ML20054M162
| ML20054M162 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 07/06/1982 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 SLNRC-82-031, SLNRC-82-31, NUDOCS 8207120039 | |
| Download: ML20054M162 (78) | |
Text
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SNUPPS Standardized Nuclear Unit '
Power Pfant System 5 Choke Cherry Hoad Nicholis A. Petrick Roce ville, Maryland 2G850 Executive Director '
(301)869 4010 July 6,1982 SLNRC 82- 031 FILE:
0541 SUBJ:
Regulatory Guide 1.97 Mr. Harold Denton,. Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Coninission Washirigton, D. C.
20555 Docket Nos:'S'TN 50-482 and STN 50-483
Dear Mr. Denton:
Provided herewith is 'the SNUPPS response to Revision 2 of Regulatory '
Guide 1.97,' " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions during and Following an Accident".
Post-accident monitoring is license condition #11 in the Callaway and Wolf Creek SERs. The response is in the form of an FSAR addition and will be included in the next revision to the SNUPPS FSAR.
Very-truly yours,
( Nek\\C j
' Nicholas A. Petrick
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SNUPPS h
APPENDIX 7A 7A.1 INTRODUCTION This appendix provides an evaluation of the instrumentation to assess plant and environs conditions following an accident.
The plant instrumentation and features provided in the!SNUPPS units have resulted from detailed design evaluations and reviews.
Design features that enable the plant to be taken to cold shutdown while utilizing only safety-grade equipment are described in Appendix 5.4A, Cold shutdown.
Chapter 18.0 provides a comparison of the SNUPPS design to the requirements of NUREG-0737.
Since most of the instrumentation in the SNUPPS units was purchased and installed prior to the issuance of Regulatory Guide 1.97, strict compliance to the many prescriptive recom-mendations is not provided in all cases.
However, the SNUPPS instrumentation and control room design is adequate to allow the operators to evaluate and mitigate the consequences of postulated accidents.
This appendix provides a detailed comparison of the SNUPPS design to the recommendations contained in the regulatory guide.
7A.2 ORGANIZATION The text of this appendix provides a summary description of the bases for the SNUPPS instrumentation design as they relate to the recommendations of the regulatory guide.
The tables provide the data necessary to perform a detailed comparison of the SNUPPS design with the recommendations of the regulatory guide.
Table 7A-1 is a cross-reference between Table 2 of the regu-l latory guide and the information presented in this appendix.
Table 7A-1 lists the vartables in the same sequence in which they appear in the regulatory guide table, assigns variable identification numbers, and identifies the data sheet upon l
which the detailed comparison with the SNUPPS design has been I
provided.
l Table 7A-2 provides a summary of the SNUPPS design to the L-recommendations of the regulatory guide.
This table also L
serves as an index to the data sheets in Table 7A-3.
l Table 7A-3 consists of individual data sheets.
One data sheet is provided for each variable or group of related variables identified in Table 2 of the regulatory guide.
The data sheet contains the recommended range, category, and purpose for the variable and includes the multiple listing requirements.
A discussion is provided of the SNUPPS plant design bases for 7A-1 t
SNUPPS s
qualification, etc., and other pertinent data which
- ranges, support the adequacy of the current design or describe design Table 7A-3 also modifications which are being implemented.
provides an indication of the computer into which the vpriable is inputted and thereby made available to the Emergency Response Facility Information System (ERFIS) computer network.
r SNUPPS DESIGN BASIS COMPARISON TO REGULATORY GUIDk 1 7A.3 The SNUPPS design bases are stated throughout the FSAR.
The discussions provided below summarize the SNUPPS design bases as they pertain to the salient recommendations of the regulatory guide.
Appropriate references to other FSAR sections are provided in Table 7A-3 for more detailed information.
The discussions below are intended to aid the review of the SNUPPS design bases for compliance with the intent of the regulatory guide recommendations.
7A.3.1 TYPE A VARIABLES Variables classified as Type A for the SNUPPS design are identified in Table 7A-2.
The reason for the classification is provided on the corresponding data sheet in Table 7A-3.
The following criteria are the bases for identification of Type A variables for the SNUPPS plants.
The terminology used in the discussion is consistent with that of the generic Emergency Response Guidelines (ERGS) for Westinghouse plants, which were submitted to the NRC by Westinghouse Owners Group letter OG-64, dated November 30, 1981.
Variables used for event diagnosis are classified as a.
Type A because these variables direct the operator to the appropriate Optimal Recovery Guidelines (formerly termed Emergency Operating Instructions) or to monitor-ing of critical Safety Functions.
b.
Variables used by the operator to perform manual actions prescribed by the Optimal Recovery Guidelines, which are associated with Condition IV events (LOCA, MSLB, and SGTR), are classified as Type A.
Condition I, II and III events are not considered in identifying Type A variables (e.g., Spurious Safety Injection).
Variables which identify the need for operator action c.
to correct single failures are not classified as Type A.
These actions are often identified as " Notes" or " Contingency Actions" in the ERGS.
d.
Variables associated with operator actions required for events not currently in the design bases of the plant are not identified as Type A variables.
=
SNUPPS s
7A.3.2 REDUNDANCY AND DIVERSITY FOR CATEGORY 1 VARIABLES The following discussion summarizes salient points of the SNUPPS design with respect to the regulatory recommendations:
a.
Adequate redundancy is considered to exist when adequate information is available to the operetor to make appropriate decisions, ass.uming a single failure.
This is done on a system, loop, or component basis, as appropriate.
For the steam generator heat sink function and pressurizer, it was done on a component basis.
For the reactor and reactor coolant loops, it was done on a system basis due to the abundance of diverse or associated variables which are available to indicate the nature of the event and identify its cause.
b.
Diverse variables are considered to be those which vary directly with or have a direct relation with the primary variable.
Associated variables are those which, when considered with the primary and/or diverse variables, aid in the identification and evaluation events and the status of the plant, c.
The need for a third reading or a diverse variable is based on the control room operators' need for the identification of the proper recovery from an event.
Diversity is not provided solely for TSC/ EOF use, accident reconstruction, or range not associated with DBEs.
d.
Since the need for a diverse variable arises upon the single failure of the primary instrumentation and that failure must result in ambiguity (e.g.,
the instrument fails in midscale, not offscale high or low), diverse variables may be rerformance or commercial grade.
Many diverse variables on SNUPPS are qualified as Class IE for reasons other than their diversity function.
t e.
Items identified as diverse variables are not con-sidered to be part of the post-accident monitoring data base and are not included in the Emergency Response Facility Data Base solely for that purpose, l
Many diverse variables are part of the post-accident monitoring data base because of their primary func-tion.
Since it is highly unlikely that a variable l
will be required for a diversity function, the EOF /TSC may contact the control room should the need arise.
i 7A-3
SNUPPS 5
7A.3.3 RECORDERS Dedicated recorders are required only where trend information is immediately required for operator use.
The current value (indicated) of the PAMs variables is normally used by the operator for decision-making purposes.
Where Class IE;indi-cators are provided, recorders may be performance grads.
7A.3.4 INSTRUMENT RANGES Instrument ranges have been determined, considering the func-tion (s) of the sensed parameters.
The installed instrumen-tation may meet the ranges recommended in the regulatory guide, meet the intent of the recommended range, or have a range appropriate for the design function.
Instrumentation that has an appropriate range is identified on Table 7A-2.
The ranges are justified on the individual data sheets of Table 7A-3.
7A.3.5 UNNECESSSARY VARIABLES Several variables listed in the regulatory guide are not nec-essary for post-accident monitoring for the SNUPPS units.
Table 7A-2 identifies which variables are considered unneces-sary from a post-accident monitoring standpoint, and the individual data sheets provide a discussion justifying the determination.
7A.3.6 QUALIFICATION FOR CATEGORY l PARAMETERS With one exception, Tables 7A-2 and 7A-3 show that instrumenta-tion for all variables designated as Category 1 by the NRC and those designated as Type A herein are qualified as Class IE from the sensor to the indicator.
The only exception is the neutron detectors which are suitably qualified for their function.
Refer to data sheet 1.1 for further discussion of these items.
Qualification of these devices will be justified in the NUREG-0588 submittals which will be provided in the last quarter of 1982.
All Class IE equipment is qualified to IEEE-323-1974 and IEEE-344-1975.
i 7A.3.7 QUALIFICATION FOR CATEGORY 2 PARAMETERS The SNUPPS design utilizes Class IE and non-Class IE sensors, transmitters, indicators, and power sources.
There is no qualification category between these two categories, as implied l
by the Category 2 terminology of the regulatory guide.
l Table 7A-2 shows that many of the Category 2 items are in fact fully qualified to Class IE environmental and seismic require-(
ments.
These items exceed the regulatory recommendations.
I l
f 7A-4
SNUPPS s
The non-Class IE instruments are termed performance grade.
These items are purchased to perform in their anticipated service environments for the plant conditions in which they must function.
The regulatory guide implies that they must function in the accident environment for the area in which they are located without consideration of the design functio.
If n
an instrument has to function following an accident, itris fully qualified to Class IE requirements.
If the instrumen't is not required following an accident, it is termed non-safety-related and purchased to performance grade requirements.
The equipment service conditions are provided in the purchase specification and include radiation levels and integrated doses, temperature, relative humidity, and other special considerations.
The current qualification levels for each item reflect its importance to safety.
Table 7A-3 addresses the function of performance grade items in Category 2.
Non-Class IE equipment is supplied from Separation Groups 5 and 6, which are highly reliable (refer to Chapter 8.0).
The non-Class IE 125 V dc buses are backed by the emergency diesel generator.
For the purpose of compliance to the regulatory requirements for seismic qualification for items identified as Category 2, the sensors / transmitters continued operation is not assumed to be required, since the indicators need not be qualified.
Assurance of pressure boundary integrity during and after seismic events is ensured for safety-related systems.
No seismic requirements are placed on items in non-safety-related systems.
7A.3.8 QUALIFICATION FOR CATEGORY 3 ITEMS The Category 3 qualification guidelines of the regulatory guide imply a possible need to ensure that the instrument sensor and transmitter are qualified for an accident environment.
Table 7A-2 identifies those Category 3 instruments located inside the containment, and the appropriate data sheet of Table 7A-3 justifies the lack of post-accident qualification.
l l
l 7A-5
1 SNUPPS TABLE 7A-1 REGULATORY GUIDE 1.97 VARIABLE LIST r
DATA VARIABLE
SUMMARY
IDENT. NO.
VARIABLE SHEET NO.
B.1 Reactivity Control B.1.1 Neutron Flux 1.1 B.1.2 Control Rod Position 1.2 B.1.3 RCS Soluble Boron Concentration 13.1 B.1.4 RCS Cold Leg Water Temperature 2.1 B.2 Core Cooling B.2.1 RCS Hot Leg Water Temperature 2.2 B.2.2 RCS Cold Leg Water Temperature 2.1 B.2.3 RCS Pressure 2.3 B.2.4 Core Exit Temperature 1.3 B.2.5 Coolant Level in Reactor 1.4 B.2.6 Degrees of Subcooling 1.5 B.3 Maintaining Reactor Coolant System Integrity B.3.1 RCS Pressure 2.3 B.3.2 Containment Sump Water Level 6.2 B.3.3 Containment Pressure 6.1 B.4 Maintaining Containment Integrity B.4.1 Containment Isolation Valve Position 6.3 (excluding check valves) l
1 SNUPPS TABLE 7A-1 (Sheet 2 )
DATA VARIABLE f
SUMMARY
IDENT. NO.
VARIABLE r
SHEET NO.
B.4.2 Containment Pressure 6.1 C.1 Fuel Cladding C.1.1 Core Exit Temperature 1.3 C.1.2 Radioactivity Concentration or Radiation 13.3 Level in Circulating Primary Coolant C.1.3 Analysis of Primary Coolant 13.1 (gamma spectrum)
C.2 Reactor Coolant Pressure Boundary C.2.1 RCS Pressure 2.3 C.2.2 Containment Pressure 6.1 C.2.3 Containment Sump Water Level 6.2 C.2.4 Containment Area Radiation 11.1 C.2.5 Effluent Radioactivity - Noble Gas 12.2 I
Effluent from Condenser Air Removal System Exhaust C.3 Containment l
C.3.1 RCS Pressure 2.3 l
l C.3.2 Containment Hydrogen Concentration 6.4 i
C.3.3 Containment Pressure 6.1 C.3.4 Containment Effluent Radioactivity -
12.1 Noble Gases from Identified Release Points C.3.5 Radiation Exposure Rate (inside build-11.2 i
ing or areas, e.g.,
auxiliary building, reactor shield building annulus, and fuel handling building, which are in direct contact with primary containment where penetrations and hatches are located) 4 l
l
SNUPPS TABLE 7A-1 (Sheet 3 )
DATA VARIABLE
- ~
SUMMARY
IDENT. NO.
VARIABLE r
SHEET NO.
