ML20065N462
| ML20065N462 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/04/1990 |
| From: | Poore G, Rubis P, Uhrinek J FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20065N460 | List: |
| References | |
| NUDOCS 9012120142 | |
| Download: ML20065N462 (96) | |
Text
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l IMPROVED DESIGN CONTROL L'0CUMENTATION FOR CRYSTAL RIVER UNIT 3 DESIGN BASIS FOR POST- ACCIDENT MONITORING INSTRUMENTAT10N The following contains design basis information pertaining to the Plant as of September 28,1990(DateofRecord).
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(/ l l0 9 $0 L bOC OO O2 P PDC These signatures apply to pages 1 through 91 , Revision 1 .
DESIGN BASIS DOCUMENT _Page i of V Crystal River Unit 3- ;
$YSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A REVISION HISTORY l
Revision /Date Description ;
O / 9/5/86 Initial issue, 1 / 9/28/90 This revision is the result of modifications and changes i made through Refuel 7 It revises all RG 1.97 variables to bring them into 911ance with the RG 1.97, Rev. 3 Compliance Table to ag, 'vious commitments to the NRC contained in FPC lewors 3F0388-18, dated 3/21/88; 3F0189-ll, dated 1/25/89; 3F1289-12, dated 12/15/89; 3F0190-06, dated 1/10/90; 3F0890-01, dated 8/2/90. It incorporates DBDTC #101 along with minor comments made during the review cycle. This revision also deletes DBDTC -
No. 66 and 83, as they were incorporated into DBDTC #101.
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DESIGN BASIS DOCUMENT Page 11 of y 9%
SY5tfM NAME W Crystal River Unit 3 SYSTEM CODE 3
POST-ACCIDENT MONITORING IASTRUMENTATION N/A DESIGN BASIS INDEX FOR POST-ACCIDENT MONITORING INSTRUMENTATION SECTION TITLE IEE
SUMMARY
SYSTEM DESCRIPTION ......................... 1 DESIGN BASIS FOR POST-ACCIDENT MONITORING INSTRUMENTATION . . . . . . . . . . S Neutron Flux ............................. 5 Control Rod Position ......................... 6 RCS Soluble Boron Content . . . . . . . . . . . . . . ........ 7 RCS Hot Leg Water Temperature . . . . . . . . . . . . . . . . . . . . . 8 RCS Cold Leg Water Temperature .................... 9 RCS Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Reactor Coolant Inventory . . . . . . . . . . . . . . . . . . . . . . 12 Degrees of Subcool ing . . . . . . . . . . . . . . . . . . . . . . . . 13 Containment Sump Water Level (Sump) . . . . . . . . . . . . . . . . . 14 Containment Sump Water Level (Flood) .................IS Containment Isola
- ion Valves Position (Manual) . . . . . . . . . . . 16 Containment Isolation Valves Position (Automatic) . . . . . . . . . . 17 Core Exit Temperature (Backup) ...................18 Core Exit Temperature (Primary) . . . . . . . . . . . . . . . . . . . 20 i RCS Radioactivity Concentration . . . . . . . . . . . . . . . . . . . 22 Containment Hydrogen Concentration .................23 Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . 24 Decay Heat flow (LPI Flow) .....................25 1 94 RET: Optt RESP' Nuc. Ops Eng 900 307
DESIGN BASIS DOCUMENT Page lii of y Crystal River Unit 3 3 SYST[M NAMg $YSf f M CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A SECTION TITLE PAGE DHHE_0utlet Temperature . . . . . . . . . . . . . . . . . . . . . . . 26 Core Flood Tank Level . . . . . . . . . . . . . . . . . . . . . . . . 27 Core Flood Tank Pressure ......................28 Core Flood Tank isolation Valve Position ..............29 Boric Acid Charging Flow ......................30 HPI Flow (0-500 gpm) ........................31 HPI Flow (0-200 gpm) ........................32 Borated Water Storage Tank Level ..................33 Reactor Cooiant Pump Status . . . . . . . . . . . . . . . . . . . . . 35 RC System Safety Relief Valve Flow ................36 Pressurizer Level . . . . . . . . . . . . . . . . . . . . . . . . . . 37 Pressurizer Heater Status . . . . . . . . . . . . . . . . . . . . . . 39 RC Drain Tank Level . . . . . . . . . . . . . . . . . . . . . . . . . 40 RC Drain Tank Temperature . . . . . . . . . . . . . . . . . . . . ... 41 RC Drain Tank Pressure .......................42 Steam Generator Level . . . . . . . . . . . . . . . . . . . . . . . . 43 Steam Generator Pressure . . . . . . . . . . . . . . . . . . . . . . 44 i
L Main Steam Safety Valve Position ..................45 l
Main Feedwater Flow . . . . . . . . . . . . . -. . . . . . . . . . . . 46 Emergency Feedwater Flow ......................47 1
Emergency Feedwater' Tank Level . . . . . . . . . . ... . . . . . . . 48 Containment Spray F1ow .......................49 RB Fan Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . 50 l'68 RET: Opti RESP, Nuc. Ops. Eng 900 M7 l:
DESIGN BASIS DOCUMENT Page iv of y Om SYSTEM NAME
%we.r Crystal River Unit 3 SYSTEM COOL 3
POST-ACCIDENT MONITORING INSTRUMENTATION N/A SECTION TITLE IME Containment Atmosphere Temperature . . . . . . . . . . . . . . . . . 52 Containment Sump Water Temperature . . . . . . . . . . . . . . . . . 53 Makeup Flow in ...........................55 Letdown Flow-Out . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Makeup Tank Level . . . . . . . . . . . . . . . . . . . . . . . . . . 57 Component Cooling Water Temperature to ESF Systems . . . . . . . . . 59 Component Cooling Water Flow to ESF Systems (System Status) . . . . . 60 High-level Radioactive Liquid Tank Level . . . . . . . . . . . . . . 61 Radioactive Gas Hold-Up Tank Pressure . . . . . . . . . . . . . . . . 62 Emergency Ventilation Damper Position Indication . . . . . . . . . . 63 Status of Standby Power . . . . . . . . . . . . . . . . . . . . . . . 64 Containment Area Radiation - High Range . . . . . . . ........65 Radiation Exposure Rate Inside Buildings or Areas Where Access is Required to Service Equipment important to Safety . . . . . . . 66 Containment or Purge Effluent, Noble Gas ..............68 Reactor Shield Building Annulus . . . . . . . . . . . . . . . . . . . 69 Auxiliary Building Noble Gas ....................70 Condenser Air Removal System Exhaust ..... ..........71 Vent from SG Safety Valves or ADVs .................72 All Plant Releaso Point - Particulates and Halogens . . . . . . . . . 73 Airborne Radio Halogens and Particulates . . . . . . . . . . . . . . 74 Plant and Environs Radiation ....................75 Plant and Environs Radioactivity . . . . . . . . . . . . . . . . . . 76 l
1 88 RET: Opti RESP: Nuc. Ops. Eag 900 397
DESIGN BASIS DOCUMENT Page V of V Crystal River Unit 3 3 Sygitu NAME SYSitM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A SECTION TITLE E831 Wind Direction . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 Wind Speed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 Estimation of Atmospheric Stability . . . . . . . . . . . . . . . . . 79 Primary Coolant and Sump - Gross Activity . . . . . -. - . . . . . . . . 80 Primary Coolant and Sump - Gamma Spectrum . . . . . . . . . . . . . . 81 Primary Coolant and Sump - Boron Content . . . . . . . . . . . .. ._. 82 Primary Coolant and Sump - Chlot ie Content . . . . . . . . . . . . . 83 Primary Coolant and Sump - Disrolved H2 or Total Gas . . . . . . . . 84 Primary Coolant and Sump - Dissolved Oxygen . . . . . . . . . . . . . 85 Primary Cool ant and Sump - pH . . . . . . . . . . . . . . . . . . . . 86 Containment Air Hydrogen Content . . .-, . . . . . . . . . . . . . . 87 Containment Air - Oxygen Content . . . . . . . . . . . . . . . . . . 88 Containment Air - Gamma Spectrum . . . . . . . . . . . . . . . . . . 90 SOURCE DOCUMENT REFERENCE , . . . . . . . . . . . . . . . . . . . . . . . . 91 i
1;44 REY Optl. RESP: Nuc Oos. En0 900 397
DESIGN BASIS DOCUMENT 1 of 91 9m Page Nmer Crystal River Unit 3 i SYSTIM NAMg 6YSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A
SUMMARY
SYSTEM DESCRIPTION The post-accident monitoring instrumentation is comprised of instrumentation and displays to assess plant and environs conditions during and following an accident.
