ML18044A712
| ML18044A712 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/01/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578, TASK-06-06, TASK-6-6, TASK-RR NUDOCS 8004070305 | |
| Download: ML18044A712 (21) | |
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consumers Power company General Offices: 212 Wast Michigan Avenue, Jackson, Michigan 49201 * (G17) 768-0550 April 1, 1980 Director, Nuclear Reactor Regulation Att Mr.Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE.DPR PALISADES PLAi\fT - TIII MODIFICATIONS -
- 2. 1. 8 .. a ADDITIONAL INFORMATION Consumers Power Company committed to provide more detailed information pertaining to the Containment Hydrogen Monitoring System (NUREG-0578, Section 2 ._i.8. a).
Attached is a system design description for tae proposed Containment Hydrogen lfonitoring System for the Palisades Plant.
David P Hoffman Nuclear Licensing Administrator CC. JGKeppler, USNRC Attachment 19 pages r
soo4010 ~cs
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SYSTEM DESIGN DESCRIPTION Page _l_ of __lL 1-*-
' PROJECT: Palisades Plant System No. 77 5 SYSTEM:
Post-Accident Radiation Monitoring Containment Hydrogen Monitoring Revision No. 0 EDITION: l!I Conceptual OPreliminary OFinal Date: March 3, 198()
CONSUMERS POWER COMPANY PALISADES PLANT POST-ACCIDENT RADIATION MONITORING JOB 64-0330-000 GWO None .
SYSTEM DESIGN DESCRIPTION NO. 1-775-51-02 FOR CONtAINMENT HYDROGEN MONITORING SYSTEM
SYSTEM DESIGN DESCRIPTION Page _2_ of J1_
( PROJECT: Pali sades Pl ant System No. 775
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Post-Acc1dent Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 ED IT ION: II Conceptual 0 Preliminary OFinal Date: March 3, .1980 TABLE OF CONTENTS Page
1.0 INTRODUCTION
- 4 1* 1 SYSTEM FUNCTIONS ************************************ 4
- 1. 2
SUMMARY
DESCRIPTION ********************************* 4 1.3 CLASSIFICATION ************************* ~ ************ 5 1.4 DEFINITIONS AND ACRONYMS **************************** 5 2.0 OPERATION *************************** ~ *************** 6
( 2. l PRIMARY OPERATING MODE ******************************
\.,_ 6 2.2 SECONDARY OPERATING MODES ****** ~ ******************** 6 2.3 SPECIAL OR INFREQUENT OPERATING MODES *************** 6
- 2. 3. l' Emergency ******************** ~ ******************* ~ ** 6 2.3.2 Start-Up ****.*.**.***.**.......* **.**. *:._.* * ..****.... 6 2.3.3 Shutdown ******************************************** 6 3.0 DESIGN CRITERIA ************************************* 7
- 3. l GOVERNMENTAL REGULATIONS AND GUIDES ***************** 7 3.2 INDUSTRY CODES, STANDARDS, AND GUIDES ** ~ ************ 8 3.3 CORPORATE STANDARDS AND GUIDES ******************* ~ ** 9 3.4 MANUFACTURER S REQUIREMENTS *************************
1 9
3.5 PLANT INTERFACE CRITERIA **************************** 10
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3.6 CLIENT REQUIREMENTS ********************************* 10
SYSTEM DESIGN DESCRIPTION Page -. of _l_9_
(.,*- PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: II Conceptual OPreliminary OFinal Date: March 3, 1980 TABLE OF CONTENTS (Continued)
Page 4.0 DETAILED DESCRIPTION ******************************** 11 4.1 COMPONENTS.a**************************************** 11 4.1. l Descrip~ion ***************************************** 11
- 4. 1. 2 Design Data ***************************************** 15 4.2 INSTRUMENTS, CONTROLS, ALARMS, AND PROTECTIVE DEVfCES ******* ~******************1****************** 15 .
4.3 IMPACT ON STRUCTURES AND OTHER SYSTEMS ************** 16 I
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5.0 *SAFETY ********************************************** 17 6.0 fv1A.I NTENANCE* *********** ~ ********************* ~ ******* 18
7.0 REFERENCES
- . 19
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SYSTEM DESIGN DESCRIPTION Page ~ of __]2_
( PROJECT: Pa1isades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: Ill Conceptual OPreliminary OFinal Date: March 3. 1980
1.0 INTRODUCTION
1.1 SYSTEM FUNCTIONS The function of the system is to pro vi de p1ant personne 1 with an indication of the hydrogen concentration in the containment building atmosphere during an after an accident.