C.3.6 Effluent Radioactivity - Noble Gases 12.1 (from buildings as indicated above)
D.1 Residual Heat Removal (RHR) or Decay Heat Removal System D.1.1 RHR System Flow 3.1 D.1.2 RHR Heat Exchanger Outlet Temperature 3.1 D.2 Safety Injection Systems D.2.1 Accumulator Tank Level and Pressure 3.2 D.2.2 Accumulator Isolation Valve Position 3.2 D.2.3 Boric Acid Charging Flow 3.3 D.2.4 Flow in HPI System 3.3 D.2.5 Flow in LPI System 3.1 D.2.6 Refueling Water Storage Tank ~ Level 3.4 D.3 Primary Coolant System D.3.1 Reactor Coolant Pump Status 2.4 D.3.2 Primary System Safety Relief Valve 2.5 Positions (including PORV and code valves) or Flow Through or Pressure in Relief Valve Lines D.3.3 Pressurizer Level 2.6 D.3.4 Pressurizer Heater Status 2.7 D.3.5 Quench Tank Level 2.8 D.3.6 Quench Tank Temperature 2.8 D.3.7 Quench Tank Pressure 2.8
t SNUPPS TABLE 7A-1 (Sheet 4 )
DATA VARIABLE r
SUMMARY
IDENT. NO.
VARIABLE SHEET NO.
D.4 Secondary System (Steam Generator)
D.4.1 Steam Generator Level 4.1 D.4.2 Steam Generator Pressure 4.2 D.4.3 Safety / Relief Valve Positions or Main 4.3 Steam Flow D.4.4 Main Feedwater Flow 4.4 D.5 Auxiliary Feedwater or Emergency Feedwater System D.5.1 Auxiliary or Emergency Feedwater Flow 5.1 D.5.2 Condensate Storage Tank Water Level 5.2 D.6 Containment Cooling Systems D.6.1 Containment Spray Flow 10.1 D.6.2 Heat Removal by the Containment Fan Heat 8.1 l
Removal System D.6.3 Containment Atmosphere Temperature 6.5 l
D.6.4 Containment Sump Water Temperature 6.6 D.7 Chemical and Volume Control System D.7.1 Makeup Flow-In 7.1 l
D.7.2 Letdown Flow-Out 7.1 l
D.7.3 Volume Control Tank Level 7.1 D.8 Cooling Water System I
D.8.1 Component Cooling Water Temperature to 9.1 ESF System D.8.2 Component Cooling Water Flow to 9.1 ESF System l
l l
l
i SNUPPS TABLE 7A-1 (Sheet 5)
DATA VARIABLE
SUMMARY
IDENT. NO.
VARIABLE SHEET NO.
D.9 Radwaste System D.9.1 High-Level Radioactive Liquid Tank Level 14.1 D.9.2 Radioactive Gas Holdup Tank Pressure 14.2 D.10 Ventilation Systems D.10.1 Emergency Ventilation Damper Position 15.1 D.11 Power Supplies D.11.1 Status of Standby Power and Other Energy 16.1 Sources Important to Safety (hydraulic, pneumatic)
E.1 Containment Radiation E.1.1 Containment Area Radiation - High Range 11.1 E.2 Area Radiation E.2.1 Radiation Exposure Rate (inside build-11.2 ings or areas where access is required to service equipment important to safety)
E.3 Airborne Radioactive Materials Released from Plant E.3.1 Noble Gases and Vent Flow Rate E.3.1.1 o
Containment or Purge Effluent 12.1 E.3.1.2 o
Reactor Shield Building Annulus NA (if in design)
E.3.1.3 o
Auxiliary Building (including any 12.1 building containing primary system
- gases, e.g.,
waste gas decay tank)
E.3.1.4 o
Condenser Air Removal System Exhaust 12.2
SNUPPS TABLE 7A-1 (Sheet 6)
DATA VARIABLE
SUMMARY
IDENT. NO.
VARIABLE I
SHEET NO.
E.3.1.5 o
Common Plant Vent or Multipurpose 12.1 Vent Discharging Any of Above Releases (if containment purge is included)
E.3.1.6 o
Vent From Steam Generator Safety 12.3 Relief Valves or Atmospheric Dump Valves E.3.1.7 o
All Other Identified Release Points 12.4 E.3.2 Particulates and Halogens E.3.2.1 o
All Identified Plant Release Points 12.5 (except steam vent design flow generator safety relief valves or atmospheric steam dump valves and condenser air removal system exhaust).
Sampling with Onsite Analysis capability E.4 Environs Radiation and Radioactivity E.4.1 Radiation Exposure Meters (continuous 17.1 indication at fixed locations)
E.4.2 Airborne Radiohalogens and Particulates 17.2 (portable sampling with onsite analysis capability)
E.4.3 Plant and Environs Radiation (portable 17.3 instrumentation)
E.4.4 Plant and Environs Radioactivity 17.4 (portable instrumentation)
E.5 Meteorology E.5.1 Wind Direction 17.5 E.5.2 Wind Speed 17.5 E.5.3 Estimation of Atmospheric Stability 17.5
SNUPPS TABLE 7A-1 (Sheet 7)
DATA VARIABLE f
SUMMARY
IDENT. NO.
VARIABLE r
SHEET NO.
E.6 Accident Sampling Capability (Analysis capability on Site)
E.6.1 Primary Coolant 13.1 E.6.1.1 o
Gross Activity 13.1 E.6.1.2 o
Gamma Spectrum 13.1 E.6.1.3 o
Boron Content 13.1 E.6.1.4 o
Chloride Content 13.1 E.6.1.5 o
Dissolved Hydrogen or Total Gas 13.1 E.6.1.6 o
Dissolved Oxygen 13.1 E.6.1.7 o
pH 13.1 E.6.2 Sump 13.2 E.6.2.1 o
Gross Activity 13.2 i
i E.6.2.2 o
Gamma Spectrum 13.2 E.6.2.3 o
Boron Content 13.2 E.6.2.4 o
Chloride Content 13.2 E.6.2.5 o
pH 13.2 E.6.3 Containment Air E.6.3.1 o
Hydrogen Content 6.4 E.6.3.2 o
Oxygen Content NA E.6.3.3 o
Gamma Spectrum 13.1 i
l l
l I
l l
l SNUPPS l
l TABLE 7A-2 l
l
SUMMARY
COMPARISON TO f
REGULATORY GUIDE 1.97 l
SENSOR CHANNEL LOCATION QUALIFICATION RANGE COMPARISON l
i' 88 f
NRC I
QUAL.
SNUPPS Complies Appro-l DATA CATE-TYPE A with Meets praate Inside Outside Class Perf.
SHEET GORY VARIABLE Req.
Intent Range Ctat Ctat IE Grade VARIABLE f
NUMBER DESCRIPTION CORE AND REACTOR VESSEL VARIABLES X
X X
X X
1 X
1.1 Neutron Flux - Intermediate Range X
X 3
X 1.2 Control Rod Position X
X 1
X 1.3 Core Exit Temperature X
X 1
X 1.4 Reactor Vessel Level X
2 1.5 Subcooling Monitor RCS AND RELATED VARIABLES X
X X
1 Yes X
X X
2.1 RCS Tcold 1
Yes X
X 2.2 RCS T 2.3 RCS Ph8ksure 1
Yes X
X X
3 X
X 2.4 RCP Status (motor current)
X X
X 2
2.5 Primary System Valve Position X
X 1
Yes X
X 2.6 Pressurizer Level X
X 2
X 2.7 Pressurizer Heater Status X
X 3
2.8 PRT Level X
X X
3 X
2.8 PRT Temperature X
3 2.8 PRT Pressure ECCS VARIABLES X
X 2
X X
X 3.1 RHR/LPI Flow Rate X
X 2
RHR/ Heat Exchanger T X
X 3.1 X
Accumulator Tank Lev 8Y 2
X X
3.2 2
X X
3.2 Accumulator Tank Pressure X
2 X
X 3.2 Accumulator Tank Valve Position X
2 X
X 3.3 Centrifugal Charging Pump Flow X
2 X
X 3.3 Safety Injection Pump Flow X
2 X
X 3.3 RCP Seal Injection 1
Yes X
3.4 RWST Level l
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SNUPPS TABLE 7A-2 (Sheet 2) t SENSOR CHANNEL RANCE COMPARISON LOCATION QUALIFICATION NRC DATA QUAL.
SNUPPS Complies Appro-SilEET
68 VARIABLE CATE-TYPE A with Meets praate Inside Outside Class Perf.
NUMBER DESCRIPTION GORY VARIABLE Req.
Intent Range Ctat Ctat IE Grade SECONDARY SIDE VARIABLES 4.1 Steam Generator Level - Wide Range 1
X X
X 4.1 Steam Generator Level - Narrow Range 1
Yes NA X
X 4.2 Steam Line Pressure 1
Yes X
X X
4.3 Secondary Side PORV Position 2
X X
X 4.3 Secondary Side Safety Position 2
NA NA NA 4.4 Main Feedwater Flow Rate 3
X X
X AUXILIARY FEEDWATER SYSTEM VARIABLES 5.1 Auxiliary Feedwater Flow Rate 2
X X
X 5.2 Condensate Storage Tank Level 1
X X
X (Pressure)
CONTAINMENT VARIABLES 6.1 Containment Pressure - Design 1
Yes X
X X
Pressure Range i
6.1 Containment Pressure - Extended 1
X X
X l
Range 6.2 Containment Normal Sump Level 1
Yes X
X X
6.2 Containment RIIR Sump Level 1
X X
X 6.3 Containment Isolation Valve Position 1
X X
X X
6.4 Containment Hydrogen Concentration 1
X X
X 6.5 Containment Atmosphere Temperature 2
X X
X 6.6 Containment Sump Temperature 2
NA*
CIIARGING AND LETDOWN SYSTEM VARIABLES 7.1 Normal Charging Flow 2
X X
X 7.1 tiormal Letdown Flow 2
X X
X i
7.1 Volume Control Tank Level 2
X X
X
(
7.1 Letdown Flow - Safety Related 2
X X
X l
[
,
- Unnecessary Variable - Refer to Table 7A-3 4
SNUPPS TABLE 7A-2 (Sheet 3 )
SENSOR CHANNEL RANGE COMPARISON LOCATION QUALIFICATION NRC DATA QUAL.
SNUPPS Complies Appro-SHEET 9
'M 88 VARIABLE CATE-TYPE A with Meets priate Inside outside Class Perf.
NUMBER DESCRIPTION GORY VARIABLE Req.
Intent Range Ctat Ctat IE Grade CONTAINMENT COOLING SYSTEM VARIABLES 8.1 Containment Cooler Heat Removal 2
NA*
COMPONENT COOLING WATER SYSTEM VARIABLES 9.1 Component Cooling Water 2
X X
X Temperature to ESF 9.1 Component Cooling Water 2
X X
X Flow Rate to ESF CONTAINMENT SPRAY SYSTEM VARIABLES 10.1 Containment Spray Flow Rate 2
X X
X AREA RADIATION MONITORING 1 11.1 Containment Area Radiation 1
Yes X
X X
11.2 Area Radiation Monitor -
2 X
X X
Containment Penetration Area EFFLUENT MONITORS 12.1 Unit Vent - Noble Gas 2
X X
X 12.2 Condensate Air Removal -
3 X
X X
Radiation Monitor 12.3 Secondary Side Radiation Release 2
X X
X 1
12.4 AFW Turbine Radiation Release 2
X X
X 12.5 Vent Particulates and Halogens 3
X X
X
- Unnecessary Variable - Refer to Table 7A-3 e
4 6
4 SNUPPS TABLE 7A-2 (Sheet 4) l SENSOR CHANNEL RANGE COMPARISON LOCATION QUALIFICATION NRC DATA QUAL.
SNUPPS Complies Appro-1
,i 6e SHEET VARIABLE CATE-TYPE A with Meets priate Inside' Outside Class Perf.
NUMBER DESCRIPTION GORY VARIABLE Req.
Intent Range Ctat Ctat IE Grade SAMPLING SYSTEMS 13.1 Inline Sampling System 3
X X
X 13.2 Containment Recirculation 3
X X
X Sump Sample 13.2 ECCS Room Sump Sample 3
NA*
13.2 Auxiliary Building Sump Sample 3
NA*
13.3 Radiation Level in RCS 1
NA*
RADWASTE SYSTEM VARIABLES 14.1 Recycle Holdup Tank Level 3
NA*
14.2 Waste Gas Decay Tank Pressure 3
NA*
DAMPER POSITION 15.1 Emergency Ventilation Damper 2
X X
X X
Position POWER SUPPLY STATUS INDICATION 16.1 Electric Power Supply Status 2
X X
X 16.2 Gas Accumulator Tank Pressure 2
X X
X ENVIRONMENTAL MONITORING 17.1 Fixed Radiation Exposure Meters 3
17.2 Port Emergency Monitor -
3 Particulates and Halogen 17.3 Particulates Monitor - Plant 3
and Environs 17.4 Plant and Environs - Gamma Spectra 3
17.5 Meteorological Parameters 3
X t
4
- Unnecessary variable - Refer to Table 7A-3 b
~
SNUPPS TABLE 7A-3, DATA SHEET 1.1 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE
~
B.l.1 Neutron Flux 10 6% to 100% full power 1
Function detection, accomplishment of
.,, g, mitigation II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.l.1 Intermediate Range 10~8% to NE35 Y
003 N
NSSS 200% full power NE36 Y
003 N
~
NSSS NA Source Range 10 '% to NE31 Y
003 N
NSSS (diversity for Later NE32 Y
003 N
intermediate range)
III.