Certain displays were added and/or upgraded in accordance with NUREG-0737 as TMI Lessons Learned Recommendations. Subsequently USNRC Regulatory Guide (RG) 1.97 of post-accident monitors was greatly expanded when supplement 1 to NUREG 0737 -
" Requirements for Emergency Response Capability (Generic letter 82-33)" was issued (12/17/82). The Crystal River Unit 3 degree of compliance is contained in the CR3 RG 1.97 Position Report submitted to the NRC August 21, 1984 on the basis of the events for which CR3 was licensed and a revised report was submitted to the NRC March 21, 1988. Note, that this section of the Design Basis Document, (Section 5-
- 11) replaces the Compliance Table previously submitted to the NRC. Rev. I will be submitted to the NRC no later than December of 1990, and will reflect our RG 1.97 position including Refuel 7 modifications.
Variables are grouped into five types depending on the importance of information as defined by RG 1.97, Rev. 3 and in addition each variable is assigned to one of three categories as a function of the safety importance of the measurernent as follows:
Type A - Those variables that provide primary information* needed to permit the control room operator to take the specified manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety function for design basis accident events. They are plant specific and were selected on the basis of the CR3 Emergency Operating Procedures.
Type B - Those variables that provide information to indicate wnether plant safety functions are being accomplished, defined as reactivity control, core cooling, primary coolant integrity, and containment integrity.
Type C - Those variables that indicate the potential for being breached or the actual breach of barriers to fission product release, including fuel cladding, primary coolant pressure boundary, and containment.
Type D - Those variables that provide information to indicate operation of individual safety systems and other systems important to safety.
Type E - Those variables that provide information for use in determining the magnitude of release of radioactive materials and for use in assessing such releases.
- Primary information is information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures.
10A RET: Opv RESP: Nac Oct Eng %C M7
Page 2 of91 DESIGN BASIS DOCUMENT " ' * "
Crystal River Unit 3 3 SYSTEM CODE SY$YEM NAME POST-ACCIDENT MONITORING INSTRUMENTATION N/A Category 1 - These measurements are key variables with the most stringent requirements.
Category 2 - These variables have less stringent requirements and generally apply to the instruments designated for indicating system operating status.
Category 3 - Is intended to provide requirements to ensure that high quality off the-shelf instruments are used for backup and diagnostic instrumentation.
Areas of qualification including range, environmental qualification, seismic qualification, quality assurance, redundancy, power source, display, schedule, position, source and reason are listed and explained below.
A. RANGE The ranges listed in the Compliance Table are the actual measurement range of the variable at CR3. If the range varies from that stated in the Regulatory Guide justification is supplied for the existing range. In some instances, the Regulatory Guide states the range in terms of a percentage of the design, in these cases, the design basis is listed next to the range in parenth'esis.
B. ENVIRONMENTAL QUAllflCATION A response -of "Yes" on the Compliance Table indicates that the currently installed equipment meets the requirements of IE Bulletin 79-01B and 10CFR50.49. This determination was based on either having actual environmental qualification documentation available or documentation on similar equipment available.
For Category 2 variables, FPC considers existing installed instrumentation located in a mild environment to be adequate for Regulatory Guide 1.97.
Category 2 variables. FPC also considers portions of the Non-nuclear Instrumentation (NNI) adequate for Category 2 variables and has the following position:
For strings which include hardware located in a harsh environment, portions in the harsh environment (sensors, cabling, terminations) should be qualified for the accident temperature, pressure, humidity, radiation and chemical environment. Hardware located in a mild environment (cabling, terminations, processing modules, power supplies, indicators and recorders) is adequate as currently installed.
i RET; Optt PESP: Nuc. Opa Eng gr4 397 1:48
DESIGN BASIS DOCUMENT Page 3 of 91 "S' "
Crystal River Unit 3 )
system CODE SYSTEM HAME POST ACCIDENT MONITORING INSTRUMENTATION N/A b The basis for this position is as follows:
The Category 2 qualification requirements of Regulatory Guide 1.97, Rev. 3, include no specific provision for seismic qualification. We interpret this to mean that environmental qualification only is M required. Since 10CFR50.49 does not require environmental qualification for equipment located in a mild environment, only those components listed in a harsh environment need be qualified.
The currently installed NNI equipment was not supplied as safety related equipment but is comparable in quality and reliability to existing safety related equipment. In fact, some of the NNI electronic modules are identical to those qualified and supplied for these safety related systems, Operating experience with the NNI indicates that this instrumentation can reasonably be expected to be operable for accident monitoring.
Category 2 instrumentation is not required to be seismically qualified, redundant, physically and electrically separated nor powered from a lE source. The existing NNI hardware located in a mild environment is consistent with the Category 2 criteria and no substantial improvement in reliability or safety would be expected if this equipment were replaced with new, qualified hardware.
Other responses are self-explanatory.
C. SEISMIC QUALIFICATION A . response of "Yes" on the Compliance Table indicates that the entire instrument string is seismically qualified in accordance with Regulatory Guide 1.100. Other responses are self-explanatory.
D. QUALITY ASSURANCE A response of "Yes" on the Compliance Table indicates that Quality assurance requirements meeting CR3's licensirg commitments as documented in the FSAR Section 1.6 were applied to at least the safety related portions of the instrument string. All other responses are self-explanatory.
E. REDUNDANCY A response of "Yes" indicates that redundant channels are available up to and including any isolation device and that the channels are both electrically independent and physically separate from each other, in accordance with IEEE Standard 279-1971, and meet single f ailure criteria.
All other responses are self-explanatory.
1 88 RET: Optt RESP: Nuc. Ops Eng 900 39?
DESIGN BASIS DOCUMENT Page 4 of 91 Crystal River Unit 3 i
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SYSTEM N AMg SYSTEM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A F. POWER SOURCE The power source for the instrument string listed n the Compliance Table is in compliance with thi- Regulatory Guide requirements unless otherwise noted.
G. DISPLAY Under this heading on the Compliance Table is how the variable is indicated and/or recorded in the Control Room (CR), EFIC Room, etc.
If the variable is available on demand in the Technical Support Center (TSC) or the Emergency Operating Facility (E0F) it will be so stated.
H. SCHEDULE This area indicates when the upgrades (if required) will be complete.
- 1. POSITION This area explains whether the variable complies, is not required, or explains when it will comply.
J. SOURCE This area indicates the source documents, which can be found on page 91, for each of the variables.
K. REASON in this area will be Florida Power Corporation's position on a particular variable which will include any justifications which are required along with any comments or clarifying remarks wnich may be needed.
If the justification presented is justification developed by the Babcock &
Wilcox Owners Group (BWOG) Regulatory Guide 1.97 Task Force, it will be so stated.
1/s4 RET: Opt! RESP: Nuc Ops Eng 94 397
DESIGN BASIS DOCUMENT Page 5 of 91_
@m BYS1EM N AME
%wer Crystal River Unit 3 SYSTEM CODE
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POST-ACCIDENT MONITORING INSTRUMENTATION N/A DESIGN BASIS FOR POST-ACCIDENT MONITORING INSTRUMENTATION PARAMETER:
VARIABLE: NEUTRON FLUX TAG NO.: N1-14-nil, N1-15-Nil, NI-15-NIR REF DWG: 205-042, NI-01 Type and Category - A, B, 1 Range - 10'" to 100%, (SR, IR, PR)
Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 channels - PR 2 channels - SR 2 channels - IR Power Source - IE Display - Indicated and Recorded in CR On Demand in E0F & TSC RG 1.97 Position - Complies SOURCE:
0, 5, 6, 7, 18, 21 REASON:
Neutron flux is the measure of reactor power required to monitor reactivity control of the ICS and RPS.
i l
U88 RET;0011 Ri$P: Nuc Ops Eng 9tX) 397
DESIGN BASIS DOCUMENT Paoe 6 of 91 m "' " "
aower Crystal River Unit 3 i BYSitM NAME SYsitM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTROL ROD POSITION TAG N0 : DR-70-KI, DR-71-KI, DR-72-KI, DR-73-KI REF DWG: 210-074 Type and Category - B, 3 Range 100%, Full-ia/ Full-out Lights, Average Group Position Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A - 2 Channels Power Source - Reg Inst, Bus VBDP-1 & VBOP-2 Display - Indicated in CR Average Group Position On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
Control rod position provides backup information that reactivity control has been accomplished by the ICS and RPS.
i t <88 RET- Octi PESP Nuc Ops Eng 900 397
DESIGN BASIS DOCUMENT Page 7 of 91 72ower Crystal River Unit 3 3 SY5f EM NAME SYS1f M CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RCS SOLUBLE BORON CONTENT TAG NO.: CA-56-CE REF DWG: 302-700 Type and Category - B,3 Range 6000 ppm Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - lE/DG Display - Lab Only RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, 12, REASON:
The manual sampling and laboratory analysis is sufficient to meet the intent of Regulatory Guide 1.97, Rev. 03. This is based on the fact that the loss of negative reactivity due to xenon decay is sufficiently slow that the Control Room ooerator need not know instantaneously or continuously what the boron concentration is in the RCS. Also, Section 11.B.3 of NUREG-0737 requires that capability exists to sample and analyze the reactor coolant in a post-accident environment.