- 1. 2
SUMMARY
DESCRIPTION The hydrogen concentration in the containment atmosphere does not pose a problem during normal plant operation. Therefore, there is no requirement to circulate the containment atmosphere through the hydrogen detector unless an accident occurs.
System operation is actuated by a plant operator.
The system samp1es the containment atmosphere and monitors the sample for hydrogen concentrations *. A hydrogen sensitive detector provides an output signal to the system electronics proportional to the hydrogen concentration detected. The
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SYSTEM DESIGN DESCRIPTION 5 Page--of-19 PROJECT: Palisades Plant System No. 775
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Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: *Conceptual 0 Preliminary OFinal Date: March 3, 1980 signal is conditioned and transmitted to the readout instrumenta-tion in the control room. Alarms, both visual and audible, are provided for alerting personnel to abnormal hydrogen concentrations.
1.3 CLASSIFICATION The system is seismic Category I and non-Quality Group, except for the containment isolation portions which are in* accordance
( with Regulatory Guides 1.26, 1.29, and 1.97, respectively.
- 1. 4 DEFINITIONS AND ACRONYMS Not Applicable I
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SYSTEM DESIGN DESCRIPTION Page -. of ..JL
( PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: El Conceptual 0 Preliminary OFinal Date: March 3. 1980 2.0 OPERATION 2.1 PRIMARY OPERATING MODE The system is designed to operate during and after an accident as defined in Phase I and Phase II, ANS 4.5, Draft 4, November 1979.
2.2 SECONDARY OPERATING MODES Not Applicable 2.3 SPECIAL OR INFREQUENT OPERATING MODES
- 2. 3. 1 Emergency See Primary Operating Mode 2.3.2 Start-Up System operation is independent of start-~p condition.
2.3.3 Shutdown System operation is independent of shutdown condition.
SYSTEM DESIGN OESCR IPTION Page _ _7_ of ___}1_
( \ PROJECT: Palisades Plant System No. 775
\ *.. Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: 1111 Conceptual 0 Preliminary OFinal o~~ March 3, 1980 3.-0 DESIGN CRITERIA 3.1 GOVERNMENTAL REGULATIONS AND GUIDES lOCFR Part 50, Appendix A, Criterion 13*, Instrumentation and Control lOCFR, Part 50, Appendix A, Criterion 56, Primary Containment Isolation Regulatory Guide (RG)
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RG 1.26 Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Rev. 3, 1976/02 RG 1.29 Seismic Design Classification, Rev. 3, 78/09 RG 1.53 Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems, 73/06 RG 1.89 Qualification of Class lE Equipment for Nuclear Power Plants, 74/11
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SYSTEM DESIGN DESCRIPTION Page _8_ of _ll_
PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0.
EDITION: mConceptual DPreliminary OFinal Date: March 3, 1980 RG 1.97 Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, Proposed Revision 2, 79/12 RG 1.100 Seismic Qualification of Electric Equipment for Nuclear Power Plants, Rev. 2, 77/08 RG 1.118 Periodic Testing of Electric Power and Protection Systems, Rev. 2, 78/06 3.2 INDUSTRY CODES, STANDARDS, AND GUIDES American Nuclear Society (ANS)
ANS 4.5, Draft 4, November 1979, Functional Requirements for Post Accident Monitoring Capability for the Control Room Operator of a Nuclear Power Generating Station
- American National Standard Institute (ANSI)
ANSI N 320-1979, Perfonnance Specifications for Reactor Emergency Radiological Monitoring Instrumentation ANSI N 45.2, Quality Assurance Program Requirements for Nuclear Facilities
SYSTEM DESIGN DESCRIPTION Page - ._9_ of __l!_
/ .\ PROJECT: Palisades Plant System No. 775
\.... Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: II Conceptual 0 Preliminary OFinal Date: March 3, 1980 American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section III, Division Institute of Electrical and Electronic Engineers (IEEE)
IEEE 279-1971, Protection Systems for Nuclear Power Generating Stations IEEE 323-1974, Qualifying Class lE Equipment for Nuclear Power Generating Stations
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IEEE 344-1975, Seismic Qualifications of Class lE E~uipment for Nuclear Power Generating Stations 3.3 CORPORATE STANDARDS AND GUIDES None 3.4 MANUFACTURER'S REQUIREMENTS Later
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SYSTEM DESIGN DESCRIPTION Page _lQ_ of~
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@. PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: Ill Conceptual 0 Preliminary OFinal Date: March 3, 1980 3.5 PLANT INTERFACE CRITERIA Piping interface with containment. atmosphere post-accident sample monitoring system.
