ML20137M385
| ML20137M385 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/16/1985 |
| From: | Kramer C GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML20137M353 | List: |
| References | |
| PROC-850716-01, NUDOCS 8509130220 | |
| Download: ML20137M385 (12) | |
Text
I s
O CERTAIN COMPONENTS CAI System Diagrams:
See Table VIII SAFETY RELATED FINAL SYSTEM DESIGN DESCRIPTION PLANT RADIATION MONITORING SYSTEM THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT UNITS 1 AND 2
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Date MY 7-M M Project Engineer
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Section Manager
[ fate Final Issue 11-30-81 Revised Issue 7-12-85 8509130220 O g [O Cilbert Associates. Inc.
PDR ADOCM O P.O. Box 1498 Reading, Pennsylvania System Designation D17
o TABLE OF CONTENTS Section Title Page
1.0 INTRODUCTION
1 1.1 SYSTEM FUNCTIONS 1
2 1.2 CRITERIA REQUIREMENTS 1.2.1 Codes and Standards 2
3 1.2.2 System Interfaces 1.2.3 Ambient Environmental Conditions 3
3 1.2.4 Design Basis 1.3
SUMMARY
DESCRIPTION OF SYSTEM 5
2.0 DETAILED DESCRIPTION OF SYSTEM 9
2.1 COMPONENTS 9
2.1.1 Plant Radiation Monitoring Panel 9
2.1.2 Annunciator 10 2.1.3 Power Supply 10 2.1.4 Plant Radiation Monitoring Subsystem Locations 11 2.1.5 Process System Radiation Monitoring 12 2.1.6 Liquid System Radiation Monitoring 18 2.1.7 Airborne Radiation Monitoring 21 2.1.8 Caseous Effluent Radiation Monitoring 36 2.1.9 Recorders 39 3.0 MODES OF OPERATION 40 3.1 STARTUP 40 3.2 NORMAL OPERATION 41 3.3 SHUTDOWN 41 3.4 EMERCENCY OPERATION 41 4.0 SAFETY PRECAUTIONS 41 5.0 MAINTENANCE 42 5.1 PREVENTIVE MAINTENANCE 42 5.2 SPECIAL DESIGN CONSIDERATIONS 42 TABLE I ATMOSPHERIC MONITORS 43 TABLE II D17 SYSTEM ANNUNCIATOR WINDOWS 45 TABLE III-A AIRBORNE RADIATION MONITOR SUBCROUP 47 TABLE III-B AIRBORNE RADIATION MONITOR SUBCROUP (ATMOSPHERIC) 48 TABLE IV CASEOUS EFFLUENT RADIATION MONITOR SUBCROUP 49 TABLE V PROCESS RADIATION MONITOR SUBCROUP 50 TABLE VI LIQUID RADIATION MONITOR SURCROUP
$1 TABLE VII IS0 KINETIC PROBES 52 TABLE VIII D17 SYSTEM DIAGRAM TABULATION 53 l
TABLE IX REFERENCES 54
--Gelbert Commonwealth ~.
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1
1.0 INTRODUCTION
This document presents a description of the Plant Radiation Monitoring System for Perry Nuclear Power Plant Units 1 and 2.
The Plant Radiation Monitoring System consists of in plant radiation monitor subsystems which provide detection,sieasurement, and indication of the level of radioactivity in selected p ant jrocess systems, water systems, and plant ventilation systems.
In addition, the atmosphere of certain areas of the plant is also monitored for radioactivity.
Area monitoring is presented in the D-21 System Description.
Post Accident Monitoring is presented in the D-19 System Description.
The Plant Radiation Monitoring System (D-17) includes the following subgroups of monitors:
Airborne Monitors and Atmospheric Monitors a.
b.
Caseous Effluent Monitors Process System Monitors c.
d.
Liquid System Monitors Location of radiation monitor subsystems are shown on CAI Plant Layout Diagrams E-013-003 to E-013-009.
System Diagrams are listed in Table VIII.
Process system radiation monitors and liquid system radiation monitors (except where noted) are supplied by the General Electric Company under the NSSS Contract.
Portions of these process radiation monitoring subgroups are safety related.
1.1 SYSTEM FUNCTIONS The functions of the Plant Radiation Monitoring System are:
a.
To detect, measure, indicate, and record the levels of radioactivity within*
1.