1;M RET: Optt. RESP: Nuc Opa Eag gr.o 397
DESIGN BASIS DOCUMENT Page 8 of 91 O,m W Crystal River Unit 3
" S*"'
SY$ tim CODE 3
SYSTEM NAME POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RCS HOT LEG WATER TEMPERATURE TAG NO.: RC-4A T14 1, RC 4B-TIP,1 REF DWG: 205-047, RC-04, RC-10, RC-12A, RC-13A Type and Category - A, B, 1 Range - 120 - 920*F Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - lE/0G Display - Indicated and Recorded in CR On Demand in TSC & E0F RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, 13, 19 REASON:
RCS Hot Leg Water Temperature is a key variable required to monitor the core cooling safety functinn, to verify natural circulation along with core exit temperatures, and to verify primary to secondary loop coupling along with steam generator pressure.
RCS Hot Leg Temperature not required below 280'F. Plant in cold shutdown below 200*F. RCS Cold leg Temperature range extends down to 50*F.
12 RET' Opti RESE tiec. Ops Eno 90 3d?
DESIGN BASIS DOCUMENT Page 9 of 91 9%
6YST[M NAME Nnver Crystal River Unit 3 POST-ACCIDENT MONITORING INSTRUMENTATION SYSTEM CODE N/A 1
PARAMETER:
VARIABLE: RCS COLD LEG WATER TEMPERATURE TAG NO.: RC-5A-T13, RC-5B-T14 REF DWG: 205 047, RC-04 Type and Category - B, 3 Range - 50*F - 650'F (Ind)
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy N/A - 2 Channels Power Source - IE/DG Display - Indicated in CR On Demand in TSC & E0F RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11 REASON:
Reg. Guide 1.97 lists Cold leg Water Temperature as a Category 1 (key) variable and Core Exit Temperature as a Category 3 (backup) variable for the core cooling function. Cold Leg Temperature indication may not in all cases provide valid information on the status of core cooling. Since it is located in the RCS loops and not the reactor vessel, there must be either forced or natural circulation flow through the steam generators for indications to be representative of actual core conditions. Also, due to the proximity of the cold leg RTDs to the HPI nozzles, HPI flow may significantly affect the cold leg temperature indication particularly in the absence of forced RCS flow. Incore temperature monitors provide a more direct indication of core cooling independent of whether or not there exists coolant flow through the loops. RCS Cold Leg Water Temperature is a backup to RCS Hot leg and Core Exit Temperatures.
I t.se RET; Octi f ESP. Nuc Ops Eng 9CO 397
DESIGN BASIS DOCUMENT. Pago 10 of 91 Crystal River Unit 3 3 SYSTEM NAME SysitM CODE POST ACCIDENT HONITORING INSTRUMENTATION N/A-The key variables for monitoring the core cooling plant safety function are RCS Hot Leg Water Temperature, Core Exit Temperature, and Steam Generator Pressure (see Discussion Section for RCS Hot leg Water Temperature). RCS Cold Leg Water Temperature is a backup temperature monitor to the RCS Hot Leg Water Temperature and Core Exit Temperature.
For these reasons, core exit temperature and RCS Hot Leg are the key variables for monitoring core cooling and are qualified to Category 1 requirements while RCS Cold Leg- Temperature serves as a backup . variable and is- qualified to Category 3 requirements accordingly.
The CR3 range of 50' to 650*F is based on providing the capability of the RCS Cold Leg Water Temperature instrumentation to measure a value greater than the saturation temperature for the steam generators, which is approximately 500*F (based on 1050 psig design pressure). 650'F for the high end of the range provides 15% excess measurement capability and is approximately 110% of the design temperature of 600*F, The low end of the range, 50'F, allows for measurement of the variable during conditions where the DHRS or LP! system is not in use or available and the steam generators are removing decay heat, s
-14 AET: Opu RESP. Nuc Ops Eng 900 397
Page 11 of 91 DESIGN BASIS DOCUMENT 9m SY6itM NAME Nmer Crystal River Unit 3 POST-ACCIDENT MONITORING INSTRUMENTATION SYSTEM CODE 3
N/A PARAMETER:
VARIABLE: RCS PRESSURE TAG NO.: RC-158-P12, RC-158-PIR, RC-159-P12 REF DWG: 205-047, RC-02 Type and Category - A, B, C, 1 Range 3000 psig Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - lE/DG Display - Indicated and Recorded in CR On Demand in TSC & EOF RG 1.97 Position - Complies
$1URCE:
0, 5, 12, 13, 19, REASON:
RCS pressure is a key variable required to monitor reactor shutdown in event of a reactor coolant upset and to monitor reactor coolant integrity and core cooling capability, i 80 RET: Optt RESP: Nuc. Ops Eng 900 391
Page 12 of 91 m DESIGN BASIS DOCUMENT ***"
Nmer Crystal River Unit 3 3 SYST(M NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: REACTOR COOLANT INVENTORY TAG N0.: RC-163A LR1, RC-163B LR1, RC-164A-LR1, RC-164B-LR1, RC-169-XR1 REF DWG: 205-047, RC-12, RC-12A, RC-13, RC-13A Type and Category 8, 1 - RV. LVL and Hpt Leg LVL B, 2 - Void Fraction B, 3 - RCS Cold leg Temperature Feeding Void Fraction3 Range - Bottom of Hot leg to Top of Hot leg Bottom of Hot leg to Top of Vessel Environmental Qualification - Yes Seismic Qualification - Yes (Category 1 Variable Only)
Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - lE (Category 1 Variable Only)
Display - Indicated and Recorded in CR RG 1.97 Position - Complies SOURCE:
0, 5, 31 KEASON:
RCS hot leg level is required to monitor, along with RC pump monitors, that no voids exist in the reactor coolant system.
' This tag number is associated with but isolated from the coolant inventory variable and is, therefore, identified as a Category 2 variable.
2 When the pumps are running, the void fraction indicators provide inventory level trend measurement.
3 RCS Cold leg temperature is an input to void fraction 1*d RET. Opti RESP: NvC Ops Eng WA 3W
Page 13 of 91 DESIGN BASIS DOCUMENT " ' ' "
Crystal River Unit 3 3 SYETEM CODE 6YSitM NAME POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: DEGREES OF SUBC00 LING TAG N0.: RC-4 T14, RC-4-T15 REF DWG: 205-047, RC-04, RC-10 and D8034033, Sh. 2 Type and Category - B, 2 - RCS Hot leg Water Temperature & RCS Pressure B, 3 - RCS Cold leg Water Temperature & Incore Monitors Range - 1 658'F Environmental Qualification - Yes (Category 2 Variable Only)
Seismic Qualification - N/A Quality Assurance - Yes (Category 2 Variable Only)
Redundancy - N/A - 1 Channel per loop Power Source - UPS/DG Display - Indicated in CR RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
Two subcooling margin monitors are located on the PSA section of the main control board. These instruments continuously display saturation temperature for each loop. In addition to displaying saturation temperature, each instrument can display RC pressure and core exit temperature on demand. Two separate groups of 6 CETs each have been selected to provide representative temperatures from each core quadrant and the control region. The temperature displayed on demand is the highest of the six CETs in each group and displays over a range of 0*F to 1,023*F, well above saturation temperatures.
1
, pa PET. Opti r%P. Nuc Ops Eng 900 397
Page 14 of 91
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DESIGN BASIS DOCUMENT " ' ' "
Crystal River Unit 3 i BYSTEM NAME 6VSitM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT SVMP WATER LEVEL (SUMP)
TAG N0.: WC-301-LI, WD-302-L1, WD-301-LR, WD-302-LR REF DWG: 205-060, WD-01 Type and Category - B, C, 2 Range 10 ft.
Environmental Qualification - Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy - N/A - 2 Channels Power Source - UPS/DG with IE Standby Display - Indicated in CR On Demand in E0F and TSC REC in EFIC Room RG 1.97 Position - Complies SOURCE:
0, 5, 22 REASON:-
Containment sump level is an important method of leak detection inside containment, including the reactor coolant system.
Location of indicators and recorder satisfies NUREG-0737, Item II.F.1.5.
N RET: Opti RE5P; tauc Ops Eng 900 397
DESIGN BASIS DOCUMENT Pace 15 of 91 m ""'" "
Crystal River Unit 3 ;
$YETEM NAME SY5 f EM CODf POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT SUMP WATER LEVEL (FLOOD)
TAG NO.: WD-303-L1, WD 304-LI, WD-303-l", WD-304-LR REF DWG: 205-060, WD 03 Type and Category - A, B, C, 1 Range 10 ft. (Above Sump)
Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - IE Display - Indiuted in CR Record 0d in EFIC Room On Demard in E0F & TSC RG 1.97 Position - Complies SOURCE:
0, 4, 5, 22 REAF3N:
Containment level is an important method of detection and inventory of a major fluid loss, including a LOCA.
