4-6 Suppression Pool Temperature Sensors - ............ 4.21 Plan View 4-7 Suppression Pool Temperature Sensors - ............ 4.22 Elevation View 4-8 Data Acquisition System............................ 4.23 4-9 SRV Line Air Bleed System - Schematic Diagram...... 4.24 5-1 Grand Gulf SRV Test Schedule....................... 5.18 I

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.I MPL-01-008 t,o INTRODUCTION I This test plan describes in detail the in-plant safety relief valve tests to be conducted at the Grand Gulf Nuclear Station Unit 1 (Grand Gulf). The purpose of the testing is to provide actual measurementa of the pressure loads which are imposed on the suppression pool boundary during safety relief valve (SRV) actuations and to verify that these ueasured pressure loads are conservative when compared to the X-quencher design loads shown in Appendix 6A to the Grand Gulf FSAR (Referente 1) and the Interim Containment Loads Report (ICLR), Rev. 2 (Reference 2).

The test has been designed to provide pressure measurements at various locations on the suppression pool boundary during single, consecutive and multiple valve actuations. Measurements of the pressures inside the SRV discharge line and X-quencher will also be taken. Sufficient hydrodynamic data will be gathered to extend the pressure data from the load cases tested to design conditions. Two additional objectives of this test are to verify the design adequacy of various submerged structures which are subjected to these SRV loads and to measure the suppression pool <

temperature distribution during an extended SRV discharge. All tests will be conducted in conjunction with normal plant start-up testing.

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I M P I, 0 0 8 This test plan has been prepared by NUTECil and representa the l combined efforts of Mississippi Power and Light Company (MP&1.),

llechtel, NUTECil, Wyle Laboratories and Middle South Services (MSS) personnel. A nummary in presented in Section 2.0. The I

test obj ectives are dicussed in Section 3.0. Section 4.0 doncribes the instrumentation layout and the data acquisition system. The test matrix and test schedule are described in l Section 5.0.

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T I

MPL-01-008 I 2.0

SUMMARY

I The overall objective or this test program is to verify that the measured pressure loads are lower than those design values used in Appendix 6A of the FSAR thus fulfilling the requirements of the NRC's " Acceptance Criteria for Quencher Loads for the Mark III Containment", (Reference 3). An outline of the Grand Gulf pressure suppression containment is shown in Figure 2-1. The specific areas of the plant to be instrumented are:

1) Safety relief valve discharge line
2) X-quencher hub and support
3) Suppression pool boundary (including containment wall, drywell wall, basemat and weir wall)
4) Submerged structures: Reactor Core Isolation Cooling System (RCIC) turbine exhaust line and RHR return line
5) Suppression pool for thermal mixing characterist.: cs I Test instrumentation will be installed to measure pressure loads and the associated submerged structure loads as well as the ther-mal mixing characteristics of the suppression pool during SRV discharge. Single, consecutive, multiple and extended relief valve actuations will be tested.

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I MPL-01-00d Most of the instrumentation in the suppression pool will be located in the vicinity of the three quenchers which will be tested. Pressure transducers will measure the transient pres-8:tres at the suppression pool boundaries during SRV discharge.

Sttain gages will be used to measure the effects of SRV actuation on the quencher piping, quencher support, an RCIC turbine exhaust and an RHR return line. Temperature sensors in the suppression pool in addition to the pool temperature monitoring system will provide temperature distribution data.

A low range pressure transducer installed in the SRV discharge line will provide information on the water level recovery inside the SRV discharge line following valve closure. Other pressure transducers will measure the SRV discharge line and quencher internal pressures during the SRV line clearing transient.

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I MPL-01-008 I

I COMTAIMMENT WALL

MAIN STEAM l

LINES

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--- - SAFETY

  • . RELIEF

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DRYW ELL _ .,

  • S V DISCHARGE I WALL Q _- y

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.. . - WElR WALL

' - I - SUPPRESSIOu

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I I Figure 2-1. GRAND GULF PRESSURE SUPPRESSION CONTAINMENT I

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I MPL-01-008 3.0 TEST OBJECTIVES

I The test objectives of the Grand Gulf SRV Test are to measure iI pressure loads, the associated submerged structure loads and the suppression pool thermal response due to safety relief valve discharge. Three adjacent quenchers, located at azimuths 0 ,
16*, and 32*, have been selected for testing. The 0* quencher was selected because it is the discharging device for V10, the low-low set SRV. As such, this valve is expected to open for every transient involving relief valve actuations which occurs during plant operation, including all single, consecutive, and multiple (with the exception of automatic depressurization (ADS))

SRV actuations and all the scheduled start-up transient tests.

The test matrix will include each of these types of tests.

Due to the similarity among all SRV discharge line geometries in Grand Gulf, the internal line pressures as well as the suppres-sion pool clearing pressures are expected to vary only slightly during actuations of different SRVs. The quencher at azimuth 32*, V12, was selected for its close proximity to various sub-merged structures, including an RCIC turbine exhaust line and an RHR return line. The 32* quencher is expected to produce the largest drag loads on these structures due to its proximity.

The quencher at azimuth 16 , V11, was selected to closely ap-proximate the asymmetric load case in Reference 1 and to minimize the pool area / quencher area ratio, thus simulating maximum pool 3-1 nutech g

MPL-01-008 I

pressures due to an all-valve case in the vicinity of quencher V11, during a simultaneous multiple valve actuation of valves V10, V11 and V12.

I Single and multiple valve actuations will be performed to deter-mine "first pop" loads on the pool wall and submerged structures.

Consecutive valve actuations will be performed to determine "second pop" loads. An extended valve actuation will be performed to provide pool thermal mixing data.

I The following subsections contain a discussion of the specific test objectives for each area of interest and describe the basis for instrument application.

I 3.1 Safety Relief Valve Discharge Line Loads I

Steam discharge from a safety relief valve results in a rapid pressurization of the discharge pipe during the water clearing phase of the transient. The maximum discharge line pressure is expected to occur near the SRV outlet. To confirm that the actual internal pipe pressures are below design values, pressure transducers will be installed downstream of the SRV exit on the V-12 discharge line. The pressure transducers will be positioned approximately 20 feet downstream of the SRV outlet to avoid entrance and pipe bend effects. The selection of which line to I 3-2 I

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.I MPL-01-008 I measure pressure is not critical because all of the SRV discharge line geometries in Grand Gulf are nearly identical.

Following closure of an SRV, steam will condense within the dis-charge pipe, reducing pipe pressure below that in the drywell and containment air space. As a result of this depressurization, suppression pool water will reflood the discharge pipe and air will enter the pipe from the drywell through the vacuum breaker.