REMARKS 1.
The excore neutron detectors are described in Section 7.2 and are powered by a Class IE power source and provide inputs to the reactor protection system. The indicators are of high quality and receive power from a Class IE source through a qualified isolation device located in the RPS racks in the control room.
Since the indicators are powered from the Class IE source and are located in a benign environment of the control room on a seismically designed control board, they are considered adequately designed to meet the intent of the regulatory recommendations.
2.
Since the source and intermediate range detectors do not have to operate following a design basis event, they are not qualified to LOCA or MSLB environmental transients. The sensors are qualified per equipment qualification data packages ESE-8 and-9 of WCAP 8587.
As noted, therein, the sensors are qualified to very high gamma and neutron integrated doses which result from normal operational environments. The sensors are also qualified to Seismic Category I requirements.
3.
The diversity requirements are provided in the range overlap regions of the source range detectors and also by the boron concentration data from inline post-accident sampling system described on data sheet 13.1 of this table. The control rod positions also provide diverse information which helps ensure that the reactor is shut down.
As stated in Section 7A.3.2, diverse variables do not require Class IE qualification.
O e
SNUPPS TABLE 7A-3, DATA SIIEET 1.2 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.I.2 Control Rod Position Full in or not full in 3
Verification i
i
'l l h0 II.
SNUPPS DESIGN PROVISIONS l
4 VARIABLE ERFIS IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.1.2 Control Rod Position Full in to full out SF0074 N
022 N
002 N
NSSS 53 rods III.
REMARKS 1.
The SNUPPS design meets the stated recommendations.
2.
SNUPPS has 53 full-length control rods arranged in four banks (A through D), and each bank is divided into two groups.
Each group consists of several assemblies which move together.
3.
The rod position monitoring is performed by two separate systems:
(1) the digital rod position indication system and (2) a demand position system. The position of each rod is indicated on a dedicated LED.
These systems are described in FSAR Section 7.7.1.3.2.
SNUPPS TABLE 7A-3, DATA SHEET 1.3 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.2.4 Core Exit Temperature 3 200 F to 2300 F (for operating 33 Verification plants - 200 F to 1650 F) 9
'il $s C l.1 Core Exit Temperature 3 200 F to 2300 F (for operating 18 Detection of potential for breach, plants - 200 F to 1650 F) accomplishment of mitigation, long-term surveillance II.
SNUPPS DESIGN PROVISIONS UARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.2.4 Core Exit Temperature 200 - 2300 F TE-1 through Y
RP081 Y
RP081 Y
NSSS C l.1 TE-50 (50 total)
III.
REMARKS 1.
The SNUPPS design meets the stated recommendations.
2.
All 50 thermocouples are qualified to Class IE requirements and provide inputs to the subcooling monitor described on data sheet 1.5.
3.
All 50 thermocouples are indicated and recorded on qualified devices in the control room. Diversity is not required due to extensive redundancy provided.
O e
SNUPPS TABLE 7A-3, DATA SHEET 1.4 I.
RECULATORY CUIDE 1.97 TABLE 2 RECO999ENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE B.2.5 Coolant Level in Reactor Bottom of core to Top of Vessel 1
Verification, accomplishment of mitigation (direct indi-v
- h cating or re-cording de-vice not required)
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDElfr. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.2.5 Reactor Vessel Water Bottom to top of LIT 1311 Y
021 Y
080 Y
NSSS Level vessel LIT 1312 Y
021 Y
080 Y
NSSS NSSS LIT 1321 Y
021 Y
LIT 1322 Y
021 Y
NSSS III.
REMARKS 1.
The SNUPPS design meets all of the stated recommendations.
2.
The SNUPPS RV level indication system will provide information on the RV water level with or without the RC pumps in opera-tion. This Class IE system will utilize two pressure taps to cover the range from the bottom of the vessel to the top of the vessel.
3.
The design includes four indicating devices which provide redundancy (two devices) for the two design conditions.
4.
Diversity is provided by the core exit thermocouples described on data sheet 1.3.
0 f
SNUPPS TABLE 7A-3, DATA SHEET 1.5 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.2.6 Degrees of Subcooling 200 F subcooling 2
Verification and analysis of plant
,i 6.
to 35 F superheat (With con-conditions firmatory operator procedures)
II.
SNUPPS DESIGN PRO */ISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.2.6 Subcooling Monitor 200 F subcooled to RPO81A Y
022 NSSS 2,000 F superheat RPO81B Y
022 NSSS III.
REMARKS 1.
The SNUPPS subcooling monitor meets all of the stated recommendations.
2.
The subcooling monitor design provisions are described in Section 18.2.13.4.
The system is Class IE and fully qualified.
3.
Diversity is not required, since this system is considered to be Category 2 per the regulatory recommendations; however, extensive redundancy in the inputs is provided to ensure system reliability.
This system could be utilized by the plant operators following an event; however, it is not considered a Type A variable, 4.
since the operator will be able to perform subcooling calculations, using existing instrumentation.
I I
l l
l
SNUPPS TABLE 7A-3, DATA SHEET 2.1 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.I.4 RCS Cold Leg Water 50 F to 400 F 3
Verification i
iTemperature B.2.2 RCS Cold Leg Water 50 F to 750 F 1
Function detection, accomplishment of miti-8 Temperature gation, verification, long-term surveillance II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.I.4 RCS Temperature 0-700 F TE-413B Y
021 Y
022 N
NSSS T
B.2.2 Wide Range Cold 0-700 F TE-423B Y
021 Y
022 N
NSSS 0-700 F TE-433B Y
022 N
NSSS 0-700 F TE-443B Y
022 N
NSSS III.
REMARK _S 1.
The RCS wide-range T instruments are Class IE and powered from Protection Sets I and II.
Protection Set I instruments areindicatedseparaEEkhonaqualifiedindicator.
The T and T readings for each loop are recorded on a dual pen cold hot recorder.
2.
The existing range meets the intent of the recommended range in that it exceeds all expected design basis conditions. Other associated variables will be available to help ensure that the operator is aware of primary system parameters.
3.
Diversity is not required due to the extensive redundancy provided; however, the operator can use the steam line pressure of the associated steam generator to estimate the T readings. T will trend with T for Asso-ciated variables which provide useful informatio8 kNelude T an8 kNe core exit temperI N res. each steam generator.
4.
This parameter is a Type A variable, and it is used throughb8k the EOIs.
SNUPPS TABLE 7A-3, DATA SHEET 2.2 1.
REGULATORY GUIDE 1.97 TABLE 2 RECOpetENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.2.1 RCS Hot Leg Water 50 F to 750 F 1
Function detection, accomplishment of
,Tempppture mitigation, verification, long-term surveil-lance II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPtfrER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.2.1 RCS Temperature Wide 0-700 F TE-413A Y
021 Y
022 N
NSSS Range T 0-700 F TE-423A Y
021 Y
022 N
NSSS Hot 0-700 F TE-433A Y
021 N
NSSS 0-700 F TE-443A Y
021 N
NSSS III.
REMARKS 1.
The RCS wide-range T instruments are Class IE and powered from Protection Sets I and II.
Protection Set I instruments are indicated separak8ky on a qualified indicator. As noted on data sheet 2.1, T is recorded with T f the same loop on a dual pen recorder.
hot eold 2.
The existwg range meets the intent of the regulatory recommendation in that it exceeds all expected design basis conditions.
3.
Diversity is not required due to the extensive redundancy provided; however, the operator could use the core exit thermo-couples as a diverse measurement. Refer to data sheet 1.3.
4.
This parameter is a Type A variable, and it is used throughout the EOIs.
4 e
t
=
SNUPPS TABLE 7A-3, DATA SIIEET 2.3 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.2.3 RCS Pressurel 0-3,000 psig (4,000 psig for 12 Function detection, accomplishment of CE plants) mitigation, verification, long-term sur-
' 6e veillance B.3.1 RCS Pressure 8 0-3,000 psig (4,000 psig for la Function detection, accomplishment of CE plants) mitigation C.2.1 RCS Pressure 1 0-3,000 psig (4,000 psig for 12 Detection of potential or actual breach, CE plants) accomplishment of mitigation, long-tena surveillance C.3.1 RCS Pressure 8 0-3,000 psig (4,000 psig for la Detection of potential for breach, accom-CE plants) plishment of mitigation.
II.
SNUPPS DESIGN PROVISIONS 2
VARIABLE ERFIS IDENT, NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.2.3 RCS Pressure 0-3,000 psig PT-405 Y
022 Y
022 N
NSSS B.3.1 0-3,000 psig PT-403 Y
O22 Y
022 N
NSSS C.2.1 0-3,000 psig PT-XXX Y
022 Y
C.3.1 NA Pressurizer Pressure 1,700 to 2,500 psig PT-455 Y
002 N
022 N
NSSS PT-456 Y
002 N
PR 455-Select NSSS PT-457 Y
002 N
1 of 4 NSSS PT-458 Y
002 N
NSSS III.
REMARKS 1.
The RCS pressure instruments meet all of the stated requirements.
2.
RCS pressure is a Type A variable, and is used throughout the EOIs.
5 SNUPPS TABLE 7A-3, DATA SHEET 2.4 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.3.1 Reactor Coolant Pump Motor Current 3
To monitor operation
, Statyp 4
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COM2 UTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.3.1 Reactor Coolant Pump 0-600A CT-PA0107 N
021 N
BOP Motor Current 0-600A CT-PA0108 N
021 N
BOP 0-600A CT-PA0204 N
021 N
BOP 0-600A CT-PA0205 N
021 N
BOP III.
REMARKS t
1.
The SNUPPS design meets the stated recommendations.
t t
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~
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SNUPPS TABLE 7A-3, DATA SHEET 1.5 1.
REGULATORY GUIDE 1.97 TABLE 2 RECOfetENDATIONS VARIABLE IDENT. NO.
VARIA*LE RANGE CATEGORY PURPOSE D.3.2 Primary System Safety closed-not closed 2
Operation status, to monitor for loss
,Re}jg{ Valve Positions of coolant (including PORV and code valves) or Flow Through or Pressure in Relief Valve Lines II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER 1NDICATOR RECORDER IDEhT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.3.2 PORV Position Closed-not closed HIS-455A Y
021 Y
BOP HIS-456A Y
021 Y
BOP D.3.2 PORV Block Closed-not closed HIS-8000A Y
021 Y
BOP Valve Position HIS-8000B Y
021 Y
BOP D.3.2 Safety Valve Position Closed-not closed ZL-8010A Y
021 Y
BOP ZL-8010B Y
021 Y
BOP ZL-8010C Y
021 Y
BOP III.
REMARKS 1.
The SNUPPS design meets the stated recommendations. Section 18.2.14.2 provides more information on these items.
2.
Since the SNUPPS design provides position monitoring of the subject valves, the flow through or pressure in the discharge lines to the PRT is not provided.
3.
Diversity is not required, since this is an NRC Category 2 variable. However, the PRT parameters described on data sheet 2.8 are available.
t e
SNUPPS i
TABLE 7A-3, DATA SHEET 2.6 I.
REGULATORY GUIDE I.97 TABLE 2 RECOMMENDATIONS l
.i VARIABLE CATEGORY PURPOSE IDENT. NO.
VARIABLE RANGE 7
Bottom to top 1
To ei.sure proper operation of pressurizer 5
Pgeysurizer Lev 51 j{
D.3.3 i
/
E' J
, ' I.
, v i
i II.
SNU?N DESIGN PROVISIONS k r,
~
9 VARIABLE
- f' \\
i SENSOR / TRANSMITTER CONTROL;100M ERFIS C%F1, UTER IDENT.[NO VARIABLE RANGE NY INDICATOR REC 092ER l'
t 2
t I
I 4,
'e,',
TNNT. NO.
'CL. IE r'
~
t N'
t; s
/
y.
t D.3.3 Pressuxiser Level Eottom to top of LT-459 YN
"' 002 Y
002
%SSS-s straight shell LT-460 Y
002 Y
Select 1 of> 3 NSSS 4,
,}
LT-461 Y
002 Y
+
NSSS i
i
^
s a
Y
\\
\\
if
~
III.
REMARKS r
is a li Appreaimately D3 permut of the total volume is covered.
1.
.The range covered meets the intent of the recommended range.
not linear.
9fonitoring'lesel in the hemispherical heads is not advisable, sincethevolune-toehvelratio]is}4 N
- 2. \\ ( This ic b Type A variable, and is used throughout the EOIs fos 'operlator actioc. [ j 4'
i s
- 1. \\ Diversity 'is not required due to the extensive redundancy provide 2.
s s
g
,s
- g i
m
.\\
. A c \\.
x, i c.