Plant vencilation systems 2.
The atmosphere of selected areas of the plant 3.
Selected plant water systems 4.
Liquid and gaseous effluent release paths 5.
Principal process streams b.
To alarm when predetermined radiation levels are exceeded, To provide a sampling and collection medium for analysis samples.
c.
d.
To maintain control over the release of radionuclides from the plant in gaseous and liquid effluents.
e.
To record the rate of release of radioactive material from the plant.
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To provide input signals to the reactor protection system and the containment and reactor vessel isolation control system, and for other control functions.
L 1.2 CRITERIA REQUIREMENTS The codes, standards and guides to which this system and its components comply, the interface relationship with other systems, the j,
system component ambient environmental requirements, and the system design bases are as follows:
1.2.1 Codes and Standards The system'is designed in accordance with the applicable requirements or guidelines set forth in the following codes, guides, and standards:
10 CFR 20, Standards for Protection Against Radiation.
a.
b.
10 CFR 50, " Appendix A, " General Design Criterta for Nuclear Power Plant":
Criterion 13 - Instrumentation and Control Criterion 60 - Control of Releases of Radioactive Materials to the Environment 1
1 Criterion 63 - Monitoring Fuel and Waste Storage Criterion 64 - Monitoring Radioactivity Releases.
10 CFR 50, Appendix B, " Quality Assurance Lriteria for Nuclear c.
Power Plants and Fuel Reprocessing Plants".
a j
l d.
U.S. NRC Regulatory Guide 1.21 (June 1974), " Measuring, e
l Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive. Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear Power Plant".
U.S. NRC Regulatory Guide 1.45 (May 1973), " Reactor Coolant l
e.
j Pressure Boundary Leakage Detection Systems".
l f.
U.S. NRC Regulatory Guide 1.75 (February 1974), " Physical Independence of Electric Systems".
g.
U.S. NRC Regulatory Cuide 8.8 (July 1974), "Information Relevant to Maintaining Occupational' Radiation Expusure as Low as i
Practicable".
(System supplements requirements of RC 8.8).
l h.
American National Standards Institute ( ANSI) Standardst j
f 1.
ANSI N13.1 - 1969, " Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities".
2.
ANSI.N13.2 - 1969, " Guide for Administration Practices in j
Radiation Monitoring", (Section 5.3.4.).
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Codes, standards and supplemental documents for the C. E.
supplied process monitors are listed in the Design Specification Data Sheets for the Design Specification 22A3767.
j.
NUREC-0737, " Clarification of TMI Action Plan Requirements."
November (1980), U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
1.2.2 System Interfaces The Process Radiation Monitoring System interfaces with the following plant systems:
a.
Selected ventilation systems b.
Selected process systems c.
Selected circulating water systems d.
The electrical system e.
The main annunciator system f.
The main computer system g.
The reactor prote-tion system h.
Post accident radtstion monitoring system (D-19) 1.2.3 Ambient Environmental Conditions The Plant Radiation Monitoring System equipment is designed to operate under the following environmental conditions:
Pressure
- 1.0 to 1.0 W.C. (inches of water)
Temperature 4.0 to 120 F Relative Humidity 20 to 90%
1.2.4 Desian Basis The design bases for the Plant Radiation Monitoring System are as follows:
To furnish quantitative information to the reactor operator and a.
to operations personnel on the level of radioactivity in principal plant liquid and gaseous process streams, liquid and gaseous effluent release paths, plant ventilation systems, and selected areas of the plant.
b.
To provide a system which can aid in minimizing personnel exposure to airborne radioactivity, and maintain occupational radiation exposure as low as practicable.
To aid in maintaining release of radioactive materials in liquid c.
and gaseous effluent paths to unrestricted areas as far below the limits specified in 10 CFR 20 as practicable.
d.
To control the release of radioactive materials in gaseous and liquid plant effluents in compliance with General Design Criterion 60.
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4 To provide monitoring of radioactivity releases, generated as a e.
result of normal or emergency operation of the plant, in effluent discharge paths as required by General Design Criterion 64.
f.
To provide an analysis sample medium from which the quantity of each principal radionuclide released to the environment can be determined in compliance with Regulatory Guide 1.21 (except for tritium samples).
To furnish information to substantiate radiation surveys as g.
required by 10 CFR 20, and provide supporting documentation of working environments.
h.