A low range pressure sensor will be installed downstream of the SRV outlet of the 32* discharge line. This sensor will provide I data which will be used to determine the water leg height sub-sequent to valve closure after the water leg height has stabilized.

I 3.2 Suppression Pool Pressure Loads I

SRV actuation results in compressed air bubbles being expelled from the discharge device into the suppression pool. The air bubbles expand and contract as they rise to the pool surface, imposing oscillatory loads on the pool walls and submerged structures.

To provide test confirmation that the loading due to SRV actua-tion is less than that shown in Appendix 6A to the Grand Gulf FSAR (Reference 1), pressure transducers will be installed on the suppression pool floor, walls and weir wall. The locations of 3-3 nutech l

I MPL-01-008 these transducers have been selected to provide measurement of single SRV loads and the combined pressure effects for multiple valve actuations.

3.3 I Quencher Support Loads The quencher and quencher support are expected to be subjected to oscillatory pressure loads and drag forces imparted by the ex-panding and contracting air bubble as well as water clearing, air clearing and steam discharge phases of the transient. The load-ing on this equipment due to SRV discharge will be determined using strain gages.

In addition to the strain gages, pressure transducers will be located in the 32* quencher hub (V12) and quencher arm to provide pressure transient data.

I 3.4 Submerged Structure Loads I The RCIC exhaust line, and an RHR return line, both of which are located near the V12 quencher at 32' will be instrumented with strain gages to measure strain due to submerged structure loading. Strain gages on the RHR return line and the RCIC turbine exhaust will measure bending strain resulting from SRV discharge.

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I MPL-01-008 3.5 Pool Thermal Mixing Data I Temperature sensors will be installed in the suppression pool. ,

The sensor locations have been chosen to allow collection of pool thermal mixing data during an extended SRV discharge test. The sensors which comprise the in-plant suppression pool temperature monitoring system will also be utilized in conjunction with the test sensors to measure the local (i.e., the temperature of the water in which the discharging steam condenses) and bulk pool temperatures. Data from the plant pool temperature recorders will be evaluated and compared with calculated bulk pool temper-I atures.

Reactor system data will be monitored during the extended dis-charges to determine the SRV steam flow rate for prediction of the bulk suppression pool temperature.

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I MPL-01-008 4.0 TEST INSTRUMENTATION This section provides a detailed description of the test instru-mentation as well as a discussion of the data acquisition system, the assurance of instrumentation integrity and the SRV discharge line air bleed system.

I 4.1 Required Instrumentation I Three types of instrumentation are required to achieve the test obj ective discussed in Section 3.0. These are pressure trans-I ducers, strain gages and temperature sensors. Tables 4-2 through 4-4 provide the identification, location, response range and environmental conditions of the required instrumentation. In-strtimentation location drawings are presented in figures 4-1 through 4-6. Instrumentation requirements and specifications are provided in Appendix A. The basis for each sensor location is given below.

I Pressure Transducers I Pressure transducer locations have been selected to allow for over 25% failures without compromising the obj ectives of the test. Sensors P1, P6 and P13 (Figures 4-1 and 4-2) are located on the drywell wall at the quencher elevation and are expected to measure the maximum pressure on the drywell wall during actuation 4-1 nutech I

I MPL-01-008 I of valves V12 (Az 32*), V11 (Az 16 ) and V10 (Az 0*), respec- )

tively. Sensors P2, P7 and P14 are expected to measure the maximum floor pressure during tests of V12, VII and V10, respec-tively.

I Due to the symmetrical arrangement of each of the quenchers with respect to the drywell and containment walls and nearly identical SRV discharge line geometries, the above sensors provide backup for each other. If one sensor from each pair fails, the maximum pressure at that point can be estimated by extrapolating the data from another valve along with that data from the remaining trans-ducer (floor or drywell wall). The same is true for containment wall sensors P3, P9, P10 and P15. Transducers P7, P8 and P12 are used to measure the maximum floor pressure during the three valve, multiple valve actuation tests. Transducer P12 is located to measure the combined floor pressure during the two valve test.

I Pressure transducers P4, P5 and P11 will measure the vertical attenuation in the pool to confirm the attenuation methodology utilized in Reference 1. The sensors which measure pressure attenuation with distance outside of the immediate quencher vi-cinity are P16-P20. Of these, P16, P18 and P19 are located so as iI to verify the line-of-sight assumption of pressure attenuation.

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I MPL-01-008 I The V12 SRV discharge line will be instrumented (Figures 4-2 and 4-3) to measure the transient and steady state internal pipe pressures, the transient and steady state internal quencher pres-sures, and the internal pipe pressure after valve closure. Only one line will be instrumented because all the SRV line air vol-umes are nearly the same and the water legs are identical. Thus, the pipe pressure responses are expected to be very similar.

Redundancy is provided for both pipe pressure, P21 and P22, and quencher pressure, P23 and P24. The pipe pressure sensors will be positioned approximately 20 feet downstream of the SRV to avoid entrance and pipe bend effects. The quencher pressure will be measured at two points; the bottom of the quencher cone and the entrance to one of the quencher arms. The low pressure transducer, P25, will be used to determine the water level in the SRV line after reflood has occurred and the water leg has stabi-lized.

I Pressure transducers P26 and P27 will measure the pressure loads on the weir wall. The two transducers have been located at the centerline elevation of the upper and middle horizontal vents at the 12* azimuth.

Pressure transducers P1 through P20 and P26 and P27 will be lo-cated above structural stiffeners to avoid the possibility of I liner " ringing" affecting the sensor output signal. Stiffeners are spaced sufficiently close to each other to allow the sensors 4-3 nutech

I MPL-01-008 to be placed above a stiffener but remain within 12" of the lo-cations shown in Tables 4-1 through 4-3. Actual pressure trans-ducer locations will be documented.

Strain Gages Strain gages will be inst lled on selected structures to measure the loads imposed on these structures during both the water / air clearing transient which immediately follows SRV actuation and the subsequent steady state steam discharge which lasts until valve closure.

Four structures will be instrumented with strain gages (Ta-bles 4-2 and Figures 4-4 and 4-5). Quencher V12 will have four strain gages on the SRV line just above the quencher cone, three strain gages and one strain rosette en the quencher base, and three strain gages and one rosette on the quencher base side support. The RCIC turbine exhaust adjacent to quencher V12 will be instrumented with four strain gages below the upper support hanger and four strain gages midway between the upper and the lower support hangers. The RHR return line will have four strain gages located midway between the first two bends on the horizon-I tal run inside the suppression pool and three strain gages and one rosette on the vertical run midway between the suppression pool sarface and the first bend. With these strain gage con-figurations, bending stresses will be determined for the turbine 4-4 nutech I

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MPL-01-008 I exhaust, the RHR return line and the quencher cone /SRV line tran-sition. Principal strains will be determined from strain gages on the quencher base and side support and on the RHR return line.