,s _
_}. -,,..
s s
v s
f i
4 t
s s
=k s
Q
-e E
t
/
[%
r
[ I e
g T
e
',,,)
?
j
's y
j g
(.'
,1 j
.g r
,yp..
\\.
s 3e
)
g
-y.
v-a s
t-s e
,s
=
?, '
E-
+#
(g '
g s,
SMIPPS
()
TABLE 7A-3, DATA SHEET 2.7 s
I.
REGULATORY CUIDE 1.97 TABLE 2 RECOP9tENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.3.4 Pressurizer Heater Electric current 2
To determine operating status
, St4tns II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR /TRJ NSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.3.4 Pressurizer Heater 0-300A CT-NB0106 Y
015 Y
BOP Current 0-300A CT-NB0208 Y
015 Y
BOP III.
REMARKS 1.
The SNUPPS design meets the stated recommendations.
Diversity is not required, since this is an NRC Category 2 variable.
2.
i O
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O 4
SNUPPS TABLE 7A-3, DATA SHEET 2.8 I.
REGULATORY CUIDE I.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.3.5 Quench Tank Level Top to bottom 3
To monitor operation D.3.6 QuenchATank Temperature 50 F to 750 F 3
To monitor operation D.3.7 Quench Tank Pressure O to design pressure
- 3 To monitor operation II.
SNUPPS DESIGN PROVISIONS ERFIS UARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.3.5 Pressurizer Relief Tank Top to bottom LT-470 N
021 N
NSSS Level NSSS D.3.6 Relief Tank Temperature 50 to 350 TE-468 N
021 N
D.3.7 Relief Tank Pressure 0-100 psig (design) PT-469 N
021 N
NSSS III.
REMARKS 1.
The PRT is a horizontal, cylindrical tank. The level is measured for 100 of the ll4-inch tank diameter, which as essen-tially top to bottom.
The PRT temperature range is adequate to monitor any expected conditions in the tank. The PRT design pressure is 100 psig 2.
(T
= 327.8 F), and the rupture disc release pressure is 91 psig, nominal. Following breach of the disc, the tempera-tuf 8 of the tank cannot exceed the saturation temperature associated with the existing containment pressure.
3.
The PRT parameters are available in the ERFIS and NSSS computers; therefore, it is not necessary to provide a dedicated recorder.
4.
Although these instruments are located inside the containment, they are not qualified for post-accident conditions, since Primary and secondary loop parameters, as well as containment they are not required following a major LOCA or MSLB break.
are available to allow the operator to determine the nature and course of the accident. The EOIs do not parameters, indicate any use of these parameters following an event. Refer to Section 7A.3.8.
e i
i A
SNUPPS i
TABLE 7A-3, DATA SHEET 3.1 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS
?
)
UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE 0 to 110% design flow
- 2 To monitor operation 3
D.1.1 fHR,jygtemFlow D.l.2 RHR Heat Exchanget 32 F to 350 F 2
To monitor operation and for analysis Outlet Temperature i0 2
To monitor operation D.2.5 Flow in LPI Systen.
O to 110% design flow II.
SNUPPS DESIGN PROVISIONS ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER VARIABLE INDICATOR RECORDER IDENT NO.
CL. IE PANEL CL. IE PANEL CL. IE D.l.1 RHR/LPI-Inj./Recirc.
0-114%
FT-618 N
017 N
018 N
NSSS FT-619 N
017 N
018 N
NSSS Cold Leg NSSS D.2.5 LPI - Hot Leg Recircu-0-170%
FT-988 N
018 N
lation Flow D.l.2 RHR Heat Exchanger A 50-400 F TE-612 N
018 N
NSSS TE-604 N
018 N
NSSS Inlet / Outlet Tempera-tures 018 N
NSSS D.l.2 RHR Heat Exchanger B 50-400 F TE-613 N
018 N
NSSS TE-605 N
Inlet / Outlet Tempera-tures III.
REMARKS The accumulator tank level and pressure instruments are provided to ensure that, during normal operation, the accumulators These variables are 1.
are functional and available to provide the required flow to the cold legs following a large LOCA.The power to the isolation valves is t
monitored every shift in accordance with Technical Specification Paragraph 4.5.1.1.
periodically verified to be locked out in accordance with the same technical specification.
i the pressure Since the accumulators will immediately discharge when the RCS pressure drops below the accumulator pressure,The operator will know the
/
2.
and level of the accumulators is unnecessary following an event.
the operator would not be able to utilize
?
Since power is locked out at the circuit breaker (outside of the control room),the pressure and level indicators fo i
For these events, the present indicators could be expected to function properly.
Jhould there be a question as to whether the accumulators actually discharged into a depressurized but relatively intact primary system, the operator could utilize the pressurizer and RV level indication to determine if nitrogen was in
}
3.
q pressurizer or the vessel head. These areas can be vented from the control room, if it is deemed appropriate.
j 1
4 4
SNUPPS TABLE 7A-3, DATA SHEET 3.1 (Continued)
III.
REMARKS 1.
The proper operation of the kHR system as verified by observing pump and valve status indications provided on the main control board, which contains simic diagrams of the flow paths. These indications are fully qualified to Class IE requirements.
serves the dual function of residual heat removal and low pressure injection / recirculation.
3.
The RHR system (Figure 5.4-7)
The flow rates are indicated for all modes of operation; however, they are provided for performance monitoring only. The flow rate and %epperature monitoring is not required for any safety-related function and, there fore, the instruments are not safety grade or Class IE.
The proper operation of the kHR system is verified by observing pump and valve status l
indications provided on the main control board, which contains mimic diagrams of the flow paths.
These indications are fully qualified to class IE requirements.
3.
Since the sensors / transmitters are part of the pressure boundary, they are designed to remain intact following an SSE; however, functionality is not assured.
4.
The RHR injection phase runout flow is limited to 4,428 gpm.
The range of FT-618 and 619 is 0 to 5,500 gpa.
The RHR hot leg recirculation flow is 2,641 gpm for one RHR pump operating. The range of FT-988 is O to 4,500 gpm.
5.
Train A flow (FT-618) and temperatures (TE-604 and 612) ate recorded on TR-612.
Train B flow (FT-619) and temperatures (TE-605 and 613) are recorded on TR-613.
The heat exchanger inlet temperatures are not considered to be part of the Regulatory Guide 1.97 data base.
p l
l l
l 4
1
SNUPPS TABLE 7A-3, DATA SHEET 3.2 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.2.1 Accumulator Tank 10% to 90% volume 2
To monitor operation Levs] bhd Presstre O to 750 psig D.2.2 Accumulator Isolation Closed or open 2
Operation status Valve Position II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.2.1 Accumulator Tank Level 13+ inches LT-950 N
018 N
NSSS (Unnecessary) through 957 D.2.1 Accumulator Tank 0-700 psig PT-960 N
018 N
NSSS Pressure (Unnecessary) through 967 D.2.2 Accumulator Isolation Closed /Open HIS 8808A Y
018 Y
BOP valves through D III.
REMARKS 1.
The accumulator tank level and pressure instruments are provided to ensure that, during normal operation, the accumulators are functionai snd available to provide the required flow to the cold legs following a large LOCA.
These variables are monitored ever) shift in accordance with Technical Specification Paragraph 4.5.1.1.
The power to the isolation valves is periodically verified to be locked out in accordance with the same technical specification.
3.
Since the accumulators will immediately discharge when the RCS pressure drops below the accumulator pressure, the pressure and level of the accumulators is unnecessary following an event. The operator will know their status based on RCS pressure.
Since power is locked out at the circuit breaker (outside of the control room), the operator would not be able to utilize the pressure and level indicators for manual actions, except for events where the RCS pressure is decreasing very slowly.
For these events, the present indicators could be expected to function properly.
3.
Should there be a question as to whether the accumulators actually discharged into a depressurized but relatively intact primary system, the operator could utilize the pressurizer and RV level indication to determine if nitrogen was in pressurizer or the vessel head. These areas can be vented from the control room, if it is deemed appropriate.
SNUPPS TABLE 7A-3, DATA SHEET 3.3 1.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS IDENT NO.
VARIABLE RANGE CATEGORY PURPOSE VARIABLE 80 2
To monitor operation D.2.3 i Boric Acid Charging 0-110% design flow Flow D.2.4 Flow in HPI System 0-110% design flow 2
To monitor operation II.
SNUPPS DESIGN PROVISIONS
}
ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER UARIABLE IND1CATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE NSSS D.2.3 Centrifugal Charging 0-140%
FT-917A Y
018 Y
Pump Flow (BIT) 0-140%
FT-917B Y
018 Y
NSSS NSSS D.2.4 Safety injection Pump 0-121%
Fr-918 N
017 N
NSSS Flow 0-121%
FT-922 N
017 N
D.2.4 Charging to RCP Seals 0-400%
FT-215A Y
001 Y
NSSS 0-400%
FT-215B Y
001 Y
NSSS 111.
REMARKS The range of FT-918 and 922 (shown on Figures 6.3-1, The SI pump flow rates are 440 gpm for injection and recirculation.The centrifugal charging pump flow rate to the BIT path is 714 gpa for injectio 1.
Sheet 2) is 0 to 800 gpm.
is O to 1,000 gpm.
The range of FT-917A and 917B (shown on Figure 6.3-1, Sheet 3)is provided by the centrifugal charging pumps,as described in Sec-2.
The flow to the RCP seals (shown on Figure 9.3-8) tion 9.3.4.
The normal flow rate is 20 gpa (5 gpm per pump). This flow path is also utilized as part of safe shutdown with only safety-related equipment. Refer to Appendix 5.4A.
The range of FT-215A and 215B is 80 gpm.
there fore, The safety injection flow is provided for performance monitoring only and is not required following an accident;The cen 3.
the transmitters are not Class IE.
therefore, they are Class IE.
1
SNUPPS TABLE 7A-3, DATA SHEET 3.4 Z.
REGULATOR 1t GUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.2.6 Refueling Water Storage Top to bottom 2
To monitor operation 4
Tank, Le, vel 1
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.2.6 Refueling Water Storage Top to Bottom LT-930 Y
018 Y
018 N
NSSS Tank Level LT-931 Y
018 Y
018 N
NSSS LT-932 Y
018 Y
NSSS LT-933 Y
018 Y
NSSS III.
REMARKS 1.
The RWST level instrumentation is shown on Figure 6.3-1 and fully meets the stated requirements.
3.
The RWST level indications and alarms are utilized during switchover from injection to recirculation in a 2-out-of-4 logic.
RWST level is a Type A variable, per the assumptions stated in Section 7A.3.1.
e
SNUPPS TABLE 7A-3, DATA SHEET 4.1 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE i
IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE t
t D.4.1
,Ste,am, Generator Level From tube sheet to separators 1
To monitor operation II.
SNUPPS DESIGN PROVISIONS 4
ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.4.1 Steam Generator Level - Near tube sheet to LT-501 Y
025 Y
026 N
NSSS Wide Range separators LT-502 Y
025 Y
026 N
NSSS LT-503 Y
025 Y
026 N
NSSS LT-504 Y
025 Y
026 N
NSSS NA Steam Generator Level - 91 inches LT-517,518,519 Y
026 Y
NSSS NSSS i
Narrow Range LT-527,528,529 Y
026 Y
LT-537,538,539 Y
026 Y
NSSS LT-547,548,549 Y
026 Y
NSSS NSSS LT-551,2,3&4 Y
025 N
III.
REMARKS The steam generator wide range instrumentation provides level indication from 22 inches above the tube sheet to the moisture i
1.
)
separators and meets the intent of the recommended range.
2.
The four narrow range level transmitters on each loop are fully qualified and are considered to be a Type A variable per the assumptions stated in Section 7A.3.1.
The narrow range transmitters are used to identify a steam generator tube rupture.
The narrow range instruments provide diverse indications within their range and would indicate the failure (high or low) of 3.
a wide range instrument.
l i
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i i-
SNUPPS TABLE 7A-3, DATA SHEET 4.2 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE D.4.2 Steam Generator From atmospheric pressure to 2
To monitor operation Pressure 20 percent above the lowest b f8 safety valve setpoint II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT NO.
CL. IE PANEL CL. IE PANEL CL. IE D.4.2 Steam Line Pressure 0-1,300 psig PT-514, 5, 6 Y
026 Y
026 (PT-514) N NSSS (0-110% above PT-524, 5, 6 Y
026 Y
026 (PT-524) N NSSS lowest safety PT-534, 5,
6 Y
026 Y
026 (PT-535) N NSSS valve setpoint)
PT-544, 5, 6 Y
026 Y
026 (PT-545) N NSSS NA Steam Line Pressure 0-1,500 psig PT-1 Y
006 Y
for PORV Operation 126%
PT-2 Y
006 Y
PT-3 Y
006 Y
PT-4 Y
006 Y
III.
REMARKS 1.
The lowest safety valve setpoint is 1,185 psig. The steam line pressure transmitters have a range of 0 to 1,300 psig, which is 110 percent above the lowest setpoint. Although this range is considered to be adequate, the higher ranges can be monitored by PT-1 through PT-4.