Location of indicators and recorder satisfies NUREG-0737, Item II.F.1.5.
t 88 RET: Opti HE3P; Nuc Oos Eng 900 397
DESIGN BASIS DOCUMENT Page 16 of 91 Crystal River Unit 3 3
SYSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING-INSTRUMENTATION N/A PARAME1ER:
VARIABLE: CONTAINMENT ISOLATION VALVES POSITION (MANUAL)
TAG N0.: N/A REF DWG: N/A Type and Category - B, 1 Range - N/A Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A -
F.% r Source - N/A Display - N/A RG 1.97 Position - N/A
, SOURCE:
0, 5, 10, 11, 23 REASON:
Containment isolation valve position is required to ensure containment integrity in event of a LOCA.
Locked closed manual valves do not require position indication.
1 68 - Rf T. Optt RESP. Nuc. Ops. Eng 900 397
Page 17 of 91 DESIGN BASIS DOCUMENT O,m M Crystal River Unit 3 SYSTEM CODE 3
$YSTEM NAME POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT ISOLATION VALVES POSITION (AUT0iMTIC)
TAG NO.: SEE ES LIGHT MATRIX REF DWG: 201-162 Type and Category - B, 1 Range - Open/ Closed Lights (via Light Matrix)
Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Redundant indicalion per valve not intended by RG 1.97, since CR3 has redundant isolation barriers for all fluid penetrations.
Power Source - 1E Display - Indicated in CR RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, 13, 19 REASON:
Containment isolation vshe position is required to ensure containment integrity in event of a LOCA, l
1M REY: Opti RESP; % c. Ops.Eng. 900 397
DESIGN BASIS DOCUMENT Page 18 of 91 Crystal River Unit 3 3 SYSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A ;
PARAMETER:
VARIABLE: CORE EXIT TEMPERATURE (BACKUP)
TAG NO.: RC-171-TR, RC-172-TR, RC-173-TR REF DWG: 205-047, RC-07, RC-08, RC-09 Type and-Category - A, 1 Range _- 0- 2500*F
-Environmental Qualification - Yes l Seismic Qualification - Yes Quality. Assurance - Yes Redundancy - Yes Power Source - UPS/DG ,
1 Display. - 16 CETs Recorded in CR !
RG 1.97 Position - Complies l SOURCE:
.0, 5, 31 i
REASON:
Core exit temperatures along with RCS Hot Leg Temperature to verify natural circulation of reactor coolant, and to detect potential breach of fuel cladding.
Ref: 'The NRC's evaluation of CR3 is response to NUREG-0737, Item II.F.2, Docket No. 50-302, dated 9/6/83.
Core Exit Temperature measurement displays include a primary and backup display arrangement.
The primary display consists of 52 Core Exit Thermocouples (CETs) recorded on demand in the Control Room over a range of 0-2500*F. (Twelve- (12) are also recorded on demand in the TSC and E0F over a range-of 0-2000*F.)
The backup display consists of 16 temperature measurements from 16 CETs - 4 from each core quadrant. The system is part of the ICC detection system and is Class 1E. Each of the 16 Core Exit Temperature measurements is continuously recorded-in the CR on three separate recorders over a range of 0-2500*F.
1-ee RET: Opit RESP: Nuc Ops. Eng 900 397 l
-e m DESIGN BASIS DOCUMENT . Page 19 of 91 Crystal River Unit 3 3
$YSTEM NAMt $YSTEM CODF POST-ACCIDENT MONITORING INSTRUMENTATION N/A ,
Primary and backup displays are electrically independent, energized from independent power sources, and physically separated, up to and including the i sol ators. The primary display is not Class lE but is energized from a battery backed, high-reliability uninterruptable power supply, which is backed up by the '
diesel generator.
l'6a RET. Gott RESP; Nuc Oos Eng gr4 317
Page 20 of 91 m DESIGN BASIS DOCUMENT ""'"
aower Crystal River Unit 3 3 BYSTIM NAug BYSTEM CODE POST-ACCIDENT MONITORit4G INSTRUMENTATION N/A PARAMETER:
VARIABLE: CORE EXIT TEMPERATURE (PRIMARY)
TAG NO.: IM-lH, 2L, 3F, 3M, 4E, 50, SH, SK, 50, 6G, CP, 7B, 7E, 7M, 7R, 88, 8F, 8H, 8N, 9C, 9G, 9M, 9N, 100, 10R, llE, llK, llL, 12F, 12K, 120, 130, 13H, 13F, 140, 14M,-TE REF DWG: N/A Type and Category - B, C, 3 Range - 0' - 2500'F Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - UPS/DG Display - 52 CETs Indicated in CR 16 Recorded On Demand in CR 12 On Demand in TSC & E0F RG 1.97 Position - Complies SOURCE:
0, 5, 31 REASON:
Core exit temperatures along with RCS Hot Leg Temperature to verify natural circulation of reactor coolant, ard to detect potential breach of fuel cladding.
Ref: The NRC's evaluation of CR3 is response to NUREG-0737, item II.F.2, Docket No. 50-302, dated 9/6/83.
Core Exit Temperature measurement displays include a primary and backup display arrangement.
The primary display consists of 52 Core Exit Thermocouples (CETs) recorded on demand in the Control Room over a range of 0 2500'F. (Twelve (12) are also recorded on demand in the TSC and E0F over a range of 0-2000*F.)
I 1
188 RET: Opn RE$P: Nuc Ops Eng 900 397
Page 21 of 91 DESIGN BASIS DOCUMENT n 5, 9m ...
Nmer Crystal River Unit 3 POST ACCIDENT MONITORING INSTRUMENTATION osuu coni 3
N/A The backup display consists of 16 temperature measurements from 16 CETs - 4 from each core quadrant. The system is part of the ICC detection system and is Class IE. Each of the 16 Core Exit Temperature measurements is continucusly recorded in the CR on three separate recorders over a range of 0 2500*f.
Primary and backup displays are electrically independent, energized from independent power sources, and physically separated, up to and including the isolators. The primary display is not Class lE but is energized from a battery backed, high reliability uninterruptible power supply, which is backed up by the diesel generator.
I A8 Ril: 0011 AESP.Nuc 'pe Eng EC 39?
d DESIGN BASIS DOCUMENT Page 22 of 91 Crystal River Unit 3 1 Sv$ftW NAME SYS11w CODE POST ACCIDENT HONITORING INSTRUMENTATION N/A i
tk '7ER:
VARIABLE: RCS RADIOACTIVITY CONCENTRATION
. TAG NO.: N/A '
REF DWG: N/A Type and Category C, 3 Range 10 2 to 10'3 ci/gm Environmental Qulification N/A Seismic Qualification - P'A ,
Quality Assurance - N/A Redundancy N/A Power Source - IE L Display - Indicated and Recorded in LAB RG.I.97 Position - Complies SOURCE:
0, 5, 10, 11, 12 REASON .
The following position is a justification developed by the BWOG Reg. Guide 1.97 Task Force.
Currently, no instrumentation exists to adequately meas are this variable on line. Existing instrumentation, letdown line radiation mor itors, can be used to ,
provide indication of fuel failure during normal operatiori. However, since the letdown line is isolated during serious accidents requiring containment isolation, it will not be available for long term measurement.Section II.C.3 of NVREG 0737 requires that capability exist at each plant to sample the RCS to assess the magnitude of fuel failures during post accident conditions. As such, this measurement should be the primary determinaiit of fuel-failure during normal operation and post accident. The letdown line radiation monitor should be used as the iritiator for sampling during normal operation because state of-the-art equipment is unavailable and the primary means of monitoring this variable must therefore be by sampling and analysis.
l l
, '00 PET: 004. RESP: Nut. Ops tag ikS 397 l
E.-_._.._. _ _ _ - _ _ _ _ - - _ , . - _ . ~ _ , _ _ . . , _ _ . _ . _ _ , .. . _ . --
DESIGN BASIS DOCUMENT Page 23 of 91 9...
$YEftsdNAuf
.. Crystal River Unit 3 ""$**
SY$tLM CODE 1
POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT HYDROGEN CONCENTRATION TAG NO.: WS-10 CR, WS-11-CR l REF DWG: 205 062, WS 01, WS-02 Type and Category - C, I Range 10%'
Environmental Qualification Yes i Seismic Qualification - Yes Quality Assurance Yes Redundancy - Yes - 2 Chai...els Power Source - lE Display - Indicated and Recorded in Efl0 Room RG 1.97 Position - Complies SOURCE:
0, 5, 22 REASON:
Containment hydrogen monitoring is a' key variable used to detect a potential breach of containment resulting from fuel failure.
l.
l Location of indicators and records satisfies NUREG-0737, item Il.F.1.6.