To initiate operation of the reactor protection system and the reactor vessel and containment isolation control system.
i.
To provide instrumentation to monitor plant ventilation systems, principal liquid or gaseous process systems, effluent discharge paths, or certain principal areas of the plant for level of radioactivity during and following an incident, j.
To augment and supplement the Leak Detection System in detecting leakage from the Reactor Coolant Pressure Boundary.
k.
To provide overall plant monitoring of airborne radioactivity and reasonable assurance that the ambient airborne radiation levels are below those requiring special monitoring equipment.
1.
To augment and supplement other monitoring systems, such as the Area Radiation Monitoring System, in the detection of incidents involving release of radioactive material.
To aid in the protection of the plant personnel from exposure to m.
airborne radioactive materials in excess of those allowed by 10 CFR 20.
To provide alarms for each channel (warning, high radiation, or n.
channel failure) and alarms for each subsystem (sampler bypassed or sample flow low).
To provide a hard copy record of radiation levels in all o.
monitored systems.
p.
To continuously monitor the plant ventilation systems for airborne radioactivity in order to permit an assessment to be made of the radiological hazards to be encountered within various regions of plant buildings, and to call attention to equipment malfunction or component failure resulting in the release of radioactivity.
q.
To provide instrumentation for use as the basis for initiating actions related to the plant radiation emergency plan.
.. Gilbert Commonwealth--
36 The monitor consists of a sampling system which draws air through a fixed particulate collection filter, a halogen collection cartridge, and a gaseous measuring channel where gross Beta activity can be detected.
-The equipment enclosures H51-P073 and H51-P074 are located 3
in the Intermediate Building, 620'-6" elevation.
Each readout module is located on panel H13-P804 in the-control room and recorded on panel H13-P600. No control functions are associated with this esdiation monitor.
Indication and alarms for each channel are provided in the control room and indication is provided on the equipment enclosure.
2.1.8 Caseous Effluent Radiation Monitoring The gaseous effluent radiation monitoring subgroup functions to:
Meet the requirements of 10 CFR 50, CDC 64, by monitoring a.
ef fluent discharge paths for -radioactivity that may be released from normal operations, abnormal occurrences, and postulated accidents, b.
Meet the requirements of 10 CFR 20, by monitoring and sampling gaseous effluents to ensure that stated release limits are not exceeded (dilution may be required to meet noble gas limits).
c.
Meet the requirements of Regulatory Guide 1.21, by representative sampling of gaseous ef fluents to provide a means for determining in tie laboratory the quantity of each principal radionuclide release to the environment.
d.
verify the effectiveness of radioactive control systems and
. provide warning to the operator of accidental releases.
e.
Provide information to plant personnel to ensure that radioactive material in gaseous effluents is minimized.
f.
Provide alarms and indication to the operator when radioactivity limits in the gaseous effluent have been exceeded.
g.
Continuously record the radioactivity level in gaseous effluent streams.
h.
Provide.information which may be used as a basis for initiating actions related to the plant radiation emergency plan.
i.
Meet the requirements of Reg. Cuide 1.97, Rev.2 and NUREC-0737 for monitoring gaseous effluents after an accident.
(This is in
-conjunction with the D19 instrumentation.)
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Provide a method to disseminate gaseous effluent release data by
{
interfacing with the ERIS and MIDAS computer systems.
k.
Provide data which can be used to determine release rates. This function is accomplished by the incorporation of engineering conversion factors into the MIDAS computer system, which in conjunction with exhaust air flow rate, provides for the a
calculation of release rates within the accuracy specified by Reg. Cuide 1.97, Rev. 2.
The plant gaseous effluent radiation monitors are discussed below; see D-806-001 and Table IV and Table IX.
a.
Off-Cas Vent Pipe Radiation Monitors (1D17K830 and 2D17K830)
This unit monitors a sample of the off gas vent pipe discharge downstream of the exhaust fans, Ref. D-912-622, for particulate, iodine, and gas activity and provides samples of the collected particulate and halogen for laboratory analysis. See D-806-008, D-856-008, D-806-022, and D-856-022.