2.
The steam line pressure transmitters used for PORV operation have a range of 0 to 1,500 psig, which is 126 percent of the lowest setpoint. These instruments are not considered part of the RG 1.97 data set per the assumptions stated in Section 7A.3.2 and are not inputted to the ERFIS data systems.
3.
The steam line pressure is a Type A variable per the assumptions stated in Section 7A.3.1, and is used to detect an SGTR and secondary side break and to identify the affected steam generator.
l l
SNUPPS TABLE 7A-3, DATA SiiEET 4.3 1.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT, NO.
VARIABLE RANCE CATEGORY PURPOSE D.4.3 64fety/ Relief Valve closed - not closed 2
To monitor operation Positions or Main Steam Flow II.
SNUPPS DESIGN PROVISIONS UAhTABLE ERFIS IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.4.3 Atmospheric Relief Closed - not closed ZS-1 Y
006 Y
ZS-2 Y
006 Y
BOP ZS-3 Y
006 Y
BOP ZS-4 Y
006 Y
BOP D.4.3 Safety Relief Valve See Note 2 Position (20 valves) 3II.
REMARKS 1.
The atmospheric relief valve (PORV) position fully meets the stated requirements. See data sheet 12.3 for a discussion of the use of the demand position indication in determining release flow rates.
2.
As described on data sheet 12.3, steam line pressure and flow will be utilized to determine if any safety valve is open.
3.
Main steam flow instrumentation is provided and available in the contrcl room, but it is not considered necessary or appropriate for the recommended function.
9
SNUPPS TABLE 7A-3, DATA SHEET 4.4 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS i
VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.4.4 Main Feedwater Flow 0-110 percent 3
To monitor operation t
's, in II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.4.4 Main Feedwater Flow 0-121 percent of FT-510 N
026 N
006 N
NSSS VWO flow FT-511 N
026 N
NSSS FT-520 N
026 N
006 N
NSSS FT-521 N
026 N
NSSS ET-530 N
026 N
006 N
NSSS FT-531 N
026 N
NSSS FT-540 N
026 N
006 N
NSSS ET-541 N
026 N
NSSS III.
REMARKS 1.
The SNUPPS design meets all of the stated recommendations.
3.
The flow transmitter has a range from 0 to 4.8 x 10 lbs/hr. The VWO flow is 3.96 x los Ibs/hr for each line.
8 e
SNUPPS TABLE 7A-3, DATA SHEET 5.1 1.97 TABLE 2 RECOMMENDATIONS I.
REGULATORY CUIDE PURPOSE CATEGORY VARIABLE RANGE IDENT. NO.
VARIABLE 2 (1 for To monitor operation 0-110 percent design B & W plants)
D.5.1
,Austi}iaryorEmergency flow 20 l
Fe&dwkter Flow II.
SNUPPS DESIGN PROVISIONS ERFIS COMPUTER CONTROL ROOM SENSOR / TRANSMITTER VARIABLE RANGE IDENT. NO.
VARIABLE INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE BOP D.5.1 Auxiliary Feedwater 0-170%
FT-1 Y
006 Y
BOP FT-2 Y
006 Y
Flow FT-3 Y
006 Y
BOP BOP FT-4 Y
006 Y
FT-7 Y
BOP BOP 0-170%
BOP NA FT-9 Y
Pf-Il Y
REMARKS III.
The auxiliary feedwater system is described in Section 10.4.9 and shown on Figure 10.4-9.Each flow transmitter is powered b loop.
Auxiliary feedwater flow to each steam generator is monitored by Class IE flowa different separat line PORV. Only two of the four 1.
2 steam generators are required to establish a heat sink for the RCS.
is provided in Section 18.2.7 generators is assured assuming a single failure.A comparison of the AFWS to the NUREG-0737 requirements for r i
i which shows complete compliance to all recommendations.The design flow to the steam generators is 250 gpa for a normal shut-3.
The range above is calculated The flow transmitters leave a range of 0 to 400 gpm.For a MSLB the design flow to two intact steam generators is 470 gpm (2 4.
down.
using the normal shutdown flow requirements.
l 1
l l
SNUPPS TABLE 7A-3, DATA SHEET 5.2 REGULATONY CU1DE 1.97 TABLE 2 RECOMMENDATIONS PURPOSE CATEGORY VARIABLE RANCE IDENT. NO.
VARIABLE To ensure water supply for auxiliary 1
Plant Specific feedwater (Can be Category 3 if not primary D.S.2
,Condgnsate Storage Tank f.evel source of AW.
Then whatever is primary I
source of AW should be listed and should be Category 1.)
11.
SNUPPS DESIGN PROVISIONS ERFIS CONTROL ROOM COMPUTER VARIABLE RANGE SENSOH/ TRANSMITTER IDI"'T. NO.
VARIABLE INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE BOP D.5.2 Condensate Storage 1ank Top to bottom PT-24 Y
005 Y
BOP PT-25 Y
005 Y
BOP Level (indicated by pump PT-26 Y
005 Y
suction pressure)
NA Condensate Storage Tank Appropriate for PT-37 Y
026 Y
BOP Level (for automatic automatic switch-PT-38 Y
026 Y
BOP BOP AFWS switchover) over to ESW PT-39 Y
026 Y
NA Condensate Storage Tank 0-100%
LT-4 N
005 N
BOP Level III.
REMARKS As stated in Section 10.4.9, The CST is shown on Figure 9.2-12, and the pressure transmitters are shown on Figure 10.4-9.
The automatic switchover to ESW upon the depletion of CST water 1.
is non-safety grade and provides a direct level reading; however, this the CST level will be determined by PT-24, 25, and 26.
volume will be initiated by PT-37, 38, and 39.
LT-4 instrument is not considered part of the RG 1.97 data base.
W), the CST level Since there is no manual action required for switchover to the alternate source of auxiliary feedwater (ES 2.
measurements are not Type A variables.
f l
SNUPPS TABLE 7A-3, DATA SiiEET 6.I 1.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE 0 to design pressure * (psig) 1 Function detection accomplishment of B.3.3 Containment Pressure 8 mitigation, verification 10 psia to design pressure
- 1 Same B.4.2 Containment Pressure 8 10 psia to design pressure *,
1 Detection of breach, accomplishment of C.2.2 Containment Pressure 8 psig (5 psia for subatmo-mitigation, verification, long-term spheric containments) surveillance 10 psia to 3 times design 1
Detection of potential for or actual breach, C.3.3 Containment Pressure 8 pressure for concrete (4 times accomplishment of mitigation, verification design pressure for steel)
(5 psia for subatmospheric containments) i II.
SNUPPS DESIGN PROVISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.3.3 Containment 'Eressure 0-60 psig PT-934 Y
018 Y
018 N
NSSS B.4.2 (normal design range)
PT-935 Y
018 Y
018 N
NSSS C.2.2 PT-936 Y
018 Y
018 N
NSSS PT-937 Y
018 Y
018 N
NSSS C.3.3 Containment Pressure -
-5 to 180 psig PT-938 Y
020 Y
020 N
NSSS Wide Range PT-939 Y
020 Y
020 N
NSSS NA Containment Pressure
-3 to +3 psig PDY-40 N
020 N
BOP (anorm.al operating range)
Ii1.
REMARKS 1.
The SNUPPS design meets all of the stat ed requirements.
2.
The design pressure of the containment is 60 psig.
The peak calculated pressure following a LOCA and MSLB are 47.3 and 48.1 psig, respectively. As stated in Section 7A.3.2, diversity is not required in extended ranges not associated with DBEs.
3 Monitoring of subatmospheric conditions recommended in items B.4.2 and C.2.2 is accomplished by the wide range instruments.
4.
Normal containment pressure will be maititained near atmospheric pressure and measured by pressure transmitters located inside and outside of the containment. The difference in pressures will be indicated in the control room. This instrumentation is not part of the Regulatory Guide 1.97 data base.
SNUPPS i
i TABLE 7A-3, DATA SHEET 6.2 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS t
UARIABLE j
IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.3.2 Containment Sump Water Narrow range (sump) 2 Function detection, accomplishment of
' Level
Wide range (bottom of contain-1 mitigation, verification ment to 600,000-gallon level equivalent)
C.2.3 Containment Sump Water Narrow range (sump) 2 Detection of breach, accomplishment of i
Level 8 Wide range (bottom of contain-1 mitigation, verification, long-tern l
ment to 600,000-gallon level surveillance equivalent)
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.3.2 Normal Sump Water Level 868,000 gallons LIT-9 Y
018 Y
BOP C.2.3 LIT-10 Y
018 Y
020 Y
BOP NA RHR Recirculation Sump 604,000 gallons LIT-7 Y
018 Y
BOP Level LIT-8 Y
018 Y
020 Y
BOP III.
REMARKS 1.
Refer to Section 18.2.12 for a comparison with NUREG-0737 requirements.
2.
The SNUPPS design provides for Class IE level monitoring in each of the two containment normal sumps and in each of the two RHR sumps. The bottom of the normal and RHR sumps are at Elevations 1,995 feet and 1,992 feet, respectively. The levels in each sump are monitored from 6 inches above the sump bottoms for the next 156 inches. The MSLB results in the maximum flood level of 2006'-6" (650,000 gallons). The normal sump level extends to 20088-6", providing 2 feet of range above the maximum flood level.
3.
Both the normal and RHR sumps are provided with twin level elements which are indicated on one continuous indicator.
Redundancy is provided in each type of sump. Diversity is not required, since there are four independent water level measurements.
4.
The normal sump level is a Type A variable on SNUPPS. The normal sump level is used for event identification. The RHR sump level is not a Type A variable. Although the recirculation sump level could be used for event identification, it is not required and would not be flooded with water immediately following an event since there is a 6-inch curb around it.
Similarly, since switchover to recirculation is initiated automatically on low RWST level, verification containment water level is not required nor part of a preplanned manual safety function. Refer to Section 7A.3.1.
k I
SNUPPS
~
TABLE 7A-3, DATA SHEET 6.3 1.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS i
1 a
i VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE B.4.1 Cont 4isynent Isolation Closed - not closed 1
Accomplishment of isolation Valve Position (ex-cluding check valves)
II.
SNUPPS DESIGN PROVISIONS UARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER 1
INDICATOR RECORDER l
IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE B.4.1 Containment Isolation Closed - not closed See Figure Y
Misc.
Y BOP Valve Position (ex-6.2.4-1 l
cluding manual and check valves)
III.
REMARKS i
1.
Refer to Section 6.2.4 and 18.2.11 for discussions of containment isolation. As noted in Section 6.2.4, manual valves do not have position indication in the control room. The position of the manual valves is verified on a monthly basis in accordance with Technical Specification Paragraph 4.6.1.1.
In addition, these valves are under administrative control and are locked or sealed closed whenever containment integrity is required.
I i
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e 6
SNUPPS TABLE 7A-3, DATA StiEET 6.4 I.
RECULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATECORY PURPOSE C.3.2 Cpntq}rgent Hydrogen o to 10% (capable of operating I
Detection of potential for breach, Concentration from 10 psia to maximum design accomplishment of mitigation, long-term pressure *)
surveillance E.6.4 Hydrogen Content 0 to 10%
3 helease assessment, verification analysis II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE C.3.2 containment Hydrogen 0-10%
AT-10 Y
020 Y
020 Y
BOP E.6.4 Concentration AT-19 Y
020 Y
BOP II1.
REMARKS I
1.
The hydrogen analyzers are described in Section 6.2.5 and shown on Figure 6.2.5-1.
2.
The hydrogen analyzers meet all of the stated requirements. Refer to Section 18.2.12 for a comparison with NUREG-0737 requirements. The analyzers will operate properly within the recommended containment pressure ranges.
3.
The hydrogen concentration as not a Type A variable, since the recombiners will be started I day after an accident. Should the need arise, the recombiners could be started following load sequencing operations should the core or primary systems indicate a pote.ntial for hydrogen generation rates above any current design bases.
As stated an Section 7A.3.1.g, Type A variables are t.ot identified for postulated conditions not in the current design bases.
4.
Although there is no need for a diverse variable, the post-accident sampling systems will provide the capability to sample the containmerit atsnosphere following an event.
Refer to data sheet 13.1.
As stated in Section 7A.3.2.d. diverse variables need only be performance grade and not Class IE.
O
SNUPPS TABLE 7A-3, DATA SilEET 6.5 1.
REGULATOkY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE f
I D.6.3 font,qippent Atmosphere 40 F to 400 F 2
To indicate accomplishment of cooling Temperature II.
SNUPPS DESIGN PROVISIONS i
VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE 2
D.6.3 Containment Atmosphere 0-400 F TE-60 Y
018 Y
BOP Temperature TE-61 Y
018 Y
BOP BOP TE-62 Y
018 Y
l TE-63 Y
018 Y
020 Y
BOP III.
REMARKS l.
The SNUPPS design meets all of the stated recommendations.
2.