I e., e or m,. ~, ... c, --
V
A1 DESIGN BASIS DOCUMENT Page 24 of 91 9.... .
SY5ftW hAMg Crystal River Unit 3 ""
SYSTEM CODE 1 _
POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT PRESSURE TAG NO.: BS-16-PI, BS-17-PI, BS-90 PI, BS-91 PI, BS-90-PR, BS-91-PR REF DWG* 205-009, BS Ol and BS 02 Type and Category B, C, 1 70 psig (BS 16, 17-PI)
Range -
0 - 200 psig (BS-90, 91 PI)
Environmental Qualification - Yes Seismic Qualification - Yes .
Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source IE Display - ' Indicated in CR Recorded in EFIC Room On Demand in TSC & E0F RG 1.97 Position - Coraplies SOURCE:
0, 5, 22 REASON:
Containment pressure is a key measurement used for detection of a LOCA,
_ verification of ESFAS mitigation, or detection of a potential . breach of containment.
Recorder location meets NUREG 0737, item II.F.1.4.
c l-r
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i;
, tis . PET: Opti RESP; Nuc. Ops Eng DO 397 s.. . . _ _ -- ,- - . , . . . . , . . _ . . . . _ . _ . _ _ . . _ - _ . - , _ . , ..:..~..,__....>-..__..,_._._.,._,.._,_.-
l DESIGN BASIS DOCUMENT Page 25 of 91 Crystal River Unit 3 3 Syst!W NAWL SY$1TUCODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A i
! PARAMETER:
VARIAB!.E: DECAY HEAT FLOW (LPI FLOW)
TAG NO.: DH 01-F13 1, DH 01-F14 1 REF DWG: 205 021, DH-01, DH 02 i Type and Category - D, 2 Range 5,000 gpm (Design = 3000 gpm) !
l Environmental Qualification - Yes i Seismic Qualification - N/A Quality Assurance - Yes Redundancy - W/A - 2 Channels Power Source - VPS/0G with IE Standby i Display - Indicated in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5 ,
REASON:
DH flow measurement monitors LPI safety injettion in event of a LOCA, or residual heat removal (RHR) during reactor shutdown.
l t
i tina Ari- Optt fitSP; Nuc Ops Eng g(0 397
_.. _ - - . ..;..._.. _ . _ . . . _ . . _ . . - . , , _ - . . . _ , . _ . _ , . . . . . _ , . . _ , . , _ - , , _ , _ . .i.., , .
DESIGN BASIS DOCUMENT Page 26 of 91 e..
BY$itW NAWf
... . Crystal River Unit 3 "" 5" SY5tfW CODE 1
POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
l VARIABLE: DHHE OUTLET TEMPERATURE i TAG NO.: DH 2 TII, DH 2 TI2 i REF DWG: 205 021, DH 04 and DH 05 Type and Category - D, 2 Range 300'F Environmental Qualification - Yes Selsmic Qualification - N/A Quality Assurance Yes Redundancy - N/A - 2 Channels Power Source - UPS with IE Standby Display - Indicated in CR RG 1.97 Position Complies SOURCE:
0, 5, 10, 11, 13, 20' REASON:
DHHE outlet temperature is used to monitor operation of the LPI system after a LOCA.
Range covers all anticipated requirements. Design temperature of the Decay Heat System and-Heat-Exchanger for CR3 is 300'F. >
1$8 Rit: 0011 RESP. Nuc. Ops Eng DJO 397
DESIGN BASIS DOCUMENT Pago 27 of 91 Crystal River Unit 3 3 POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CORE FLOOD TANK LEVEL TAG NO.: CF 2 LII, CF-2-LI2, CF-2 L13, CF-2-Ll4 REF DWG: 08034038 Type and Category - 0, 2 ,
Range - 13" from bottom to 14 ft. >
' Environmental Qualification - Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy . N/A - 2 Channels ,
Power Source - UPS/DG Display - indicated in CR RG 1.97 Position - Complies i SOURCE:
0, 5, 10, 11, 16 REASON:
CF tank' level is required to monitor safety. injection in event of a LOCA. i
+
d j
I 1784 mit: 09ti RESP, Nuc Ops Le9 9U0 397
Page 28 of 91 DESIGN BASIS DOCUMENT ""
h'D v., , _ ,
Crystal River Unit 3 i
l POST-ACCIDEN1 MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CORE FLOOD TANK PRESSURE TAG NO.: CF 1-PII, CF-1-P12, CF-1 P13, CF 1-P14 REF DWG: 08034038 Type and Category - D, 3 Range 800 psig Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy N/A 2 Channels Power Source
- UPS/DG Display - Indicated in CR RG 1.97 Position - Complies SC'JRCE:
0, 5, 10, 11, 12 REASON:
Core flood Tank Pressure is a key variable for pre-accident stattis to assure that this passive safety system is prepared to discharge into the PIS in the event of a LOCA. This pressure indication provides no essential information for operator action during or following an accident. The key variable necessary to determine whether the Core Flood Tanks have fulfilled their safety function is Core Flood Tank Level. Therefore, Core Flood Tank Pressure is a backup type variable and has been classified as a Category 3 instrument accordingly.
1 te RET. Opti DESP. Nut Ops (fg WN 397
DESIGN BASIS DOCUMENT Page 29 of 91 !
Crystal River Unit 3 1
$Y$f(W NAM ( EYOTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CORE FLOOD TANK ISOLATION VALVE POSITION TAG NO.: CFV-5, CFV-6 REF DWG: 302-702 Type and Category - D, 2.
Range - Closed /0 pen Lights Environmental Qualification Yes Seismic Qualification - N/A Quality Assurance Yes Redundancy - N/A - 2 Channels Power Source - UPS/DG Display - Indicated in CR RG 1.97 Position Complies SOURCE:
0, 3, 5,.13, 20 REASON:
CF Tank Isolation Valve position is required to monitor that valve operational -
status is correct.
i 1# - RET. Opti RESP; Nuc Ops. Eng 900 397
- -.-.m._. . . . _ . . , - . . - . _ - - . , _ . -
DESIGN BASIS DOCUMENT Pace 30 of 91
. . . . . . . Crystal River Unit 3 1 POST-ACCIDENT MONITORING INSTRUMENTATION 5/A PARAMETERv VARIABLE: DORIC ACID CHARGING FLOW TAG NO.: N/A REF DWG: N/A Type and Category - D, 2 Range - N/A Environmental Qualification - N/A Swismic Qualification N/A Quality Assurance - N/A Redundancy - N/A Power. Source - N/A I Display - N/A j RG.I.97 Position - Complies SOURCE:
0, 5, 10, 11, 12 REASON:
To Monitor Operation of RCS Injection Systems.
The B&W - designes NSSS does not include a charging system as part' of the Emergency Core Cooling System (ECCS). Flow paths from the ECCS to the RCS include high pressure injection (HPI) and low pressure injection (LPI) with the BWST or the RB Sump as_the suction source, and the Core Flood Tank injection.
L HPI and LPI flow rates are monitored, and BWST, RB sump, and Core Flood Tank E levels are monitored by RG 1.97 variables. Therefore, Boric Acid Charging Flow does not need to be monitored as a Type D variable to monitor the operation of the ECCS.
i r 1 88 RET. Opti RESF. Nuc Ops Eng KC 39/
i DESIGN BASIS DOCUMENT Page 31 of 91 Crystal River Unit 3 l
SYSTtW N AME SYSitM CODt POST ACCIDENT MONITORING INSTRUMENTATION N/A 4
PARAMETER:
VARIABLE: HPl FLOW (0-500 gpm)
TAG NO.: MV 23-FII, MV-23-F12, MU-23 F13, MU 23-F14 REF DWG: D8034039 Type and Category - D, 2 Range 500 gpm (Design - 300 gpm)
Environmental Qualification - Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy -
N/A -
2 Channels (One Channel is 0 200 gpm and the Redundant Channel is 0-500 gpm)
Power Source - UPS/DG Display - Indicated in CR On Demand in TSC & EOF Schedule - Refuel Vill RG 1.97 Position - This flow loop will be upgraded to Class lE, RG 1.97 Type and Category A, D, I during Refuel Vill.