A representative sample is continuously extracted from the unit off-gas vent pipe effluent path through an isokinetic probe in accordance with ANSI N13.1-1969 with the feature of regulating the sample flow in proportion to the discharge flow (autokinetic). This 1 inch sample line has been heat traced to preclude any condensation. A 1-CFM portion of this representative sample is taken by another probe and passed through the monitor to detect the particulate, iodine, and gas activity, which are indicated on ratemeters in the control room on panel H13-804 and recorded on panel H13-P600.
The autokinetic sampling panel H51-P146 and the monitor sampler enclosure H51-P169 are located in the Turbine Building at 620'-
6".
Interlocks associated with this monitor are used to initiate sampling and monitoring by D19 System (D19P400) upon a high radiation trip.
The autokinetic sample supply pump is powered from the non-IE diesel backed Stub Bus which ensures system availability.
The sampling unit motor-blower assembly is powered from non-IE diesel backed electrical bus FIC08 (F2C08) to ensure system availability.
b.
Plant Vent Radiation Monitors (ID17K780 and 2D17K780)
This unit monitors a sample of the plant vent discharge, Ref. D-912-613, for particulate, iodine, and gas activity and provides samples of the collected particulate and halogen for laboratory analysis.
See D-806-007,-D-856-007, D-806-023, and D-856-023.
A representative sample is continuously extracted from the unit plant vent effluent path through an-isokinetic probe in accordance with ANSI N13.1-1969 with the feature of regulating
~ Gilbert Commonwealth ~
38 the sample flow in proportion to the discharge flow
-(autokinetic). This 1 inch sample line has been heat traced to preclude any condensation. A 1-CFM portion of this representative sample is taken by another probe and passed through the monitor to detect the particulate, iodine, and gas activity which are indicated on ratemeters in the corl trol room on panel H13-P804 and recorded on panet H13-P600.
The autokinetic sampling panel H51-P149 and the monitor sampler enclosure H51-P086 are located in the Intermediate Building at 682'-6".
Interlocks associated with this monitor are used to initiate sampling and monitoring by the D19 System (D19P300) upon a high radiation trip.
The autokinetic sample supply pump is powered from the non-IE diesel backed Stub Bus thereby ensuring system availability. The sampling unit motor-blower assembly is powered from non-IE diesel backed electrical bus F1C08 to ensure system availability.
c.
Turbine Building-Heater Bay Exhaust Radiation Monitors (ID17K850 and 2D17K850)
This unit monitors a sample of the turbine building and heater bay stack discharge, Ref. D-912-621, for particulate, iodine, and gas activity and provides samples of the collected particulate and halogen for laboratory analysis.- See D-806-022, D-806-023, D-856-022, and D-856-023.
A representative sample is continuously extracted from the linit
' Turbine Building / Heater Bay stack effluent path through an isokinetic probe in accordance with ANSI N13.1-1969 with the feature of regulating the sample flow in proportion to the discharge flow (autokinetic). This 1 inch sample line has been heat traced to preclude any condensation. A 1-CFM portion of this representative sample is taken by another probe and passed through the monitor to detect the particulate, iodine and gas activity which are indicated on ratemeters in the control room on panel H13-P804 and recorded on panel H13-P600.
The autokinetic sampling panel _H51-P757 and the monitor sampler enclosure H51-P756 are located in the Heater Bay at 667',-6".
Interlocks associated with this monitor are used f.o initiate sampling and monitoring by the D19 System (D19P500 (- D19K580) upon a high radiation trip.
The autokinetic sample supply pump is powered from the non-IE diesel backed Stub Bus to assure system availability. The sampling unit motor-blower assembly is powered from non-IE diesel backedelectricalbusF1808toassuresystemavailabiy.ty.
d.
Steam Packing Exhaust Radiation Monitoring System (ID17K840 and-2D17K840) t i,
5 X
... Gilbert Commonwealtha.
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Ut 3.2 NORMAL OPERATION The system is normally energized. Observation of the readout module meter, the, recorder, or the local meter on the equipment enclosure indication panel provides indication of the instrument channel radiation level. Alarm lights at the equipment enclosure provide
=,
,q local information as to equipment malfunction, operating status, or
. system alarm conditions. Movable atmospheric radiation monitors
\\\\ ';
provide local audible alarms and indication only to warn personnel of
} 3 high airborne radiation or equipment failure.. Alarm lamps and
^
annunciator points alert the control room operator of alarm s
i c,onditions.