All strain gages have been located in the zones of maximum ex-I pected stress.

Temperature Sensors Along with the existing suppression pool temperature monitoring system, 16 additional test sensors will be installed to measure the suppression pool thermal response to SRV actuation (Ta-ble 4-3). Both the plant monitoring system sensors and the additional test sensors are shown on Figures 4-6, 4-7. The existing plant sensors are sufficient to measure the overall pool temperature distribution so additional sensors will be installed only in the vicinity of discharging quencher V10 (azimuth 0*) for the extended valve test. Sensors T1 through T4 will be located at a point one foot below and above the anter of the quencher hole pattern. These sensors are expected to measure the local temperature of the water feeding the steam condensation process. T5 through T10 will be located on the drywell wall 4*

to each side of quencher V10 at 3 elevations. Due to their symmetric arrangement with respect to quencher V10, T5-T7 and T8-T10 can be used as backups to each other. T11 through T13 are expected to measure the naximum containment wall temperature.

Test sensors T14 through T16 will show the pool temperature 4-5 nutech

i MPL-01-008 differences between the wall temperature sensors nearest the discharging quencher (TS-TIO) and those farthest from the discharging quencher (TE N024A, B, C, D). j i

l 4.2 Data Acquisition System The Grand Gulf safety relief valve tests will require 61 fast channels of instrumentation with a maximum frequency response capability of 200 Hz. The signals from the fast channel instru-mentation will be processed through appropriate signal conditioning equipment and stored in digital format on magnetic tape. Each sensor will be scanned at 1000 samples /second.

Approximately 25% of the fast channel instrumentation will be recorded on oscillograph recorders to provide real time data.

The real time data will be compared to the appropriate acceptance criteria following each test. After analysis of this real time data shows that all safety criteria are satisfied, the test program may proceed.

An additional 16 slow-response (0-3 HZ) thermocouples will be located in the suppression pool. Thermocouple outputs for the extended valve test will be scanned every 30 seconds and recorded i in real time on a Fluke Data Logger.

Figure 4-8 shows a schematic of the data acquisition system.

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l MPL-01-008 4.3 Assurance of Instrumentation Integrity Safety relief valve test programs, which have been previously conducted at other nuclear power plant sites, have experienced  !

1 some failures of underwater instrumentation. In most instances, these failures have been attributed to water in-leakage through connectors and cabling. To prevent this problem from occurring during the Grand Gulf SRV test program, all underwater connectors and cabling will be enclosed in either integrally welded stain-less steel sheath or in tubing with pressure tight connecting fittings.

All strain gages and temperature sensors will undergo a hydro- ,

l static leak rate test prior to shipment by the vendor. Strain  !

gages will be tested to 1500 psig; temperature sensors will be tested to 700 psig. The underwater connectors on the pressure sensors have been successfully used and qualified by Wyle Labora-tories for previous SRV test programs.

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MPL-01-008 1

4.4 SRV Discharge Line Air Bleed System An air bleed system will be installed on the 0*, 16' and 32*

discharge lines. A schematic of this system is shown on Figure 4-9. When actuated prior to an SRV test, this system will equal-ize the discharge line and drywell air space pressures. This pressure equalization ensures that the discharge line water leg height is coincident with the suppression pool water surface, thus ensuring repeatability of test conditions. The air bleed

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system will be actuated prior to all normal water leg (NWL) tests.

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M M M M M M M M Table 4-1 PRESSURE SENSOR LOCATIONS AND RESPONSE RANGES LOCATICN

  • SENSOR EXPECIED FREQUENCY EWIRON-SENSOR ID ElIV. RESIm SE RANGE FOiT NGIES TYlli A2. RAD.

Pressure P1 32* 41'-6" 10-35 psia 0-200 11: El 98'-Oh Pressure P2 32* 51'-6" 10-35 psia 0-200 11:

93'-Of" Pressure P3 32" 62'-0" 10-35 psia 0-200 11:

93' - Of" Pressure P4 16* 107'-0" 41'-6" 10-35 psia 0-200 H:

Pressure P5 16* 102'-4" 41'-6" 10-35 psia 0-200 11:

Pressum P6 16* 41'-6" 10-35' psia 0-200 11:

y 98'-h" Pressure P7 16" 51'-6" 10-35 psia 0-200 11:

93'-Of" Pressure P8 24* 4 6' - 6" 10-35 psia 0-200 11: " ) Suppression 93'-Of" Pool Sensors Pressum P9 16 62'-0" 19-35 psia 0-200 11:

93'-Of" Pressure 16 62'-0" 10-35 psia 0-200 11:

P10 98'-h" Pressure P11 16* 107'-0" 62'-0" 10-35 psia 0-200 11:

Pressure P12 8* 4 6' - 6" 10-35 psia 0-200 11:

93'-0f'" a Pressure P13 0* 41'-6" 10-35 psia 0-200 11: f 98'-Of" Pressure P14 0* 51'-6" 10-35 psia 0-200 II: "

93'-Of" o Pressure P15 0* 62'-0" 10-35 psia 0-200 11: " @

98'-Of" 10-35 psia 0-200 II: "

C Pressum P16 344* 98'-Oh" 41'-6" J

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(;9 sensor locations are approximate. Actual locations may vary because of equipment obstructions or local O *Al of ct considerations.

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M M M M Table 4-1 (co*tinued)

PRESSURE SENSOR LOCATIONS AND RESPONSE RANGES IDCATICN

  • SENSOR SENSOR ,

EXPECIED FREQUENCY ENVIRON-TYE ID AZ. ELEV. RAD. RESP (ESE RANGE ENT NCHES Pressure P17 344 93'-Oh" 51'-6" 10-35 psia 0-200 11: El Pressure P18 304* 41'-6" 10-35 psia 0-200 11: El 98'-Of" Suppression P 1 nsors Pressure P19 304* 51'-6" 10-35 psia 0-200 ti: El 93'-Of" Pressure P20 304* 62'-0" 10-35 psia 0-200 11: El 9d'0-f" Pressure P21 e See Figure 4-3  :-- 0-400 psia 0-200 11: E5 Panstream of SRV I i y Pressure P22 .a See Figure 4-3  : 9-400 psia 0-200 11: E5 Downstream of SRV l 1 e Pressure P23  : See Figure 4-2 > 0-700 psia 0-200 11: E4 Inside QuencherHut I i Pressure P24 4 See Figure 4-2  : 0-700 psia 0-200 11: E4 Inside Quencher Air i i Pressure P25 4 See Figure 4-3 > 0-25 psia 0-200 11: E5 Im Range Pressure Sensor -Downstream of SRV Pressure P26 12* 104'-4" 34'-0" 10-35 psia 0-200 H E5 Weir Wall

  • -sure P27 12" 100'-2" 34'-0" 10-35 psia 0-200 11: E5 Weir Wall 2::

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C kN *All sensor locations are approximate. Actual locations may vary because of equipment obstructions or local O effect consideraticas.