SOURCE ~
0, 5, 8, 9, 15, 17 REASON:
HPI flow measurement is a key variable used to monitor operation of the ESFAS I ,
system in event of a LOCA.
o I
va- net.oussese m on ena uw
[
'l DESIGN JASIS DOCUMENT Page 32 of 91 Crystal River Unit 3 3 SYSff PJ NAMt SY$1[M CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A 4 PARAMETER:
VARIABLE: HPI FLOW (0 - 200 gpm)
TAG NO.: MU-23-F15-1, MU 23 FI6-1, MV 23 FI7-1, MU-23 F18-1 REF DWG: 205-046, MU 01, MU 02, MU 03 and MU 04 Type and Category - A, D, 1 l Range 200 gpm Environmental Qualification - Yes Seismic Qualification Yes ;
i Quality Assut..nce - Yes l Redundancy - Yes -
2 Channels (One channel is 0-200 gpm and the redundant channel is 0-500 gpm.)
Power Source - VPS/DG Display - Indicated in CR I On Demand in TSC & EOF RG 1.97 Position - Complies j SOURCE:
0, 5, 8, 9, 15, 24, 25, 26 REASON:
HPI flow measurement is a key variable used to monitor operation of the ESFAS system in event of a'LOCA.
I l
tte R E f; 0011 RESP- Noc. Ops (eg 100 397
DESIGN BASIS DOCUMENT Page 33 of 91 9.. .
Crystal River Unit 3 3
- " ~
POST ACCIDENT MONITORING INSTRUMENTATION f/A PARAMETER:
VARIABLE: B0 RATED WATER STORAGE TANK LEVEL TAG NO.: DH 7-LI, DH-37-LI, DH 7-LIR-1 REF DWG: 205 021, DH 06, DH 07 ,
Type and Category - A, D, 1 Range - O e 50 ft.
Environmental Qualification - Yes Seismic Qualification Yes Qualit/ Assurance Yes Redundancy - Yes - 2 Channels Power Source IE/DG Display - Indicated an't Recorded in CR On Demand in TSC & EOF RG 1.97 Position - Complie >
SOURCE:- .
O, 5,--10,- 11.- 32 ,
REASON:
BWST level indication is a key variable in' that this tank is the primary source of injection water for at least 20 minutes following a LOCA.
The variable is indicated on redundant, qualified, ' indicators, located on a seismically qualified panel board and one of the redundant channels is recorded.
Due to a lack of seismically qualified panel space the recorder is mounted on panel not seismically qualified.
The recorder itself is environmentally qualified and electrically isolated from the rest of the qualified instrument loop.
B&W's Criteria for BWST sets three criteria which must be met by the BWST. The first criterion is related to fuel-handling and transfer operation: and is not-applicable for accident events. The second criterion requires that sufficient
- volume be contained in the- BWST to provide sufficient time for injection operation prior to switchover to an alternate source. This is a critemn which must be satisfied during normal plant operation to ensure availability of the BWST during an accident. This volt.ine is less than that required to meet the .
first criterion.
-Ma m[T; C>t' RESP; Nuc Ops Eng 900 391 -
- - - . . . . . - - _ . . . _ ~ _ _ . - _ . . _ _ , _ . . - -
-- - -,,.,-- - .- c-,- -, . -
DESIGN BASIS DOCUMENT Page 34 of 91 I
1 9%
SvEttM NAug W ~
Crystal River Unit 3 SYSTEM CODE 3
- POST ACCIDENT HONiiOR!hG INSTRUMENTATION N/A i +
i The third criterion is the important ne for use during and after an accident.
This criterion requires that the BWSr level be such that adequate NPSH for all ECCS pumps be available, To meet the desired intent of the regulatory guide that accident monitoring ,
, instrumentation also be used, to the extent practicable, during normal .
- - operations, the existing BWST lovel instrumentation has suf ficiently wide range to monitor the level required in the BWST. At CR3, the tank level is monitored from 0 to 50 feet. A low alarm is provided at 4 feet and switchover is required '
at 2.5 feet. Thus, the operator is provided with adequate level indication at all times.
s 9
D
- MT Opti MS*; Nuc. Ops (eg W . d7 w~;-,.-...
Page 35 of 91 m D _ SIGN BASIS DOCUMENT "" "
S3wer Crystal River Unit 3 EYSTEW CODE
$v$1tW Naut POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: REACTOR COOLANT PUMP STATUS TAG NO.: RECALL PT NO. 129, 130, 131, 132 REF DWG: N/A Type and Category - D, 3 Range 150% LOAD Environmental Qualification - N/A Seismic Qualification N/A Quality Assurance - N/A Redundancy - N/A 1 per pump Power Source OP Display - Indicated Limits in CR 0 150% ledicated in CR Indicated Total Amps in Switchgear On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
RC pump motor amps and indicating lights are required to monitor operation of the primary coolant system pumps.
un an.ow erst noc en tna .x w
Page 36 of 91 e%
sv$11M NAug
%wer DESIGN BASIS DOCUMENT Crystal Filver Unit 3 " " * *
$YSf!M CODE 3
POST-ACCIDENT HONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RC SYSTEM S F ' O.ELIEF VALVE FLOW / POSITION TAG NO.: RC-160 Mll, i 0 M12, RC-160 M13 REF DWG: 205 047, RC 1 -
Type and Category - D 2 Range - Acoustic System Envir>nmental Qualification - Yes Seismic Qualification - N/A i Quality Assurance - Yes Redundancy - N/A (Sensor Back up Only) .
I Power Source - UPS/DG j Display - Indicated in CR On Demand in TSC & EOF j l
RG 1.97-Position. Complies i SOURCE:
O, 5 i REASON:
RC System safety valve flow is a key variable to monitor valve operation and loss of primary coolant.
Accelerators are seismically mounted.
7 W4 Rff: CYti RESP: Ac Ops ("O 900 397 I
~~ v , - w w w- v'm. . .,-..rv. -.u,v-- - - - - - - , - - - - - - --.,,r,-s, ,n , ,r , , , ~ , - - - - , - - - -
r's DESIGN BASIS DOCUMENT Paoe 37 of 91 Crystal River Unit 3 3
.ysitu nmi Sv5tiu cxc POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
s VARIABLE: PRES $URIZER LEVEL TAG NO.: RC-1-LIR 1, RC-1-LIR-3 REF DWG: 205-047, RC-01, RC-05, RC-06 Type and Category D, 1 Range 0 - 320 Inches.
Environmental Qualification - Yes Seismic Qualification Yes Quality Assurance - Yes Redundancy Yes - 2 Channels Power Source lE/DG Display - Indicated and Recorded in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 1, 2, 5, 10, 11, 12 REASON:
Pressurizer level is a key variable required to ensure proper operation of the pressurizer.
The pressurizer level was sized based on the following. The water volume is chosen such that the reactor coolant system can experience a reactor trip from full power without uncovering the level sensors in the lower shell and to maintata system pressure above the HPI system actuation setpoint The steam volume is chosen such that the reactor coolant system can experience a turbine trip without covering the level sensors in the upper shell. The range of 0 320" H2 O was based on this criteria and setpoints for automatic or manual actions are based on this range.
The pressurizer is approximately 512 inches tall. The 0 inch reference for the pressurizer level instrument range is 43 inches above the lower datum line (approx. 96 inches from the bottom),16 inches below the upper set of heaters, and approximately at the level of the second set of heaters. The upper pressarizer level top 320 inches above the 0 inch reference) is 43 inches below the upper datum (approx. 92 inches from the top), and appraximately 37 inches from the spray head.
U88 RET 0011 RESP: Nsc Ops (og IKO M7
DESIGN BASIS DOCUMENT ,
Pao
- 38 o' 91 j Crystal River Unit 3 l 3
SysitM NAME SY5 f t M CODE l i POST-ACCIDENT MONITORING INSTRUMENTATION N/A 1
i The Accident Analysis chapters of several B&W Owners Group Utility Final Safety Analysis Reports (SAR), as well as Part II, Volume 2 of the B&W Owners Group Abnormal Transient Operating Guidelines (ATOG) were reviewed to obtain pressurizer level responses to anticipated transients and accidents.
For anticipated transients such as decreasing feedwater temperature, excessive main feedwater flow, loss of main feedwater flow, decreasing steam flow, small steam leaks, loss of external load, loss of off-site power, loss of condenser vacuum and small steam generator tube leaks, the existing ranges for the pressurizer level are sufficient such that indicated level should remain on-scale.
For severe transients (accidents) such as steam line break, steam generator tube rupture and many small break LOCA's, the pressurizer will void. Following ESFAS actuation of the HPI system, actions can be taken as necessary to stabilize the plant. Those actions are based on subcooling margin and RCS pressure, not pressurizer level. For the case of a total loss of feedwater, the pressurizer will go solid unless either main or emergency feedwater is restored to the steam generators within about 15 minutes. Actions taken are dependent on when feedwater is restored, secooling margin and RCS pressure, not pressurizer level.
in general, for severe transients os accidents, the pressurizer will either void or go solid. A voided pressurizer will cause indicated level to go off-scale i low followed by a rapid decrease -in RCS pressure to saturation. A solid pressurizer will cause indicated level to go off scale high accompanied by high RCS pressure, possible large and rapid changes in RCS pressure, PORV and pressurizer safety valve actuation. All of these indications are available in the Control Room.