3.3 SHUTDOWN No unusual s utdown procedure is required for the equipment.
7 Detailed instructions are provided in the Vendor's instruction manual.
Channels with interlock outputs will normally be in trip mode when i
shutdown fENERGENCYOPERATION 3.4 tIn the case of a plant emergency, as may result from a LOCA or loss of 4
j off-site power, the main steam line radiation monitoring system and the containment ventilation exhaust radiation monitoring system are 9
not requiret' to operate.
In the case of a LOCA, their protection s
function is accomplished by the LOCA signal.
In the case of a i
complete loss.of power to the RPS buses, the channels would trip the failsafe mode and accomplish their protection function.
'The remaining subsystems of the plant radiation system are not required to operate in the case of a LOCA or loss of off-site poweri i
however,\\this system receives power from the nonessential load diesel-backed bus (see Section 2.1.3) to ensure system availability to the control room operator. The availability of this system increases the quantity of information needed for the operator to interpret the nature and extent of an incident involving the release of radioactivity.
i In the case of a LOCA, the plant radiation monitoring system is available to the reactor operator upon re-energizing the stub-bus.
i
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4.0-SAFETY PRECAUTIONS The equipment in this system has power supplies which produce high voltages.' Trocedures to be followed for operation and maintenance of l_ j the system are described in the system instruction manual.
Standard health physics procedures must be followed in handling test and calibration radioactive sources and radioactive check sources.
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TABLE IV GASEOUS EFFLUENT RADIATION MONITOR
~5UBGROUD UNITS 1 AND 2 Subsystem Radiation Monitor,
7aaNo
$ubsystem Sarn ole Point Imtrument Channels f unction of Sutnystem 1017K830 Off Gas Vent Pipe Radiation Off-Gas Vent Pipe G5P Local.and Control Room H$P indication and alarms G017K 830)
Monitor PSP interlock with D19 System 1D17K780 Plant Vent Radiation Mon tar Plant Vent Autokinetic GSP Local and Centrol Room HSP alarms anc ind catton
$ampter PSP interlock with D19 5ystem i
1D17K850 Turbine Building Heater Bay HB TS stack Autokinetic G59 Local and Control Room (2D17K850)
E nhaust yadiation Monitor Samoler HSP alarms and ino cation PSP interloo Aith D19 5ystem 1D17k B40 Steam Packing E shaust Rad 4ation Steam pack ing enhJuster GS F
- iniine Control Room alarms and (2D17K 840)
Monitor effi ect hne rdgation
/
NOTE.
Tag Numbers prbed by 1D17 are components aw;oa'ed with Unit No 1 Tag Numbers prefined by 2D17 are components anoodted with Unit No 2 Gas tnambe sontillator GSP r
=
Halogen cartriage scintillator HSP
=
Partavlate filter sontolator PSP
=
a w
--Gilbert Commonwealth---
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52 TABLE Vli 150K INE Tic paogy UNIVS 1 AND 2 (1)
(1)
Monitor isohnetic Duct Design Flow N
Probe No
( nches)
EM Ventilation 5ctem 3
M14 Containment Vessel and Drywell Purge 1D17k660 1017N661A 48 m 48 5 000 1D17N661B 48 x 48 30 000 MIS Reactor 31dg Annulus E shaust Gas 1017F 690A ID17N601A 14 s 16 400
Treatme nt ID17k 6900 1017N6918 14 = 16 400*
M36 Off Gas Bidg Ventilation 5ystem ID17K760 1D17N761 10 : 46 15 000 M3B Aus.bery Bldg Ventilation System 1D17K700 1017N701 30 = 90 10 500 CO9% ION TO BOTH UNITS M25 Control Room HV AC and Emergency D17k 770 D17N771 38e12 11 540 Reorculation system M31 Rad.vatte Bldg Ventilat:on Syuem D17x720 D17K721A 32 x 90 30.000 D17x7219 32 a 90 30.000 M33 intermediate Biog ventitation system D17k730 D17K731 46 = 46 27 400 M40 FuelHandling Area Ventilation System D17x710 017k711 40 x 70 30 000 WOTE S 1
Unit I has 1 preceding the number. e e,1017k--
Unit 2 had 2 preceding the number 2
With no recycle to the annutus space 2000 CFM is powhle probe nozzle designed for high flow
- Gilbert Commonwealth--