The SNUPPS design utilizes containment pressure to verify that containment heat removal is being accomplished. Refer to data sheet 8.1 for a further discussion.
3.
Containment temperature is not a Type A variable, since it does not meet the requirements discussed in Section 7A.3.1.
i 0
k
SNUPPS TABLE 7A-3 DATA SilEET 6.6 1.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT, NO.
VARIABLE RANGE CATECORY PURPOSE D.6.4 Contpt/nment Sump Water 50 F to 250 F 2
To monitor operation
, Temperature II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VAplABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE l
D.6.4 Containment Sump Water Temperature (unnecessary 1
l variable) i l
l III.
REMARKS 1.
This variable is unnecessary for the SNUPPS plants. The recommended purpose is to " monitor operation"; however, there is no system on SNUPPS for it to monitor. Containment cooling is monitored by the air temperature monitors described on data sheet 6.5.
2.
Sump temperature is not required for RHR operation or assurance of NPSH available, since NPSH calculations conservatively assume saturdled water was present. See Safety Evaluation Eleven of Section 6.2.2.1.3 and Table 6.2.2-7.
3.
Primary system, PRT, and other containment parameters are all available to help determine the plant conditions. Sump level indications indicate the amount of water, and the other parameters indicate its source.
4.
Note that proper RHR functions during the recirculation mode are provided by other variables described on data sheet 3.1.
5.
The Callaway SER (NUREG-0830) in Section 6.2.1.1 (page 6-4) indicates that the NRC Staff agrees that this variable is not necessary for the SNUPPS plants and finds this exception to the guidelines of Regulatory Guide 1.97 acceptable.
0 1
SNUPPS L
TABLE 7A-3, DATA SHEET 7.1 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS l
e-VARIABLE IDENT. NO.
VARIABLE RANGE CATEGOkY PURPOSE l-l D.7.1 gakeup, flow - In 0 to 110% design flow'8 2
To monitor operation
}'
D.7.2 Letdown Flow - Out 0 to 110% design flow 2
To monitor operation 88 I
D.7.3 Volume Control Tank Top to botton 2
To monitor operation l
Level e
II.
SNUPPS DESIGN PROVISIONS o
ERFIS y
VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE NSSS
[!
D.7.1 Normal Charging Flow 50 to 267%
ET-121 N
002 N
- 1 NSSS I,
D.7.2 Normal Letdown Flow 0 to 267%
FT-132 N
002 N
9I I
D.7.3 Volume Control Tank Top to bottom of LT-185 Y
002 Y
Level straight shell LT-112 Y
002 Y
LT-144 N
NSSS l4 t
!l D.7.2 Safety Related Letdown Later FT-138A Y
001 Y
l NSSS Later FT-138B Y
001 Y
6 III.
REMARKS f
1.
The normal charging and letdown flow rates are described on this data sheet. The DBA-related portion of the charging system I
is described on data sheet 3.3.
2.
The volume control tank level is Class IE to ensure a suction source from the RWST (automatically) on low VCT level.
6 3.
The level of the VCT is monitored for the straight shell portion only. The span is 75 inches. The hemispherical heads are l
not monitored, since the volume-to-level ratio is not linear.
4.
Appendix 5.4A describes the safety grade cold shutdown system provided in the SNUPPS design. As part of this des 2gn, a Class IE letdown system is provided to the PRT through the excess letdown heat exchanger.
6
SNUPPS TABLE 7A-3, DATA SHEET 8.1 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE D.6.2 yeat Rppoval by the Plant specific 2
To monitor operation contihent Fan Heat a
Removal System II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.6.2 Containment Cooler Heat Removal - (unnecessary variable)
III.
REMARKS 1.
This variable is unnecessary and is not provided on SNUPPS. The accomplishment of post-accident cooling is verified by monitoring the containment pressure and air temperature, as described on data sheets 6.1 and 6.5, respectively.
2.
During the transient of an accident, heat removal by air coolers cannot be used by an operator, since too many variables are changing rapidly. The amount of energy released to the containment cannot be accurately quantified. Heat removal mechanisms are those identified in Section 6.2.1 and include heat transfer to passive heat sinks, containment sprays, and containment air coolers. The operator must determine what equipment is operating and watch the changes in containment pressure, temperature, sump level, and radiation levels to determine the nature of the accident.
3.
The operability of the air coolers is verified periodically throughout the life of the plant in accordance with Technical Specification Paragraph 4.6.2.3, which ensures the proper operation of the system.
n e
SNUPPS TABLE 7A-3, DATA SHEET 9.1 1.
REGULATORY CUIDE I.97 TABLE 2 RECOMFENDATIONS UARIABLE IDENT. NO.
VARIABLE RAMGE CATEGORY PURPOSE D.8.1 Compqngpt Cooling Water 32 F to 200 F 2
To monitor operation Temperature to ESF System i
38 2
To monitor operation D.8.2 Component Cooling Water 0 to 110% design flow Flow to ESF System II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE 1
D.8.1 CCW Heat Exchanger 0-200 F TE-31 Y
019 Y
BOP Discharge Temperature TE-32 Y
019 Y
BOP D.S.2 CCW Pump Discharge Flow 0-137 percent FT-95 N
BOP FT-96 N
BOP ET-97 N
BOP FT-96 N
BOP III.
REMARKS 1.
The component cooling water system is described in Section 9.2.2.
The SNUPPS design meets the recommended ranges.
2.
Section 7A.3.7 describes the qualification of NRC Category 2 variables, as provided on SNUPPS. The instruments described l
herein are located outside of the containment in areas served by Class IE room coolers. These instruments are not required i
for the proper operation of the system; rather, they are provided for performance monitoring only.
3.
Since these instruments are part of the system pressure boundary, they are seismically designed to ensure integrity of the system boundary.
O
SNUPPS TABLE 7A-3, DATA StiEET 10. A REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS 1.
PURPOSE CATEGORY VARIABLE kANGE VARIABLE IDENT. NO.
To monitor operation 88 2
0-110% design flow D.6.1
, Con g4nment Spray Flow II.
SNUPPS DESIGN PROVISIONS ERFIS COMPUTER CONTROL ROOM SENSOR / TRANSMITTER UARIABLE RANGE IDENT. NO, VARIABLE RECORDER INDICATOR IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE BOP D.6.1 Containment Spray Flow 0-126% (design FT-5 N
017 N
flow - injection)
BOP 0-106% (design FT-11 N
017 N
flow - recircula-tion)
The spray system need only operate during the injection phase III.
REMARKS The containment spray system is described in Section 6.2.2.the flow rate monitor exceeds the recommended range.These instruments are located 1.
as provided on SNUPPS.
for cooling purposes. During this phase, These instruments are provided for performance Section 7A.3.7 describes the qualification of NRC Category 2 items,in areas tierved by Class IE room coolers.
2.
outside of the containment its integrity.
monitoring and not to allow proper system operation.
The instruments are part of the pressure boundary and are seismically designed to ensure 3.
Si e
SNUPPS TABLE 7A-3, DATA S!!EET 11.1 I.
REGULATORY GUIDE I.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE I
C.2.4 Containment Area 1 R/hr to 10' R/hr 36*7 Detection of breach, verification
' R'ddi'ation 3 E.1.1 Containment Area 1 R/hr to 10 R/hr l?
Detection of significant releases, release 7
Radiation - High assessment, long-tern surveillance, emergency plant actuation n
Range II.
SNUPPS DESIGN PROVISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE l
BOP C.2.4 Containment Area 1 to 10' R/hr 0-GT-RE-59 Y
067 Y
Radiation E.1.1 0-GT-RE-60 Y
067 Y
20 Y
BOP III.
REMARKS 1.
These instruments meet all of the stated recommendations and are further described in Section 18.2.12.
2.
As described in Section 7A.3.2, diverse variables are performance grade. Diversity for containment area radiation is pro-vided by the post-accident in line sampling system. Also, the SNUPPS design includes area radiation monitors with a range to 10 R/hr located inside the containment.
3.
This is a Type A variable and is used for event identification in the EOIs.
1 l
l
3 e
SNUPPS TABLE 7A-3, DATA Si!EET 11.2 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS l
VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE C.3.5 Aadihtien Exposure Rate 10 8 R/hr to 10' R/hr 2'
Indication of breach
~
(inside buildings or
- areas, e.g.,
auxiliary building, reactor shield building annulus, fuel handling, which are in direct contact with primary containment where penetrations and hatches are located)'
Detection of significant releases, release E.2.1 Radiation Exposure Rate' 108 R/hr to 104 R/hr 27 (Inside building or assessment, long-term surveillance areas where access is required to service equipment important to safety)
II.
SNUPPS DESIGN PROVISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE C.3.5 Radiation Exposure Rate Unnecessary Variable E.2.1 III.
REMARKS 1.
Area radiation monitors are shown on Figure 12.3-2 and are provided in accordance with the criteria stated in Section 12.3.4.1.
Process and effluent monitors are provided in accordance with the criteria stated in Section 12.3.4.2.
Area As monitors are provided in the corridors of the auxiliary building and not in the penetration areas or equipment spaces.
described in Section 12.3.4.2.2.2.9, a portable monitor may be used to determine the conditions in any equipment space.
The process and effluent monitors will provide indication of releases and/or breaches in the systems in cperation following 2.
an event. Use of extended range area monitors in the areas adjacent to the containment are not appropriate since the background, direct radiation levels can be expected to be quite high. The process and effluent monitors provide the required public protection.
3.
The existing area radiation monitors provide for adequate employee protection with their range to 10R/hr. Should this range
.be exceeded, employee entry will be prohibited.
SNUPPS TABLE 7A-3, DATA SilEET 12.1 REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS 1.
CATEGORY PURPOSE VARIABLE RANGE IDENT. NO.
VARIABI.E 2***
Detection of breach, accomplishment of l
i C.3.4 eCont4%nnent Effluent 10~' Ci/cc to mitigation, verification Radioactivity - Noble 10~3 Ci/cc l
Cases from Identified 3
Release Points 2*
Indication of breach 8
10~' Ci/cc to C.3.6 Effluent Radioactivity Noble Cases (from 103 Ci/cc buildings as indicated above) 2" Detection of significant releases, release i
~5 Ci/cc to assessment, long-term surveillance 8
10 E.3.1.3 Auxiliary Building l
3 Ci/cc (including any building 0 to 110% vent design flow
- 10 l
containing primary (Not needed if ef fluent dis-system gases, e.g.,
charges through common plant waste gas and vent flow rate) vent)
Detection of significant releases, release
~
28 E.3.2.2 Common Plant Vent or 10 ' Ci/cc to assessment, long-term surveillance 103 Ci/cc Multipurpose Vent Dis-0 to 110% vent design flow 88 charge Any of above 8
Releases (if con-10 Ci/cc to tainment purge is 10* Ci/cc included) 11.
SNUPPS DESIGN PROVISIONS ERFIS CONTROL ROOM COMPUTER VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER INDICATOR RECORDER IDENT. NOJ CL, IE PANEL CL. IE PANEL CL. IE
~7 to 10 pCi/cc GT-RE-21B~
N SP010 N
.SP010 N
RRIS 5
C.3.4 Plant Unit Vent Wide 10 E.3.2.2 Range Gas
~7 to 10 pCi/cc CH-RE-10B N
SP010 N
SP010 N f RRIS 5
Radwaste Building Wide 10 Range Gas O
e e
r 4
i
SNUPPS TABLE 7A-3, DATA SHEET 12.1 (Continued)
REMARKS 1.
The plant unit vent receives the discharge from the containment purge, auxiliary building, control building, fuel building, and the condenser air removal system. The radwaste building vent receives the discharge from the radwaste building exhaust fan.
The r3dwaste building contains the waste gas decay tanks.
2.
The unit vent flow rate is determined by fan run contacts which are imputted to the RMS computer. Each system is balanced and assumed to be operating at the design flow. The high range monitor is being purchased with an isokinetic flow monitor.
These provisigrw adequately meet the requirements of the item.
3.
The radwaste building vent is a constant flow vent receiving the discharge of the radwaste building exhaust fans. Flow rate monitoring is not required. The high range monitor for the radwaste building vent also has an isokinetic nozzle.
e e
g.
i.
SNUPPS i
s N*
~~
(s TABLE 7A-3, DAT[ SI.cr 12.2 u
I.
REGULATORY-GOIDd't.97 TABLE 2_ltECOMMENDA"JIONg
,.{
r
_ i 4.
i r
i VARIABLE **
6
\\
m i 2 ' ~-i
/
s s
IDEhT.N6,-(\\
VARIABLE
{
RANGE o's CATECORY PURPOSE q
i I
- 4 i -
3*
'1 Detection 4I breach, verification
'~-
1 A'-
C.2.5 Rffidettt Radioactivity - 10~' to 10 ! pCijcc
,~
5(
- 4. \\WobeI?,Cas Ef fluent from
/ f 2[
{'
-Cohdenser Air' Removal
' $; stem Exhas t'
/
l g/,
,.,d E.3.2.1 ' +. donderiser iiK Itemoval-10~6 to 105 pCi/cc '
g(
j s
, s g
Q
,\\ /
5 f -
,2"
.\\, / '
Dd get.ic,r.of'sJyaificm?. releases, release 0 to J10 percent vent design j,,,q')
? ',
/
flow ' (not needed if effluero. //.
ahessmeth.
i '
_ Dbeuri8 j
e
?.'
j(
l 4,.
l' y : [, -
- (j'i 1 / c'
\\ - ){ ) j 'i j(
discharges through, common i
t
.. ~ _
J'
_N 6
,N' plant vent) 4 l e
g l
\\
s-
/
s f[K V
s s
4 II.
SNUPPS DESIGN PROVISIONS
'i
).\\'
L
\\
n-VARIABLE
,i ERFIS't IDENT. NO. J.