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m m m m m m m m m m m Table 4-2 STRAIN GAGE LOCATIONS AND RESPONSE RA GES IDCATICN

  • SENSOR SENSOR EXPECIED FREQUENCY ENVIRON-1YIE ID AZ. EllN. RAD. RESIWSE RAN ENT NOTES infin ,

Strain Gage SGI 32*

101'-ff" 46'-6" 0.0001-0.002 0-200 11: El Axial Strain Cage SG2 32* 101'-h" 46'-6" 0.0001-0.002 0-200 11: El Axial Strain Cage SG3 32* 46'-6" 0.0001-0.002 0-200 11: El Axial 101'-h" Strain Gage SG4 32*

101'-h" 46'-6" 0.0001-0.002 0-200 11: El Axial Strain Gage SGS 32* 42'-0" 0.0001-0.002 0-200 11: El Axial 95'-h"

. Strain Gage SG6 32* 93' d" 42'-0" 0.0001-0.002 0-200 11: El Axial C '

Strain Gage SG7 32* 94'- 42'-0" 0.0001-0.002 0-200 11: El Axial Strain Gage SG8 32*

94'-h" 42'-0" 0.0001-0.002 0-200 11: El Rosette **

Strain Gage SG9 32" 94'-h" 42'-0" 0.0001-0.002 0-200 11: El Rosette **

Strain Gage SG10 32* 94'- 42'-0" 0.0001-0.002 0-200 11: El Rosette **

Strab. C ;s #4 11 34* 100'-2" 53'-8" 0.0001-0.002 0-200 11: El Axial Strain Gage SG12 34* 100'-2" d-8" 0.0001-0.001 0-200 11: El Axial 2:

Strain Gage SG13 34" 100'-2" 53' 8" 0.0001-0.001 0-200 11: El Axial 5 E

Strain Gage SG14 34" 100'-2" 5','-8" 0.0001-0.001 0-200 11: El Axial y Strain Gage SG15 34* 106'-3" '33'-8" 0.0001-0.001 0-200 11: El Axial Strain Gage SG16 34* 106'-3" 53'-8" 0.0001-0.001 0-200 11: El Axial C

  • "4" k) *All sensor locations are approximate. Actual locations may vary because of equipment obstmctions or local O effect costsiderations.

M M M M M M M M M M M M M M Table *-2 (continued)

STRAIN GAGE LOCATIONS AND RESPONSE RANGE IDCATION

  • SENSOR SENSOR EXPECED FREQUENCY ENTIRON-1YPE ID A2. EIIV. RAD. resin SE RANGE MhT M7ES in/in Strain Gage SG17 34* 106'-3" 53'-8" 0.0001-0.001 0-200 11: El Axial Strain Gage SG18 34* 106'-3" 53'-8 ' O.0001-0.001 0-200 11: El Axial Strain Gage SG19 29" 109'-4" 61'-6" 0.0001-0.001 0-200 11: El Axial Strain Gage SG20 29* 109'-4" 61'-6" 0.0001-0.001 0-200 II: El Axial Strain Gage SG21 29* 109'-4" 61'-6" 0.0001-0.001 0-200 II: El Axial Strain Gage SG22 29 109'-4" 61'-6" 0.0001-0.001 0-200 11: El Rose t te**

x.

L Strain Gage SG23 29" 109'-4" 61'-6" 9.0001-0.001 0-200 11: El Rosette * *

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, Strain Gage SG24 29 109'-4" 61'-6" 0.0001-0.001 0-200 H: El Rosette **

Strain Cage SG25 44*

107'-h" 58'-6" 0.0001-0.001 0-200 11: El Axial Strain Gage SG26 44* 107'- 58'-6" 0.0001-0.001 0-200 11: El Axial Strain Gage SG27 44* 107'- 58'-6" 9.0001-0.001 0-200 H: El Axial Strain Gage SG28 44* 58'-6" D.0001-0.001 0-200 II: El Axial 107'-4h" Strain Gage SG29 32* 95'-9h" 47'-6" 3.0001-0.001 0-200 11: El Rose tte*

  • 1 o Strain Gage SG30 32* 95'-9 "

7 47'-6" 3.0001-0.001 0-200 11: El Rosette ** 7 o

Strain Gage SG31 32* 47'-6" 3.0001-0.001  ?-200 ti: El 5 95'-h" Rose tte*

  • 3 Strain Gage SG32 32*

95'-9h" 46'-6" ).0001-0.001 0-200 11: El Axial C

e9=

lY *All sensor locations are approximate. Actual locations may vary because of equipment obstructions or local O effect considerations.

I

M M M M WM M M M M M M M & M M M Table 4-2 (continued)

STRAIN GAGE LOCATIONS AND RESPONSE RANGE IDCATIm*

N SENSOR EXPECIED FREQUENCY ENVIRON-TYE ID AZ. EIEV. RAD. RESPWSE RAN2 MNT MNES in/in Strain Gage SG33 32' 95'-9f" 46'-6" 3.0001-0.001 0-200 H: El Axial Strain Gage SG34 32' 95'-9f" 45'-6" 3.0001-0.001 0-200 11z El Axial

  • All sensor locations are approximate. Actual locations may vary because of equi Inent obstructions or local effect cmsiderations.
    • Three (3) strain gages are arranged to fonn a rectangular rosette with I gage parallel to the longitudinal axis of the pipe and 1 gage oriented along the circumference of the pipe.

t r

C C

C 00 C

e ty)

O "T

m m m M M M M M M M M M M M M M M M Table 4-3 TEMPERATURE SENSOR LOCATIONS AND RESPONSE RANCE IDCATION* EXPECIED St.NSOR SliNSOR -