Output interface with Tech Support Center.
3.6 CLIENT REQUIREMENTS Consumers Power Company, Palisades Plant - ltem.2.1.8.a, Improved Post-Accident Liquid and aaseous Sampling
SYSTEM DESIGN DESCRIPTION Page _ 11_ of _ 19_.
PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITiON: II Conceptual OPreliminary OFinal Date: March 3, 1980 4.0 DETAILED DESCRIPTION
- 4. l COMPONENTS 4.1.1 Description A fluid system diagram of the monitoring system is shown on Drawing No. PP-B-1-775-51-10-002. Each monitoring system is housed in a 72"H x 30"W x 30"D steel cubicle. The cubicle is constructed of welded steel plates (1/4" front 3/16" sides and i
\. top and 14 gauge rear door) inside a 2" x 2" square tube frame. Sample tubing is 3/8" x .065" wall,. stainless steel SA-213, GR316 eddy current and hydrostatic tested.
The monitoring system is designed to monitor containment gas for percentage by volume of hydrogen. The operating range is
-2 to 60 psig, 40 to 290°F, and relative humidity from 0 to 100.percent. After the sample passes through the entry valve, it enters the heated cell housing where the temperature is maintained at 300°F. The sample then passes through a cornbina-tion moisture separator and air vent, where 150 cc/min of the
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SYSTEM DESIGN DESCRIPTION Page___}£ of --1.2_
PROJECT: Pa I1sades PI ant System No. 775
\ ... Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: II Conceptual 0 Preliminary OFinal Date: March 3, 1980 stream is directed to the sample measuring cells, and the remainder of the gas and any moisture droplets is passed through a back pressure regulator to the system exhaust. The back pressure regulator provides a constant pressure differen-tial across the measuring cells and the sample flowmeter. The sample, reference, and bypass flows are cooled by natural convection to less than 150°F and returned to the containment by a diaphragm pump.
Analysis is accomplished by using the v1ell established principle
( of thennal conductivity me,asurements.of gases. This technique
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utilizes a self-heating filament fixed in the center of a temperature-controlled metal cavity. The filament temperature is detennined by the amount of heat conducted by the presence of yas from the filament of the cavity wa 11 s. Therrna l conduct iv-ity varies with gas species, thereby causiny the filament temperature to chanye as the yas in the cavity changes._,
Filament resistance changes with temperature; therefore, by using two filaments in separate cavities and connecting them in an electrical bridge, the difference in thermal conductivity of gases in'the separate cavities may be determined electrically.
SYSTEM DESIGN DESCRIPTION Page -11.. of -1.L PROJECT: Palisades Plant System No. 775 Post-Ac~ident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: 11:1 Conceptual
- 0 Preliminary OFinal Date: March 3, 1980 Electrical zero is set by first introducing the same gas to both cavities then adjusting the electrical bridge to balance, resulting in a zero output. As different gases are introduced to the two individual cavities, the bridge becomes unbalanced and the electrical output is amplified with increasing differences in thennal conductivity of the gases used.
Although this technique is non-specific, it is an extremely reliable technique when the gases or gas mixtures are known, and the variation in composite thennal conductivity can be
( accurately detennined.
The measurement of hydrogen in the presence of nitrogen, oxygen, andwater vapor is possible because the thennal conductiv-ity of the hydrogen is approximately seven times* higher than nitrogen, oxygen, or water vapor, v1hich have nearly the same thenna 1 conductivities (at the filament operat i ona 1 temperature of approximately 500°K). The measurement is accomplished by using a thennal conductivity measurement cell and a catalytic reactor. The sample first flows through the reference section of the cell then passes through the sample section of the measuring cell that includes the catalyst. The change in
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SYSTEM DESIGN DESCRIPTION Page _JL of __li_
PROJECT: Pa 11 sades p I ant System No. 775 Post-Accident Radiation Monitoring 1I SYSTEM:
EDITION:
Containment Hydrogen Monitoring D Conceptual 0 Preliminary OFinal Revision No.