VARIABLE 4
r RANGE SENSOR / TRANSMITTER
'r CONMOL ROOM (,
COMPUTER INDICATOR RECORDER Is
\\.
~
g 1
7 IDENT. NO.
CL. IE IE' M PANEL CL. IE PANEL CL.
s -
= j, '
p, y h 7
v.
~ -
C.2.5 condenser Air Removal 1071 to 10 2 pCi/cc RE-92
'N 056' N
056
'N I
f.Rf S
- J, Exhaust Radioactivity i [.
g l e, --
t.(L
- k 't\\ }*)
[.
)
, g
.A 4
e r
E.3.2.1 Condenser Air.Removil T'
t
.\\q" s
g s
Exhaust (not regull.ed-N, r, * -
i, ',
f'l I. y
(<
a f ';' eg~i s
/ht
/g q f p, N
discharge through plant
\\
g vent)
(
7 N't *I[
j
/
i, j
t 4}N t,*
4.<
[',
/
N III.
REMARKS i
~g
. (
'g y
x 1.
The condenser air removal exhaust discharges through the plant ventr therefoIe, the monitor for item E.3 2.P h not required.
s J
The existing condenser'azr removal exhaust, monitor stets'.br: requir ementi 'c f fitem'C.2.5.
);. *
-x
/ I
(+
\\
.b
.~ _
} ;\\
s t
i 1
y w.
x
}'
f g\\ '
k f
,h'
...a.f
.g-U,
'M 1
N s
s j
R y
g s
s
- Nf N
j
. p.
B
/
,/
j
+
/
\\
s V,. 5 ' k,.
,'i
/
\\ i.
u
- r (i
1 s
t
(-
s,,
s SNUPPS 2*
TABLE 7A-3, DATA SHEET 12.3 1
\\
/
t v*
1.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE E.3.1.6 Vynt frpp Steam Gen-108 pCi/cc to 103 Ci/cc 2:2 Detection of significant release erator Safety Relief (duration of releases in assessment Valves of Atmospheric seconds and mass of steam Dump Valves per unit time)
II.
SNUPPS DESIGN PROVISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.3.1.6 Vent from Steam Gen-Later RE-Ill N
SP010 N
SP010 N
RRIS erator Safety Relief RE-ll2 N
SP010 N
SP010 N
RRIS Valves or Atmospheric RE-113 N
SP010 N
SP010 N
RRIS Dump Valves RE-ll4 N
SP010 N
SP010 N
RRIS III.
REMARKS 1.
The SNUPPS design monitors the atmospheric dump valve plumes. The atmospheric dump valves are set to open at a lower pres-sure than the safety relief valves and are safety grade, highly reliable components. These valves are provided with position indication. It is assumed that the dump valves will be open and releasing the same concentration and distribution of radio-nuclides any time any of the safety relief valves on the same steam line are open.
2.
Radiation detectors will be po sitioned to view the plume directly from each of the four atmospheric dump valves.
3.
Determination of releases made by the safety valves will be made by reviewing strip chart recording of main steam pressure and flow.
SNUPPS TABLE 7A-3, DATA SiiEE A 12.4 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT..NO.
VARIABLE RANGE CATEGORY PURPOSE E.3.1.7
,All,q$her Identified 10~6 2
Ci/cc to 10 Ci/cc.
28 Detection of significant releases, release Release Points 0-110 percent vent design assessment, long-term surveillance flow 80 (not needed if ef fluent discharges through other monitored plant vents)
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.3.1.7 Auxiliary Feedwater Later RE-385 N
SP010 N
SP010 N
RRIS Pump Turbine Exhaust Monitor III.
REMARKS 1.
A radiation detector monitoring the plume of the auxiliary feedwater turbine exhaust is used to determine the releases.
SNUPPS TABLE 7A-3, DATA StiEET 12.5 1.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE CATEGORY PURPOSE IDENT. NO.
VARIABLE RANGE E.3.2 Part.iculates and llalogens t
1 fa E.3.2.1 All Identified Plant 10 3 pCi/cc to 10 pCi/cc 3aw Detection of significant release, release 2
l0 assessment, long-term surveillance Release Points (except 0 to 110% vent design flow steam generator safety relief valves or atJnospheric steam dump valves and condenser air removal. system exhaust).
Sampling with Onsite.
Analysis capability II.
SNUPPS DESIGN PROVISIONS ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER VARIABLE INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.3.2.1 Unit Vent Monitors RRIS Particulates 102 to 107 pCi/cc GT-RE-21A N
SP056 N
6 lodines 10 ta to 10 pCi/cc Radwaste Building Vent Monitors RRIS Particulates 102 to 107 pCi/cc GH-RE-10 N
SP056 N
~6 lodines 10~88 to 10 pCi/cc II1.
REMARKS 1.
The SNUPPS design meets all of the stated recommendations. Refer to Sections 12.3.4.2 and 18.2.12.2 for further discussions.
Refer to data sheet 12.1 for a discussion of vent flow rate monitoring and wide range gas monitors.
The wide range noble gas monitors described on data sheet 12.1 include the capability to obtain grab samples for both halogens 2.
3.
and particulates. After collection, laboratory samples will be used to quantify releases.
SNUPPS TABLE 7A-3, DATA SHt:ET J3.1 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE P,4 gary Coolant Grab Sample 35 88 Release assessment, verification analysis i
E.6.1 E.6.1.1 Gross Activity 10 Ci/ml to 10 Ci/ml E.6.1.2 Gamma Spectrum (Isotopic Analysis)
E.6.1.3 Boron Content 0 to 6,000 ppm E.6.1.4 Chloride Content 0 to 20 ppm E.6.1.5 Dissolved Hydrogen 0 to 2,000 cc(STP)/kg or Total Gasas E.6.1.6 Dissolved Oxygen
0 to 20 ppm t
E.6.1.7 pH 1 to 13 B.I.3 RCS Soluable Boron 0 - 6,000 ppm 3
Verification Concentration c.1.3 Analysis of Primary 10 pCi/gm to 10 Ci/gm or 35 Detail analysis, accomplishment of Coolant (Gamma Spectrum) TID-14844 source term in mitigation, verification, long-term coolant volume surveillance i
i E.6.6 Containment Air Gamma (isotopic analysis)
Release assessment, verification analysis Spectrum II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.6.1.1 Gross Activity Refer to Section SJ-145 N
SJ-082 N
PASS 18.2.3 E.6.1.2 Gamma Spectrum E.6.1.3 Boron Content
SNUPPS TABLE 7A-3, DATA S!!EET 13.1 (Continued)
II.
SNUPPS DESIGN Pl40 VISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANGE SENSOR /TRANSMI'1"rER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE 9
1e f a Y
E.6.1.4 nloride Content SJ-145 N
SJ-082 N
I Y
E.6.1.5 bissolved Hydrogen SJ-145 N
SJ-082 N
Y E.6.1.6 Dissolved Oxygen SJ-145 N
SJ-082 N
E.6.1.7 pH SJ-145 N
SJ-082 N
Y III.
REMARKS 1.
The SNUPPS design inc-des an inline post-accident sampling system which meets the stated requirements. Refer to Section 18.2.3 for desalls on the system design provisions. Samples are obtained from redundant sample points with class IE isolation valves for the containment atmosphere, the containment sump, and the reactor coolant.
I
SNUPPS TABLE 7A-3, DATA SiiEET 13.2 I.
REGULATORY CUIDE 1.97 TABLE 2 RLcOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE E.6.2 p ump,,,
Grab sample 35.'"
Release assessment, verification analysis E.6.2.1 o Gross Activity 10 pC1/ml to 10 Ci/ml 3
E.6.2.2 o Gamma Spectrum (isotopic analysis) 3 E.6.2.3 o Boron Content 0-6,000 ppm 3
E.6.2.4 o Chloride Content 0-20 ppm 3
E.6.2.5 o pH 1 to 13 3
II.
SNUPPS DESIGN PROVISIONS
(
UARIABLE ERFIS l
IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER l
INDICATOR RECORDER l
IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.6.2 Sump Grab Sample Containment Recir-See data sheet 13.1 culation ECCS Pump Room Sump Not required Auxiliary Building Sump Not required III.
REMARKS 1.
The containment recirculation sumps are sampled by the inline sampling system described on data sheet 13.1 and in Section 18.2.3.
2.
The ECCS room and auxiliary building sumps are provided with class IE level indication and operate as described in Section 9.3.3.
Process and effluent monitors provide indication of any airborne activity in these sumps since they are directly vented to the auxiliary building normal exhaust system.
3.
Sump sampling for the ECCS rooms and auxiliary building is considered unnecessary.
e
~
SNUPPS TABLE 7A-3, DATA S!!EET 13.3 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE C.l.2 Sadioap,tivity Concen-1/2 Technical Specification 1
Detection of breach tratToh' or Radiation limit to 100 times technical Level in Circulating specification, limit R/hr.
Primary Coolant II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARInBLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE C.l.2 Radioactivity Concen-tration (unnecessary variable)
III.
REMARKS 1.
As noted in comments provided by the AIF, this variable is unnecessary, and there is no presently available means of pro-viding this information. Also, there is no apparent need or use for this variable which would require its classification as Category I.
2.
The SNUPPS inline sampling system will provide detailed information on the properties of the RCS fluids following an event.
This system is designed to function after an event; however, it is not a Class IE system.
?
D SNUPPS TABLE 7A-3, DATA SHEET 14.1 REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE 3
To indicate storage volume D.9.1 HighvLevel Radioactive Top to bottom Liquid Tank Level II.
SNUPPS DESIGN PROVISIONS I
ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER VARIABLE INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.9.1 Recycle Holdup Tank Level (Unnecessary variable)
III.
REMARKS It The SNUPPS design precludes the need for this variable. The liquid radwaste system is not required following an event.
i 1.
is located in the radwaste building, and is controlled from the radwaste building control room. System parameters are not l
provided in the main control room.
3 The safety grade letdown system is located within the containment, and the containment isolation system is designed to pre-i clude inadvertent discharge from the containment.
Since the system will only be operated The recycle holdup tank levels are provided in the radwaste building control room.the control room operators may obtain that status of t 3.
from that room, It may be used during recovery, if the personnel. The liquid radwaste system need not be operated during an accident. inadvertent contamination of the radwaste building is pre-radwaste building is habitable. As noted in Section 18.2.2.2, cluded by design and is not postulated.
I l
l l
l l
l
SNUPPS TABLE 7A-3, DATA SHEET 14.2 I.
RECULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE R4pi active Gas Holdup 0-150% design pressure 3
To indicate storage capacity D.9.2 i
A Tank Pressure II.
SNUPPS DESIGN PROVISIONS UARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.9.2 Waste Gas Decay Tank Pressure (unnecessary variable)
III.
REMARKS 1.
Refer to data sheet 14.1 for a discussion of radwaste system status and operction following an event.
2.
The waste gas decay tank pressure are indicated in the radwaste building control room. The range of the indication covers the design pressure ratings of the tanks.
6 I
a O
SNUPPS TABLE 7A-3, DATA SiiEET 15.1 1.
REGULATORY CUIDE I.97 TAliLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE b.10.1 Ey rgency Ventilation Open-closed status 2
To indicate damper status
.,bamper Position II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.10.1 Safety Related Damper Open-closed HIS-XX Y
020 Y
BOP Position 068 019 III.
REMARKS 1.
The safety-related dampers which receive an automatic signal to reposition are provided with Class IE position indication in the control room. The SNUPPS design meets all of the stated recommendations.
O e
SNUPPS TABLE 7A-3, DATA SHEET 16.1 1.
kECULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE FANGE CATEGORY PURPOSE D.11.1
, St4Ws of Standby Power Voltages, currents, 281 To indicate system status Sources important to Safety II.