RESIU4SE FREQUENCY lYpE ID AZ. ELliV. N RAD. (*F) RANGE Temperature TI 358* 45'-0" 50-150 96'-6f" 0-3 El Below quencher am Temperature T2 358 45'-0" 50-150 99'-6f" 0-3 El Above quencher am Temperature T3 2" 45'-0" 50-150 96'-6f" 0-3 El Below quencher am Temperature T4 2* 99'-6f" 45'-0" 50-150 0-3 El Above quencher am Temperatu:e TS 4" 41'-6" 50-150 Drywell wall 98'-Of" 0-3 El p Temperature T6 4 107'-0" 41 ' - 6 '.' 50-150 0-3 El Drywell wall Temperature T7 4* 111'-0" 41'-6" 50-150 0-3 El Drywell wall Temperature T8 356 41'-6" 50-150 98'-Of" 0-3 El Drywell wall Temperature T9 356* 107'-0" 41'-6" 50-150 0-3 El Drywell wall Temperature T10 356* 111'-0" 41'-6" 50-150 0-3 El Drywell wall Temperature T11 0* 98'-Of" 62'-0" 50-150 0-3 El Containment wall Temperature T12 0* 107'-0" 62'-0" 50-150 0-3 El Containment wall g Temperature T13 0* 111'-0" 62'-0" 50-150 0-3 El Containment wall 5 e

1 Temperature T14 ~20' 98'-0 "

7 41'-6" 50-150 0-3 El Drywell wall [

Temperature TIS 20* 107'-0" 41'-6" 50-150 0-3 El Drywell wall Temperature T16 20* 111'-0" 41'-6" 50-150 0-3 El Drywell wall f

t '/ *All sensor locations are approximate. Actual locations may vary because of equipment obstructions or local O effect considerations.

O

i MPL-01-008 1

I Table 4-4 I SENSOR ENVIRONMENTAL CONDITIONS l

dl - Conditions in Suppression Pool  ;

(1)

Fluid . . . . . . . . . . . . . . . . . Water I Pressure . . . . . . . . . . . . . . .

Temp e ra tu re . . . . . . . . . . . . . .

50 psia 50 F-200 F

. (2) E2 - Conditions in Drywell l

Fluid . . . . . . . . . . . . . . . . . Air Pressure . . . . . . . . . . . . . . . 15.4 psia Rel . Ilumidity . . . . . . . . . . . . . 100%

Temperatu:c . . . . . . . . . . . . . . 135"F (3) E3 - Conditions in SRV Discharge Line and Quencher Assembly

.I Fluid . . . . . . . . . . . . . . . . . Water / Steam / Air 400 F l

Temperature . . . . . . . . . . . . . . l Pressure . . . . . . . . . . . . . . . 700 psia 1

(4) E4 - Combination of El and E3_

Sensor will be in the SRV discharge line and the "outside" of the sensor and its cabling will be exposed to conditions in suppression pool.

(5) ES - Combination of E2 and E3 l I Sensor will be in the SRV discharge line and the "outside" of the sensor and the cabling will be

)

I exposed to conditions in the drywell.

.I I

I 4.15 nutech )

I - - - - - - - - - - - _ _ . . _ _ _ _ . _ _. __

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I l Figure 4-1. SUPPRESSION P0ut PRESSURE SENSORS - PIAN VIIM I

i I 4.16 I

nutech

l I

l MPL-01-008 f ^

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\ P14 LOCATED EFORE FIRST MOW OF f () HOLES. El" P' ROM QUENCHER. d.

I .

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I Figure 4-2. SUPPRESSION POOL PRESSURE SENSORS -

I ELINATION VIEN nutech 4.17

MPl-01-008 SRV VlE I

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t VACUU M g v 4

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- - R.CIC TURSIME 8 -l r_i __ - -

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m M M M M M M M M M M M M M M M M OSCILIDGRAPli _-

Digital REW RDERS Data 110NEYWELL 1508 Analog

=

Data r-------------------------------~-]

TO STRAIN STRAIN GAGE

\hT) P SOR' DIGITAL l AND AND PRESSURE l ANALOG llANDLING ---- BUFFER, ~ MAGNETIC l b

" =

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l u DIGITAL l MOGTO ##

l l DITIGAL l l CONVERTER CONW RTER VISIIAY 2100 b---------

= OSCILIDGRAPII TEMPERATURE FLUKE

  • - DATA PRINTER SENSORS
  • LOGGER l

l Figure 4-8. DATA ACQUISITION SYSTEM r l  :=

"3 a C 7 l

  • o l @ s O

7

,I MPL-01-008 A.C. or D.C. Voltage Source

l

! a f Manual Switch at Data Acquisition Station l

I Containment Penetration

;

!II SRV Discharge Line I

'I '  %

Solenoid Valve Normally Closed

' yg)

' i ' 1 VIZ

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p 1 w w ,

} x VII I c 1" Biced Line with Two Valve in Series (Typical) 1 I

Figure 4-9. SRV LINE AIR BLEED SYSTEM -

SCilEMATIC DIAGRAM g

4.24 nutech

I MPL-01-008 I 5.0 TESTS 5.1 Test Matrix and Schedule I

The test matrix is presented in Table 5-1. Definitions and foot-notes for the Test Matrix are contained in Tabic 5-2. The test matrix includes single, consecutive, multiple and extended valve actuations. The tests have been selected to provide a data base which can be extended to the design load cases. The Grand Gulf SRV test schedule is presented in Figure 5-1. The order of testing in the matrix has been selected to minimize the hold time required between tests.

5.1.1 Single Valve Actuations The test matrix provides for single valve actuations of the 0*,

16 and 32* azimuth SRV discharge lines. All lines are expected to produce loads of almost equal magnitude because all three of the SRV lines are of very similar configurations (as are all the SRV lines in the Grand Gulf Nuclear Station). However, separate actuations of the three valves will show the relative amount of data spread which can be expected during first pop conditions.

More detailed pressure / distance attenuation information can also I

be gathered by actuating these different valves.

I 5-1 nutech g

I MPL-01-008 5.1.2 Consecutive Valve Actuations Consecutive valve actuation tests will be performed with the V10 (0") and V12 (32*) SRV lines. The 0* line contains the low-low set SRV. This SRV is used in the Grand Gulf FSAR as the consecu-tive load case since, by design, this valve is the only one which is expected to experience a consecutive valve actuation (CVA).

CVA's will be run on the 32* line to gain more detailed pressure /

distance attenuation data and also to measure the effect of the possible higher CVA loads on the submerged structures. Again, actuation of this valve is expected to show the magnitudes of data spread which can occur with slightly different line condi-tions for the CVA case. The valve open and valve closed times for these CVA's have been selected to bound the conditions which are expected to occur in the plant during operating transients (Reference 1).

5.1.3 Multiple Valve Actuation I The multiple valve actuation cases given in Reference 1 are 1) two adjacent SRV'S, 2) eleven SRV's, 3) eight SRV's (ADS actua-tion), and 4) all valves. The two adjacent valve cases will be tested by simultaneous actuation of V10 and V11 (Az 0 and 16*).