Date:
d Ma re h 3, 1980
sample composition, due to the catalytic reaction, is therefore I
I indicated by the difference in thennal conductivity of the sample hydrogen content, as measured in the sample and reference I
II sides of the cell.
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!I If an excess amount of oxygen does not exist in the sample for recombining a11 the hydrogen, oxygen can be provided ahe~d of *
'~ . the hydrogen analyzer. The amount of oxygen added is determined by the highest range of the analyzer.
Span calibration is accomplished by introducin~ a known amount of oxygen and gas mixture of hydrogen in nitrogen to the cell; this gives a specific output for a readout calibration.
Zero calibration may be accomplished by shutting off the oxygen supply of the span gas mixture. This results in the gas flowing unchanged through both sides of the cell, the thenna 1 conductivity remains unchanged, the ce 11 is ba 1anced; and the electrical output is zero.
Calibration, zero and span controls, and lights are located on the analyzer cabinet. A master off, stand-by power on, and analysis mode selector switch is located on the analyzer
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cabinet and on the remote control room readout panel.
PROJECT: Palisades Plant
- SYSTEM DESIGN DESCRIPTION Page~of~
System No. 775 Post-Accident Radiation Monitoring SYSTEM: Conta1nment Hydrogen Monitoring Revision No. 0 EDITION: El Conceptual 0 Preliminary OFinal Date: March 3, 1980 In addition to the high hydrogen, high oxygen, and instrument failure alarms, a 4-20ma current output from each analyzer drives the control room readout and recording panel.
Alarms* are provided for high hydrogen concentration, cell
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failure, and loss of power. Theie alarms are available on the analyzer itself and as signals ~o the plant annunciator.
Additional alarms on the analyzer itself include low instrument temperature, low sample flow, low gas pressure, and co1111ilon failure.
- 4. 1. 2 Desiyn Data Later 4.2 INSTRUMENTS, CONTROLS, ALARMS, AND PROTECTIVE DEVICES See Sectio~ 4.1.1
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- e SYSTEM DESIGN DESCRIPTION Page _Ji ot--1L PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: II Conceptual 0 Preliminary OFinal Date: March 3, 1980 4.3 IMPACT ON STRUCTURES AND OTHER SYSTEMS
- a. Selection of system location.
- b. Electrical power from Class lE sources.
- c. 120 VAC, 10 amps, 60 Hz
- d. 480 VAC, 30, 2.5 amps, 60 Hz
- e. Hydrogen Span Gas
- f. Reagent Gas, Oxygen, 99.6 Purity
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- SYSTEM DESIGN DESCRIPTION Page _lL_ of _lL
/ PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: II Conceptual 0 Preliminary OFinal Date: March 3, 1980 5.0 SAFETY Later
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SYSTEM DESIGN DESCRIPTION Page ~ of --12..
PROJECT: Pa 11 saaes I-' 1ant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: l!i Conceptual 0 Preliminary OFinal Date: March 3, 1980 6.0 MAINTENANCE Later
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- SYSTEM DESIGN DESCRIPTION Page __l2_ of _J2_
PROJECT: Palisades Plant System No. 775 Post-Accident Radiation Monitoring SYSTEM: Containment Hydrogen Monitoring Revision No. 0 EDITION: 111 Conceptual 0 Preliminary OFinal Date: March 3, 1980
7.0 REFERENCES
Fluid System Diagram No. PP-B-1-775-51-10-002
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H2 ANALYlER CONTAINllENT AIR PRELIMINARY UNCHECKED ISSUED COtffAI NVENT AIR POST ACCIDENT SAMPLE UOHITMING MAR. 4 1980 FOR CONCEPT ONLY ..
TO THIS IS A NUCLEAR SAFETY RELATED DOCUMENT. NO DEVIATION SHALL BC 9llTIATEC A
OR PERFORM CD WITHOUT PRIOR DOCUM[IH ATION AND WRITTEN APPROVAL FllOM COMMONWEALTH ASSOCIATES INC SCALE*- *
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PALISAOtS t'LANT FSO - CONTAINMENT TITL&
H. C. GARG, P.E. HYDROGEN ANALYZER at 0111cn or CONSUMERS POWER COMPA P£V OAT£ DESCRIPTION BY APPROVED DATE .~~~*.~~:-:~:~:: .~~~~~!!:. ~.. JO.S N". 64-QJJQ-QQQ PRINTS SENT OUT
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