SNUPPS DESIGN PROVISIONS UARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER 1 DENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.11.1 Status of Standby Power 4160 V Class IE Incoming Current Current 0-2000A CT-NB0109 Y
Y BOP Current 0-2000A CT-NB0lll Y
Y BOP Current 0-2000A CT-NB0212 Y
Y BOP Current 0-2000A CT-NB0209 Y
Y BOP Current 0-1200A CT-PA0201 N
Y BOP 4160 V Class IE Bus Voltage Voltage 0 - 5 KV PT-101/G Y
Y BOP Voltage 0 - 5 KV PT-201/B Y
Y BOP Diesel Gen No. 2 Current 0 - 1500A CT-NE107 Y
Y BOP Voltage 0 - SKV PT-NE107 Y
Y KW 0 - 8MW CT/PT-NE107 Y
Y BOP Vars 0 - 8Mvar CT/PT-NE107 Y
Y BOP Frequency 55 - 65 liertz PT-NE107 Y
Y BOP Diesel Gen No. 1 current 0 - 1500A CT-NE106 Y
Y BOP Voltage 0 - SKV PT-NE106 Y
Y BOP KW 0 - 8MW CT/PT-NE106 Y
Y BOP Vars 0 - 8MVar CT/PT-NE106 Y
Y BOP Frequency 55 - 65 Hertz PT-NE106 Y
Y BOP
SNUPPS TABLE 7A-3, DATA SHEET 16.1 (Continued)
II.
SNUPPS DESIGN PROVISIONS ERFIS VARIABLE IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE 1
i.fa Current to Class IE 480 V System BOP Current 0 - 300A CT-NB0llo Y
Y BOP Current 0 - 300A CT-NB0ll3 Y
Y BOP Current 0 - 300A CT-NB0210 Y
Y BOP Current 0 - 300A CT-NB0213 Y
Y BOP Current 0 - 300A CT-NB0ll7 Y
Y BOP Current 0 - 300A CT-NB0217 Y
Y BOP l
Current 0 - 300A CT-NB0ll6 Y
Y BOP l
Current 0 - 300A CT-NB0216 Y
Y l
Class IE 125 V DC System All Panel 16 i
BOP I
Current
-800 - 800A Shunt Y
Y BOP current 0 - 500A Shunt Y
Y BOP Current
-800 - 800A Shunt Y
Y BOP l
Current 0 - 500A Shunt Y
Y BOP Current
-800 - 800A Shunt Y
Y BOP Current 0 - 500A Shunt Y
Y BOP Current
-800 - 800A Shunt Y
Y BOP Current 0 - 500A Shunt Y
Y BOP Voltage 0- 150V Batt Mon Y
Y BOP Voltage 0 - 150V Batt Mon Y
Y BOP Voltage 0-150V Batt Mon Y
Y BOP Voltage 0- 150V Batt Mon Y
Y 111.
REMARKS 1.
The SNUPPS design meets all of the stated recommendations. All Class IE buses are provided with voltage and current indications.
O C____
SNUPPS TABLE 7A-3, DATA SHEET 16.2 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS
/
VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE D.ll.1
, St4yg of Energy Pressures 2a To indicate system status Sources Important to Safety (hydraulic, pneumatic)
II.
SNUPPS DESIGN PROVISIONS ERFIS UARIABLE IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE D.ll.1 Air Accumulator Tank Pressures BOP AFW Control Valve and 0-800 psig PT-108 N
BOP Secondary Side Steam 0-800 psig PT-110 N
Dump Valve 0-800 psig PT-ll2 N
BOP 0-800 psig PT-114 N
BOP III.
REMARKS 1.
The safety-related air accumulators are described in Section 9.3.1 and shown on Figure 9.3-1 Sheet 5.
The SNUPPS design meets all of the stated requirements.
9 6
e I
SNUPPS TABLE 7A-3, DATA SHEET 17.1 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE E.4.1 Radiation Exposure Range, location, and qualifi-3 Verification of significant release and Meters ! continuous cation criteria to be devel-local magnitudes i indie& tion at fixed oped to satisfy NUREG-0654, locations)
Section II.H.5.b and 6.b for emergency radiological monitoring II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR /TRANSMITT+.R CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE Later 4
SNUPPS TABLE 7A-3, DATA SHEET 17.2 1.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANCE CATEGORY PURPOSE E.4.2 Airborne Radiohalogens 10-8 to 10-8 pCi/cc 8
34 Release assessment; analysis and Particulates (port-
'ablW hampling with on-site analysis capability)
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE See RemarksSection III.
REMARKS 1.
Callaway Health physics air sampling and analysis equipment will be available on site for the monitoring and assessment of airborne radioactivity concentrations. Airborne sampling capabilities for particulate and radioiodine will be provided by low flow air samplers using glass fiber filters and TEDA-impregnated activated charcoal or silver Zeolite cartridges (accident conditions). Analysis of collection media will be performed by germanium gamra ray spectroscopy equipment (multichannel analyzer and HPGe detector with lead shield).
In the control building count room or EOF laboratory, utilization of laboratory gamma spectroscopy equipment will ensure the capability to analyze samples within the detection limits of 10-s pCi to 10-8 pCi for principal gamma emitters.
2.
Wolf Creek Later G
e-
SNUPPS TABLE 7A-3, DATA SHEET 17.3 I.
REGULATORY GUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE E.4.3 Plant and Environs 10'8 to 104 R/hr photons 315 Release assessment; analysis Radiation (portable 10*8 to 10* rads /hr beta 3:s finstrhmentation) radiations and low-energy photons II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT, NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT NO.
CL. IE PANEL CL. IE PANEL CL. IE See RemarksSection III.
REMARKS 1.
Callaway In accordance with Regulatory Guide 1.97 recommendations, portable radiation survey instrumentation with the capability to detect gamma radiation over the range of 10'8 to 10* R/hr will be maintained in the site health physics instrument inventory. The capability to measure beta radiation fields over the range of 10-3 to 10* R/hr will be provided by portable survey instrumentation equipped with beta-sensitive detectors.
2.
Wolf Creek Later e
SNUPPS TABLE 7A-3, DATA SHEET 17.4 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS VARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE E.4.4 Plant and Environs Multichannel gamma-ray 3
Release assessment; analysis Radioactivity (portable spectrometer
- l'frattumentation)
II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANGE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE See RemarksSection III.
REMARKS 1.
Callaway A portable, battery powered, 2,048-channel multichannel analyzer will be used with a 2-inch x 2-inch No. I detector for quantification of radioactivity in plant and environmental radiological samples.
In addition, portable single-channel analyzers with No. I detectors will be available in emergency kits for analysis of selected radioisotopes.
2.
Wolf Creek Later 6
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SNUPPS TABLE 7A-3, DATA SHEET 17.5 I.
REGULATORY CUIDE 1.97 TABLE 2 RECOMMENDATIONS UARIABLE IDENT. NO.
VARIABLE RANGE CATEGORY PURPOSE E.5.1 iWind pirection 0 to 360 degrees (15 degrees 3
Release assessment accuracy with a deflection of 15 degrees). Starting speed 0.45 mps (1.0 mph). Damping ratio between 0.4 and 0.6, distance constant _2 meters.
E.5.2 Wind Speed 0 to 30 mps (67 mph) 10.22 mps 3
Release assessment (0.5 mph) accuracy for wind speeds less than 11 mps (24 sph) with a starting threshold of less than 0.45 mps (1.0 mph)
E.5.3 Estimation of Base on vertical temperature 3
Release assessment Atmospheric Stability difference form primary system,
-5 C to 10 C (-9 F to 18 F) and 10.15 C accuracy per 50-meter intervals (10.3 F accuracy per 164-foot intervals) or analogous range for alternative stability estimates II.
SNUPPS DESIGN PROVISIONS VARIABLE ERFIS IDENT. NO.
VARIABLE RANCE SENSOR / TRANSMITTER CONTROL ROOM COMPUTER INDICATOR RECORDER IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE E.5.1 Wind Direction 0-540 degrees, Later N
RRIS 12 degrees Wind Speed 0-100 mph, Later N
RRIS 1.15 mph O
SNUPPS TABLE 7A-3, DATA SHEET 17.5 (Continued)
SNUPPS DESIGN PROVISIONS 11.
ERFIS COMPUTER CONTROL ROOM SENSOR / TRANSMITTER VARIABLE RANGE RECORDER IDENT. NO.
VARIABLE INDICATOR IDENT. NO.
CL. IE PANEL CL. IE PANEL CL. IE f
1, ta RRIS Estimate of Atmospheric N
Stability
-50 to 50 C, Later Temperature 1.15 C N
RRIS
-4 to +10 C, Later Temperature Difference 2.05 C RRIS N
-50 to 50 C, Later 2.5 C N
RRIS Dew Point 0 -5 inch Later Precipitation 1.5 inch Ground Level III.
REMARKS The SNUPPS design meets all of the stated recommendations. ides inputs to the RRIS via the meteorological monitoring syst to the RRIS computer in
- The meteorological information system (site related) provThe RRIS converts the inputs to digital form at the met tower and tra h
1.
3 the met towers.
The parameters are sampled at a frequency of 1 minute or less by the RRIS.
the computer room.
3.
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SNUPPS NOTES TO TABLE 7A-3 (Sheet 1)
Footnotes to Regulatory Guide 1.97 Table 2 - PWR Variables
^
2Where a variable is listed for more than one purpose, the instrumentation requirements may be integrated and only one measurement provided.
2The maximum value may be revised upward to satisfy ATWS requirements.
3A minimum of four measurements per quadrant is required for operation.
Sufficient number should be installed to account for attrition.
(Replacement instrumentation should meet the 2300 F range provision.)
4 Design pressure is that value corresponding to ASME code values that are obtained at or below code-allowables values for material design stress.
5Sampling or monitoring of radioactive liquids and gases should be performed in a manner that ensures procurement or represen-tative samples.
For gases, the criteria of ANSI N13.1 should be applied.
For liquids, provisions should be made for sampling from well-mixed turbulent zones, and sampling lines should be designed to minimize plateout or deposition.
For safe and convenient sampling, the provisions should include:
a.
Shielding to maintain radiation doses ALARA b.
Sample containers with container-sampling port con-nector compatibility Capability of sampling under primary system pressure c.
and negative pressures d.
Handling and transport capability e.
Prearrangement for analysis and interpretation l
6Minimum of two monitors at widely separated locations.
7 Detectors should respond to gamma radiation photons within any l
energy range from 60 kev to 3 MeV with an energy response accuracy of 120 percent at any specific photon energy from 0.1 MeV to 3 MeV.
Overall system accuracy should be within a factor of two over the entire range.
8Monitors should be capable of detecting and measuring radio-active gaseous effluent concentrations with compositions l
ranging from fresh equilibrium noble gas fission product mixtures to 10-day-old mixtures, with overall system accuracies l
within a factor of two.
Effluent concentrations may be expressed
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SNUPPS NOTES TO TABLE 7A-3 (Sheet 2) in terms of Xe-133 equivalents or in terms of any noble gas nuclide(s).
It is not expected that a single monitoring device will have sufficient range to encompass the entire range provided in this regulatory guide and that multiple components or systems will be needed.
Existing equipment may be used to monitor any portion of the stated range within the equipment i
design rating.
9Provisions should be made to monitor all identified pathways for release of gaseous radioactive materials to the environs in conformance with General Design Criterion 64.
Monitoring of individual effluent streams is only required where such streams are released directly into the environment.
If two or more streams are combined prior to release from a common discharge i
point, monitoring of the combined stream is considered to meet the intent of the regulatory guide, provided such monitoring has a range adequate to measure worst-case releases.
10Design flow is the maximum flow anticipated in normal operation.
j 11 status indication of all standby power ac buses, de buses, inverter output buses, and pneumatic supplies.
12 Effluent monitors for PWR steam safety valve discharges and atmospheric steam dump valve discharges should be capable of approximately linear response to gamma radiation photons with energies from approximately 0.5 MeV to 3 MeV.
Overall system i
accuracy should be within a factor of two.
Calibration sources should fall within the range of approximately 0.5 MeV to 1.5 MeV (e.g., CS-137, Mn-54, Na-22, and Co-60).
Effluent concentrations should be expressed in terms of any gamma-emitting noble gas nuclide with the specified energy range.
I Calculational methods should be provided for estimating con-current releases of low-energy noble gases that cannot be detected or measured by the methods or techniques employed for monitoring.
I taTo provide information regarding release of radioactive halogens and particulates.
Continuous collection of repre-sentative samples followed by onsite laboratory measurements of samples for radiohalogens and particulates.
The design envelope for shielding, handling, and analytical purposes should assume 30 minutes of integrated sampling time at sampler design flow, an average concentration of 102 Ci/cc of particulate radio-iodines and particulates other than radioiodines, and an average gamma photon energy of 0.5 MeV per disintegration.
14For estimating release rates of radioactive materials released during an accident.
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- " - - - - ' - - - - - " ' " ~ ~ " ^
~ ~ - ~ ' - - *
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I SNUPPS NOTES TO TABLE 7A-3 (Sheet 3) 1S To monitor radiation and airborne radioactivity concentrations in many areas throughout the facility and the site environs where it is impractical to install stationary monitors capable of covering both normal and accident levels, r
16Guidance on meteorological measurements is being developed in a Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants."
17 The time for taking and analyzing samples should be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time the decision is made to sample, except for chloride which should be within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
18 An installed capability should be provided for obtaining containment sump, ECCS pump room sumps, and other similar auxiliary building sump liquid samples.
19 Applies only to primary coolant, not to sump.
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