Of the remaining cases, al:. of which cause symmetric loading on the containment, the design basis is the actuation of all twenty valves. Multiple valve actuations with three valves are also l 5-2 nutech 1

MPL-01-008 included in the test matrix. Extrapolation of the two and three valve data base, as well as the single and consecutive valve actuation data, is expected to provide the necessary data for comparison to the design basis case. In performing the multiple valve tests, the SRV's tested will be actuated simultaneously.

Ilowever, to minimize a reactor flux transient and subsequent scram, the SRV's will be closed separately at spaced intervals as shown in the test matrix.

5.1.4 Extended Valve Actuations An extended valve actuation will be performed to provide pool thermal mixing data. SRV V10 (Az. O*) will be utilized for the extended valve actuation because:

I 1) Its discharge location in the suppression pool sim-plifies the task of gathering bounding data with the fewest additional sensors

2) There are few structures at the containment wall opposite quencher V10 to interfere with the measure-ment of the maximum containment wall temperature.

The plant pool temperature monitoring system will be activated and the data recorded during the extended valve actuation test.

The sixteen test temperature sensors will be scanned every 30 5-3  ;

rititenc:ti !

MPL-01-008 seconds and their output recorded on a data logger recorder. All pressure and strain data will be recorded at the beginning of the test and periodically throughout the course of the test to gain data on quencher steam condensation loads.

SRV discharge will continue until the pool temperature approaches the limit, as defined in the Plant Technical Specifications.

5.1.5 Plant Transient Tests Although not an integral or necessary part of the In-Plant Test, the normal startup test program will provide a number of additional SRV actuations where supplemental data may be acquired. Reactor vessel pressurization and SRV actuations are expected to result from the all-MSIV closure and generator load rejection startup tests. Prior to the initiation of these tests, the data acquisition system will be activated to record both pressure and strain data. This supplemental data is useful since valves will actuate with their own time phasing depending on the vessel pressure rise rate and on their pressure setpoints. These tests can therefore provide actual timing and load magnitude information for multiple valve and possible subsequent actuations of the lowest set-point valve.

l l

l l

5-4 nutech

MPL-01-008 These tests have been included in the Test Matrix to provide supplemental information to the data base. In the event hydro-dynamic data is not collected during the transient start-up test, the overall objectives of the test program will not be jeopardized.

5 .1. 6 Shakedown Tests Shakedown tests have been provided in the test matrix for the purpose of ensuring proper instrumentation and data acquisition system operation prior to the start of the main test program.

5.2 Criteria for Test Operations Specific test results and operating parameters will be monitored prior to, during, and after each specific test to assure that the I test program can proceed as planned. Criteria will be estab-lished at two levels. Level I criteria will be established to assure that the plant is operated within design and techical I

specification limits. Level II criteria will be established to monitor parameters as related to expected performance during the test. These acceptance criteria are documented in the Test Procedure (MPL-01-010).

5-5 nutech

MPL-01-008 5.2.1 Level I Criteria If Level I criteria are not satisfied, the plant must be placed in a hold condition that is judged to be satisfactory and safe based on previcus testing. Resolution of the problem must be pursued immediately, and following resolution the applicable test portion must be repeated to verify the Level I requirement is satisfied. Level I criteria are established to ensure the plant is operated within design and technical specification limits.

5.2.2 Level II Criteria Level 2 criteria are associated with expected system transient response whose characteristics might be improved by equipment adj us tments . If Level 2 criteria are not met, plant operating or test plans would not necessarily be altered. An investigation would be made, and the test repeated following resolution to verify the Level 2 requirements are met.

5.3 On Site Data Evaluation This section provides an on site data evaluation procedure for determining a statistical basis for the suppression pool pressure loads from single and three-valve actuations.

5-6

nutech

MPL-01-008 5.3.1 Single Valve Data Evaluation Procedure I 5.3.1.,

Upon completion of matrix te ts MT1 through MT32, calculate the mean (X) and the standard deviation (c) of the highest real time peak boundary pressures from all of the SVA, CP, INL matrix tests. Calculate these parameters again for the CVA, AWL tests.

I 5.3.1.2 Calculate the 95-95 pressure load separately for both the SVA and the CVA tests using the following equation:

P = 5 + ot I where:

I P = 95-95 pressure load X = Measured peak pressure mean t = Multiplier from Table 5-3 o = Standard deviation 5.3.1.3 Compare P to Po (acceptance criterion for suppression pool pressure).

I 5-7 nutech

MPL-01-008 IfPfP o for both SVA and CVA tests, continue on to the next matrix test.

If P > P g for either the SVA oc the CVA tests, perform an addi-tional test run of that test type and recalculate X and a based on all runs of this matrix test. For CVA retests, the conditions which resulted in the highest measured real time boundary pres-I sure should be repeated.

5.3.2 Three-Valve Data Evaluation Procedure 5.3.2.1 Upon completion of the matrix tests MT60 through MT100, calculate the mean (X) and the standard deviation (a) of the highest real time peak pressures of the three-valve MVA's.

5.3.2.2 Calculate the 95-95 pressure load using the following equation:

P = X + ot I

I I

I 5-8 nutech ll

f MPL-01-008 where:

I i

P = 95-95 pressure load X = Measured peak Pressure mean j t = Multiplier from Table 5-3 o = Standard deviation 1

5.3.2.3

! Compare P to Po (acceptance criterion for suppression pool pres-sure).

I l If P f Po , continue on to the next matrix test.

If P > P o, perform an additional test run and recalculate E and a 1

based on all runs of this matrix test. Return to Step 5.2.2.1.

I 5.4 Reporting Results I

5.4.1 Quick Look Report A preliminary " quick look" report will be issued after the com-pletion of testing. This report will be based on the real time data and will contain the following:

I lI 5-9 nutech

I MpL-01-008

1) General discussion of the test data
2) Tabulation of the maximum stresses, pressures and pool temperatures observed in the real time data
3) Comparison of the above results to the acceptance criteria and/or expected results
4) Discussion and comparison of results for single, consecutive and multiple valve actuations
5) Discussion of test data variation
6) Preliminary conclusions en the test program I

5.4.2 Final Report A draft final report will be issued following the completion of testing. The report will be based on all test data. Highlights of the report will be as follows:

1) Discussion of instrumentation locations, calibra-tions, signal conditioning system, data collection and reduction
2) Discussion of the test data variation, including instrument uncertainty
3) Tabulation of maximum and minimum values of all data channels for each test condition
4) Discussion of test results and comparison to accep-tance criteria and/or expected results g 5-io g

nutech

I Mpt-01-00S i

I 5) Discussion and comparison of test results for single, consecutive and multiple valve actuations

6) Representative plots of all data in engineering units for each condition tested
7) Conclusions regarding the goal of the test program to demonstrate that the NRC's acceptance criteria (Ref-crence 3) for the X-quencher is met.