Based on this information, the existing ranges of pressurizer level indication are sufficient for anticipated transients. For severe transients or accidents, indicated pressurizer level will go off-scale high or low due to the pressurizer l going solid or voiding and, as a res*Jit, top to bottom instruments would provide no significant additional information, in these cases, subcooling margin, RCS pressure, PORV status and pressurizer safety valve status are monitored to determine actions to be taken.
W6 RET. Opu RESP. Nuc Oct f n0 MM
.._.----- -, . , . - - . . - -. . - - . - ..,.. ,,. ,. ----- .~- -__- -_.., -- - , - - ,
I Page 39 of 91 DESIGN BASIS DOCUMENT "' "
- Crystal River Unit 3 3 SY$1EM NAME SYSIIM CODI POST ACCIDENT HONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRESSURIZER HEATER STATUS b! b4
- Type and Category - D, 2 Range 1000 kw Environmental Qualification - Yes Seismic Qualification - N/A Qualit.y Assurance Yes Redundancy - N/A Power.S'Jrce - Unit Bus with IE Standby Display - Wattmeters in Ca RG 1.97 Position - Complies SOURCE:
0, 1, 2, 4, 5, 10, 11, 14 REASON:
Pressurizer heater status-is important to determine operating m tas of the pressurizer. Emergency heaters are loaded manually onto the ciesels with observation of load before and after, tite RET. Opti RESP: Nuc. Ops Eng 9U0 397 -
DESIGN BASIS DOCUMENT Page 40 of 91 Crystal River Unit 3 3
$YETip NAME Sf$ flu CODE POST ACCIDENT MONITORING INSTRL' MENTATION N/A PARAMETER: ;
VARIABLE: RC DRAIN TANK LEVEL TAG NO.: WD-23 LII REF DWG: 205-060, WD 04 Type and Category - D, 3 Range - 6" from Bottom - Top Environmental Qualification - N/A Seismic Qualification - N/A
. Quality Assurance - N/A Redundancy - N/A -
Power Source - UPS/DG Display - Indicated in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
RC drain tank level is required to monitor operation of the RCS system relief valves.
A sisa P. Eft Opu. M&P. Nw Ops (.ng ##JO 39/
. . , . . . . . . . . . . _ _ _ . . _ . . . . _ . . . . . - . _ . _ . , _ . . . -. . . . _ . .,_. . . . . . . . - _ _ __m, , . . . . . _ _ ,
DESIGN BASIS DOCUMENT Page 41 of 91
,. . Crystal River Unit 3 1
6f$7tM NAug SYsitM CODE POST. ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RC DRAIN TANK TEMPERATURE ,
TAG NO.: WD-24-TI-l REF DWG: 205 060, WD 02 ;
Type and Category - D, 3 i
Range - 0 400*F j i
Environmental Qualification N/A l Seismic Jualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - UPS/DG l 4
j Display - Indicated in CR '
On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11 REASON:
RC drain tank temperature is required to monitor operation of the RCS system relief valves.
Rupture disc (set 9 110 psig) precludes temperature from exceeding 345'F.
RG 1.97 range of.0 - 400'F is acceptable to 50 - 750'T NRC requirement.
t 086 RET: Opti RESP Nuc, Ops Eng 900 397
DESIGN BASIS DOCUMENT Page 42 of 91 l 9...
SYSTiu Naut
. Crystal River Unit 3 "" "
6YSilW CODE 1
l POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER.
i VARIABLE: RC DRAIN TANK PRESSURE l
TAG N0.: WD 22-Pil RET DWG: 205-060, WD-06 Type and Category D, 3 Range -.0 - 100 psig (Design - 100 psig) l Environmental Qualification - N/A Seismic Qualification N/A Quality Assurance - N/A l
Redundancy - N/A Power Source - UPS/0G ,
1 Display - Indicated in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
RC drain tank pressure is required to monitor operation of the RCS system relief )
valves.
l Una RET: 001 RESP; Peve 004 Ens M 397 l
DESIGN BASIS DOCUMENT Page 43 of 91 Crystal River Unit 3 3 SYSitM hAut SYSTEM CODE POSTACCIDENTMONITORINGi$htVMENTATION N/A PARAMETER:
VARIABLE: STEAM GENERATOR LEVEL TAG NO.: SP 17-LII, SP-17-LIR, SP 18 LII, SP 21-LII, SP-21-LIR, SP-22-LII, SP 25 LII, SP-25 LIR, SP 26 Lil, SP-29-Lil, SP-29 LIR, SP-30 LIl REF DWG: 205-074, SP-01 thru SP 04 Type and Category - A. D, 1 Range 150 Inches (Startup) 100 - 394 inches (Operation)
Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Chsnnels Power Source - lE/DG Display - Indicated and Recorded in CR i On Demand in TSC ; EOF RG 1.97 Position - Complies SOURCE:
0, 5, 19 REASON:
Steam generator level is a key variable to monitor secondary plant operation (FW,EF,EFIC).
CR3, having a B&W NSSS, utilizes Once Through Steam Generators (OTSG) which produce superheated steam and therefore are not equipped with moisture separators in the steam generator. CR3 installed the Emergency Feedwater Initiation & Control' (EFIC) system, which was completed in Refuel 5, This system provides Class lE, redundant, level indication in the CR. The lower range (start-up) measures 0 to 150 inches and the upper range (operating) measures 100 to 394 inches.
The lower level sensing tap (0 inches) is approximately 6 inches above the lower tube sheet and the upper level sensing tap (394 inches) is at approximately the level of the aspirating ports.
.. sigg PET Opti RESP. Nuc Ops ta0 DM 397
.. . . _ _ . . , _ _ . . . . . . _ . _ . . -. ~_ .- . .
DESIGN BASIS DOCUMENT Pao
- 44 o' 91 Crystal River Unit 3 l SYSitM hAME SYSitM CODE POST-ACCIDENT HONITORING INSTRUMENTATION N/A PARAMETER:
VARIABl.E: STEAM GENERATOR PRESSURE TAG NO.: MS-106 PIR, 015-107-PIR, MS-Il0-PIR, MS Ill-PIR REF DWG: 205-039, MS-01 and MS-02 Type and Category A, D, 1 Range 1200 psig (Ind)
Environmental Qualification Yes Seismic Qualification -'Yes Quality Assurance Yes Redundancy Yes - 4 Channels Power Source lE/DG ;
Display - Indicated and Recorded in Cr.
RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, 19 REASON: i Steam generator pressure is a key variable-to monitor secondary plant operation.
The steam generator pressure range of 01200 psig is acceptable because the safety valve setpoints range from a low of 1050 psig i 10 psig to 110 psig 110 psig, which are close to 20% above the low setpoint recommendation. The high safety valve setpoint is about 100 psig below the high end of the instrument scale.
7he highest safety valve setting is typically 110 psig. The steam relief capacity is 20-25% above the expected steam flow rate. Excess relief capacity
.is maintained when safety valves are inoperable. The FSAR analysis indicates a naximum steam pressure of about 1100 psig for operating plants. Based on these 1 Tac s, it is FPCs position that the existing range of 0-1200 psig is sufficient.
148 - REfeOpti RtSP: Nw Ops Eng WJO 397
4 DESIGN BASIS DOCUMENT Paoe 45 of 91 Crystal River Unit 3 3 Systf W NAME SYSTIM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: MAIN STEAM SAFETY REllEF VALVE POSITION TAG NO.: MSX-1, MSX-2, MSX-3, MSX-4, MSX S REF DWG: 209 039, MS-23 Type _and Category - D, 2 Range Video Display Environmental Qualification Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy - N/A Power Source - UPS/DG ,
Display - Video display unit viewing MSSV vent stacks is mounted on the MCB RG'i.97 Position - Complies SOURCE:
0, 1, 2, 4, 5, 10, 11, 27 REASON:
Main steam relief valve position is important to monitor secondary plant i releases.
148. RET: Optt RESP: Nc Ops the gre 397
DESIGN BASIS DOCUMENT . Pago 46 of 91 Crystal River Unit 3 3 Systid haut SYtTIM CODI POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PAIN FEEDWATER FLOW TAG NO.: SP-8A Fil, SP-8A-F12, SP-8B-F12, SP-8A-FIR 1, SP-88 Fil REF DWG: 08034031, Sh. I and 3 Type and Category - 0, 3 Range 0 - 6,000,000 lb/hr (Design - 5.3 x 106 lbs/hr)
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A - 3 Channels Power Source - UPS/DG Display - Indicated and Recorded in CR On Demand in 1SC & E0F RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
Main feedwater flow is important to monitor secondary plant operation during normal operation, OM RET Opti ptGP.N w C+s tag 9A 397
Page 47 of 91 l DESIGN BASIS DOCUMENT """"
Crystal River Unit 3 3 D SitM C, ODE SYstIM hAME POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: EMERGENCY FEEDWATER FLOW TAG NO.: EF-23-Fil, EF-24-Fil, EF-25-Fil, EF-26-Fil REF DWG: 205 026, EF-01 and EF 02 Type and Category - 0, 1 Range 1000 gpm (Design - 740 gpm)
Enviroi. mental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 4 Channels Power Source - lE Display - Indicated and Recorded on demand in CR On Demand in TSC & E0F RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
Emergency feedwater flow is important to monitor secondary plant operation during a transient.