I I

I I

I I

4 I

I I

I I

5-11 nutech l

l __ _ _ _ _ _ _ __--__

M M M M M M M M M M M M M M M M M M Table 5-1 TEST MATRIX II)(0)

INITIAL (INDITICNS VALVE CLOSURE PIPE (DOLING VAL \E(S)

TEST TEST 10 BE SRV POOL P0hER DISOIART TDE PRIOR PPIOR 10 IEST NINBER 1YPE ACluA1ED(10) PIPE IDP(*F) LEVEL (%)(11) TDE(SEC.) 10 CVA (MIN:SEC)

SD1 SD 0*(F051D) CP,hh1(2) See Note 4 See Note 5 5 N/A See Note 6 SD2 SD 16*(F047A) CP,Nh1 See Note 4 See Note 5 5 , N/A See Note 6 SD3 SD 32*(F041E) CP,Nh1 See Note 4 See Note 5 5 N/A See Note 6 Mr1 SVA 0* CP,PML See Note 4 50-75 (TC3) 5 N/A See Note 6 Mr2 SVA 16' CP,hh1 See Note 4 50-75 (103) 5 N/A See Note 6 Mr3 SVA 32* CP,Nh1 See Note 4 50-75 (103) 5 N/A See Note 6

. Mr10 SVA 0* 7,hh1 See Note 4 50-75 (TC3) 20 1 Min. See ?bte 6 -

ss

" Mill CVA 0* HP,Ah1(3) See Note 4 50-75 (103) 10 1 Min. 1 Min.

Mr12 CVA 0* IIP,Ahl See Note 4 50-75 (103) 5 30 Min. 1 Min.

Mr13 CVA 0* hP,Aht See Note 4 50-75 (103) 5 30 Min. 30 Min.

Mil 4 CVA 0* hP,AhL See Note 4 50-75 (103) 5 N/A 30 Min.

Mr20 SVA 16* 7,Nht - See Note 4 50-75 (103) 5 N/A See Note 6 Mr30 SVA 32' CP,hh1 See Note 4 50-75 (103) 20 See Note 7 See Note 6 Mr31 CVA 32* See Note 7 See Note 4 50-75 (103) See Note 7 See Note 7 See Note 7 Mr32 CVA 32* See Note 7 See Note 4 50-75 (103) See Note 7 N/A See Note 7 Mr40 MVA 0*,16* T,hht See Note 4 50-75 (TC3) 10,5 N/A See Note 6 y t~

MISO MVA 0*,16* T ,hh1 See Note 4 50-75 (103) 10,5 N/A See Note b '

3 7 C

re 8

=

%)

O 3*

m M M M M M M M M M M M M M M M M Table 5-1 (continued)

TEST MATRIX ( )( )

INITIAL CONDITIONS VALVE (S) VALVE CILSURE PIPE COOLING TEST TEST TO EE SRV POOL PChTR DIS 0 W CE TIME PRIOR PRIOR TO TEST MNBER 1TPE ACIUATED(10) PIPE IIMP (*F) EVEL(%) (11) TIME (SEC.) 1U CVA (MIN:SEC)

MT60 WA (f,16 .32 CP, El See Note 4 50-75 (TC3) 15,10,5 N/A See Note 6 MI70 WA 0 ,16 ,32 CP, 21 See Note 4 50-75 (TC3) 15,10,5 N/A See Note 6 0 U 0 IG80 WA 0 ,16 ,32 CP, El See Note 4 50-75 (103) 15,10,5 N/A See Note 6 MT90 MVA 0 ,16 ,32 CP, 21 See Not 4 50-75 (TC3) 15,10,5 N/A See Note 6 MT100 MVA 00,16 0 ,3 0 CP, W1 See Note 4 50-75 (TC3) 15,10,5 N/A See Note 6 0 See Secticn 5.1.4 See Note 6 MT110 ESVA 0 CP, NWL See Note 4 50-75 (TC3) N/A

's TT1 MSIV Auto (9) CP, 21 See Note 4 95-100 (TC6) Variable N/A See Note 6 u Closure j Tf2 Genera- Auto (9)  ! CP,21 See Note 4 95-100 (106) Variable N/A See Note 6 tor Inad i Rejec-tion

  • C 3 7 C
  • a M o O

7

I MPL-01-008 I Table 5-2 TEST MATRIX - DEFINITION OF ABBREVIATIONS AND FOOTNOTES ABBREVIATIONS:

SD = Shakedown Test MT = Matrix Test TT = Transient Startup Test SVA = Single Relief Valve Test CVA = Consecutive Relief Valve Test MVA = Multivalve Test ESVA = Extended Single Valve Test CP = Cold Pipe NWL = Normal Water Level AWL = Actual Water Level WP = Warm Pipe HP = Hot Pipe I

NOTES:

(1) Additional tests shall be performed if necessary to pro-vide a statistical basis for the limiting single, consect-tive and cultiple actuation cases. The procedures for determining these statistical bases are given in Section s.2.

I l (2) NWL implies that the level of the discharge pipe water leg is coincident with the suppression pool water surface.

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lI MPL-01-008 Table 5-2 (continued)

I (3) AWL implies that the level of the discharge pipe water leg I has reached a steady state value which is below NWL.

11 (4) An initial suppression pool temperature shall be main-tained within tS *F for all SRV, CVA and MVA testa.

(5) Shakedown tests shall be performed when the reactor power is high enough to support steady state steam flow through an SRV discharge line. Test condition TC2 (per G.E. spec-ification 22A5722) is the recommended power level for these tests.

I (6) Prior to a cold pipe SRV actuation, the pipe temperature shall be f 150*F or the pipe shall have cooled for at I least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a previous actuation.

Ij (7) The valve closed time prior to CVA tests MT31 and MT32 J

will be the valve closed time which resulted in the high-est real time pool boundary pressure for tests MT11 to MT14.

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I MPL-01-008 I Table 5-2 (continued)

I (8) All RHR circulation shall be shutoff prior to all tests to ensure the suppression pool is stationary. The time interval between RHR shutoff and valve actuation which is required to ensure static water conditions shall be determined during pre-startup ECCS testing.

(9) Additional data will be recorded during safety relief valve actuations which occur during normal startup testing. Safety relief valve actuations will occur during the Generator Load Rejection and the all MSIV Closure I transient tests.

(IG) Valve Designations shown in parenthesis correspond to the actual control room identification on the valve mode switches.

I (11) Abbreviations in parenthesis correspond to the startup test conditions as described in the General Electric spec-ification 22A5722, Rev. C.

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MPL-01-008 I Table 5-3 MULTIPLIER (t) FOR CALCULATION OF 95-95 PRESSURE LOAD I

Value of t as a function of n, the nisber of tests perfonned at a given test condition.

I n= 5 6 7 8 9 10 15 20 30 40 50 t = 4.19 3.67 3.36 3.14 2.99 2.88 2.54 2.38 2.21 2.12 2.06 I

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'Ihe values of t are based on a 95% probability of non-exceedance and 1

95% confidence.

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M M M M M M M M M M M M M M M M M WEEKS

^ 14 10 -s 4 - L o 2. 4- 6 8 to 12. 14 IG 18 20 EE E4 26 28 30 ES */o

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FUEL LOAD. 50 % POWER POWER POWER ,oo g goo g INITI AL HEATUP POWER ggow pgow TEST SETUP A A SHAKEDOWN O '

TESTING j

SHAKEDOWN DATA A A

, EVALUATION T

2 G TEST M ATRI X A A

r TRAhJSIENT O STARTUP TESTS I

(100*4 POWER) l FULL MSiv CLOSURE i

T-6 LOAO REJEC. TION f*RELIMIMARY A A z (Q UIC K LOO K) @

REPORT a F lM AL REPORT &

A $00 1

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C r$

i G Figure 5-1. GRAND GULF SRV TEST SCilEDULE g

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  • MPL-01-008 l

6.0 REFERENCES

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Grand Gulf Nuclear Station, FSAR Docket No. 50-416, l 1.

50-417.

1 I 2. Interim Containment Loads Report (ICLR) - Mark III Con-tainment, GE Document No. 22A4365, Rev. 2.

3. NRC " Acceptance Criteria for Quencher Loads for Mark III Containment", July 16, 1976. l 1

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' l APPENDIX A l

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l REQUIRED INSTRUMENTATION  ;

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l MPL-01-008 I SENSOR REQUIREMENTS Type of Sensor: Pressure Transducer ,

I Sensor Identification (s): P1 to P20 and P26-P27 i

Location: Suppression Pool I Expected Response: 10-35 psia Frequency Range: 0 Hz to 200 IIz Environmental Conditions:

Atmosphere: Water, Air, Steam Temperature: 50 F to 270 F Pressure (psia): 50 Manufacturer /Model: Bell 6 Ilowell/ CEC-1000-0207 I Operating Range / Accuracy: 0 to 100/+2% of F.R.O.

Additional Information:

Sensors will be supplied with special 1/2" thread and six I electrical brazed terminal cup to replace standard clectrical connector. Sensors will have 150' of steel sheath cabling.

Extension cabling will be P/N 6XE 24-1936STJ, Type "E" Teflon I wire, overall stranded shield with Teflon tape jacket. All wires shall meet the fire protection guidelines of NFPA-803 and IEEE 383-1974. Signal conditioning shall be supplied I via Vishay Model 2100.

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I MPL-01-008 SENSOR REQUIREMENTS Type of Sensor: Pressure Transducer Sensor Identification (s): P21 to P24 Location: SRV Discharge Line and Quencher Expected Response: 0 to 700 psia Frequency Range: 0 liz to 200 liz Environmental Conditions:

Atmosphe re : We . Air, Steam Temperature: 400'F Pressure (psia): 700 Manufacturer /Model: Bell f llowell/

i CEC-1000-0208 Operating Range / Accuracy: 0 to 1000 psia /+2% of F.R.O.

Additional Information:

Sensors will be supplied with special 1/2" thread and six I clectrical brazed terminal cup to replace standard electrical connector. Outer case of sensors P23 and P24 will be exposed to water, air, and steam at 50 psia and 50 to l 270 F.

Sensors will have 150' of steel sheath cabling. Extension cabling will be P/N 6XE 24-1935STJ , Type "E" Teflon wire , overall stranded shield with Teflon tape jacket. All wires shall meet the fire protection guidelines of NFPA-803 and IEEE 383-1974. Signal conditioning shall be supplied via Vishay Model 2100.

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neu-ui-uuo SENSOR REQUIREMFNTS Type of Sensor: Pressute Transducer (Low Range)

Sensor Identification (s): P25 Location: SRV Discharge Line Expected Re.,Jonse:

, 0 to 25 psia Frequency Range: 0 IIz to 200 liz Environmental Conditions:

Atmosphe re : Air, Water, Steam Temperature: 400 F Pressure (psia): 700 Manu facture r/ Mode l: Validyne/AP-10-1219 Operating Range / Accuracy: 0-50 psia /+1/2% of F.S.

Additional Information:

Outer case of sensor will be exposed to air, 10 0 % R . II . at 15.4 psia and 135 F. Signal conditioning shall be supplied via Validyne carrier demodulator Model CD15. Wiring shall meet fire protection guidelines NFPA803 and IEEE 383-1974.

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r SENSOR REQUIREMENTS u

- Type of Sensor: Strain Gage u

Sensor Identification (s): S1 to S34 m

Location: Netwell Submerged Structures e

E Expected Response: N/A

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Frequency Range: 0 Hz to 200 Hz F

L Environmental Conditions:

- Atmosphe re : Water, Air, Steam Temperature: 50 F to 270 F E Pressure (psia): 50 L

Manufacturer /Model: Ailtech/MG125/20-01H-6S*

Operating Range / Accuracy: .020 in/in/+3%

Additional Information:

  • Temperature compensation based on SA106 Gr. B steel. Sensors will have 150 feet of 1/16" 0.D. steel sheath cable with three open leads. Sensors will be hydrostatically tested to 2500

[ psig and 500 F prior to shipment by the vendor.

Extension wire shall be P/N 3XE 24-196STJ, Type "E",

F 600V. Teflon wire with stranded shield and Teflon jacket.

L All wires shall meet the fire protection guidelines NFPA803 and IEEE 383-1974. Signal conditioning shall be supplied via Vishay Model 21J0.

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l MPL-01-008 I SENSOR REQUIREMENTS Type of Sensor: Temperature (Thermocouple)

Sensor Identification (s): T1 to T16 I Location: Suppression Pool l

Expected Response: 60-150 F l Frequency Range: 0 llz to 3 Hz J Environmental Conditions:

Atmosphere: Air, Water Steam Temperature: 50 to 200 F Pressure (psia): 50 i Manufacturer /Model: Medtherm/TC-T-150-10350 i Operating Range / Accuracy: 0-600 F/+1.5 F l l

I Additional Information:

I Thermocouples are copper /Constantan with grounded tip and 150 feet of steel sheath cabling. Additional wire from termination of steel cable to data acquisition system will be type "T", 20 ANG, shielded Teflon coated jacket and wires. All wire shall meet the fire protection guidelines of NFPA803 and IEEE 383-1974. All sensors will be hydro-statically tested to 700 psig prior to shipment by the vendor.

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