A redundant 4 channel system with all safety parts seismically qualified, and transmitters environmentally qualified were installed in conjunction with the EFIC modifications, 1
I 1# RET: Opit RESP. Nuc Ora Eng 9t0 397
Page 48 of 91 m DESIGN BASIS DOCUMEN'r """""
Nmer Crystal River Unit 3 3 SYSTiw Naut SY6itu CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: EMERGENCY FEEDWATER TANK LEVEL 1AG NO.: EF-98 Lil EF-99-L11 REF OWG: 205 026, EF 05 Type and Categocy - A, 0, 1 Range 0 < 38 FT.
Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - IE Display - Indicated and Recorded on Demand in CR On Demand in TSC & EOF RG 4.97 Position Complies SOURCE:
0, 5, 28 REASON:
Emergency feedwater tank level is a key variable to ensure water supply for emergency feedwater.
3
' 'Be RET,000 RESP: Nuc Ops Eng 1K0 397 1
Page 49 of 91 DES.'GN B ASIS DOCUMENT 9,M SYBtEM NAME Crystal River Unit 3 SYSTEM CODE 3
POST ACCIDENT MON 1W5" -G INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT SPRAY FLOW TAG NO.: BS-1-Fil, BS-1-F12 REF DWG: D8034036 Type cnd Category - D, 2 Range - 0 lann = = '0esign - 1500 gpm) ,
Environmental Qualification - Yes Seismic Qualification N/A Quality Assurance - Yes Redundancy - N/A - 2 Channels Po.or Source - UPS/DG Display - ' Indicated in CR RG 1.97 Position - Complies SOURCE:
0, 5, REASON:
Containment spray flow is important to monitor operation of the Reactor Building spray system in event of an accidtnt.
T' an: een aEsa nx on En, aw l v
DESIGNL BASIS DOCUMENT Pago 50 of 91 Crystal River Unit 3 3 SY5f tM NAMg . SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RB FAN HEAT REMOVAL TAG N0.: Computer Pt. S348, S376, S387 (SW-47-FT1, SW 51-FT1, SW-55-FTI)
REF DWG: 205 056, SW-01 Type and Category - D, 2 '
Range - On-Off Indicator Lights NSCCW Flow ,
1 Environmental Qualification - Yes Seismic Qualification - N/A l l
Quality Assurance - Yes j Redundancy - N/A Power Source - V60P-2 Display - ES Status Lights (Display for DW flow to RBCU is available on demand via plant computer.)
RG 1.97 Position - Complies SOURCE:
0, 5, 13 REASON:
RB heat removal is important to monitor Rea: tor Building cooling in event of an accident..
The following position is a justification developed by the BWOG Reg. Guide 1.97
. Task Force.-
The plant' has a design air flow rate from the Reactor . Building fans during '
normal and accident or emergency conditions The design flow rates are achieved by reducing the normal tunning speed of the fan motors by about one-half during accidents where the heavier steam-air mixture might over-load the motors at full speed. The fan cooling units are cooled by cooling water from the Nuclear Services Closed Cycle Cooling System (SW).
For the follt. wing reasons, the status of the fan breakers and cooling water flow rates are the acasured variables. The primary indication that the Reactor Building is being cooled 1: the Reactor Building temperature. A first indication that the Reactor ~ Building fans n e performing their. function is an
!!64 - RET: Optl, RESR huc. Oct Eng 900 3st w .
DESIGN BASIS DOCUMENT Paco 51 of 91 Crystal River Unit 3 3 SYstLM NAME 6YSTEM COOf POST-ACCIDENT MONITORING INSTRUMENTATION N/A indication of the status of the fan breakers to ensure that the fans are on and the delivery of cooling water flow to the cooling units. The flow variable was upgraded to comply with RG 1.97 requirements during Refuel 6.
l As backup information to ensure coupling between the fan and motor, each fan is equipped with vibration detectors which annunciate in the Control Rorm.
Calibrated percent load meters for the motors are also located in the Control Room.
1 Bd RET:Op , htSF, Nuc Ops Eng $X) 377
DESIGN BASIS DOCUMENT _ Page 52 of 91 Crystal River Unit 3 3 SYSTEM NAME . SYSTEM CODE PC..-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE:- CONTAINMENT ATMOSPHERE TEMPERATURE TAG NO.: AH-536 TIR, AH 537-TIR, AH-538-TIR, AH 539-TIR REF DWG: 205-056, AH-01 Type'and Category - D, 2 Range 400*F Environmental Qualification - Yes Seismic Qualification - N/A Quali'.y Assurance - Yes Redundancy - N/A -4 Measurements Power Source - UPS/0G Display - Recorded in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0,'5, 19 REASON:
Containment atmospheric temperature is important to indicate accomplishment of cooling following an. accident.
s 15 RET. Opte. RESP; Nuc. Ops. Tng 900 397
l DESIGN BASIS DOCUMENT Pao' 53 of 91 s
9%
SYSTEM NAME
!.b wet Crystal River Unit 3 POST-ACCIDENT MONITORING INSTRUMENTATION
$YSTEM CODE 3
N/A Pl.RAMETER:
VARIABLE: CONTAINMENT SUMP WATER TEMPERATURE TAG NO.: N/A REF DWG: N/A Type and Category - D, 2 Range - N/A Environmental Qualificatior. - N/A l Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - N/A RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11 REASON:
The NRC RG 1.97 requires containment sump water temperature indication as a Type D variable for-the purpose of monitoring the operation of containment cooling systems. No additional justification is provided.
It is expected that this information would be used following high energy line breaks in containment. While containment sump temperature trends may be indicative of high energy fluid leakages and containment cooling, it would be difficult to conceiva of any correlation from monitored values to any useful measure of sur. cess.
Containment sump temperaures impact containment cooling only when the Reactor Building spray system is in operation ith suction being taken from the sump.
This would be expected to be used only after depletion of available supplies from the BWST.
- a. [pntainment Coolina System Manitorina Containment atmospheric temperature ir.3trumentation provides the most direct indication of containment cooling system success. Containment 1:3a RET: rett RE5h Nuc Ops Eng 900 397
Page 54 of 91 CESIGN BASIS DOCUMENT
@m BYSTEM NAME W Crystal River Unit 3 SYSTEM CODE 3
POST-ACCIDENT MONITORING INSTRUMENTATION N/A atmospheric temperature instrumentation was upgraded during Refuel 6 to meet RG 1.97 requirements.
The next most valuable indication of containment cooling is provided by instrumentation which monitors the operation of systems with a containment cooling function. This function is provided by the Reactor Building Spray System (BS) and the Reactor Building Air Handling System (AH). The Reactor Building containment Fan Heat Removal Cooling Water Flow Instrumentation (SW) was upgraded to provide heat removal indication meeting the requirements of RG 1.97 during Refuel 6 (See position Page 50).
Containment atmospheric temperature is recorded in the Control Rom. The Reactor Building air handling fan motor breaker positions, indicating lights and percent full load ammeter indicators representative of air flow loading are monitored on the control board. Fan cooling water flow loakage is also monitored and alarmed.
Coi;tainment sump water temperature provides only a crude indication of conte ment cooling system success, Because of this and the availability of Je instrumentation described above, sump water temperature instrumentation is not necessary for containment cooling system monitoring. Nevertheless, containment sump temperature can be determined when the LPI is in the recirculation mode, using temperature indicators meeting all other RG 1.97 requirements,
- b. Eauioment Temnerature limits Protection of DH and BS from Excessive Sump Temperatures: These systems are designed for fluid temperatures in excess of the RG 1.97 required range for sump water temperature instrumentation (Ref: FSAR, Table 6-3).
No operator action is required in response to sump water temperature.
Actual options available with excessive sump water temperatures would be limited to the reactor coolant system and containment cooldown prior to transferring to the recirculation mode of contcinment spray. This transfer is not required for over an hour after a LOCA, in which time the sump temperature is below 205'F.
- c. NPSH Reauirements The. minimum available NPSH for the Decay Heat Removal pumps is conservatively calculated with sufficient safety margin such that indication of sump temperature is not required in order to insure adequate NPSH and no automatic or manual actions are initiated based on this temperature.
l
)
i SA REl: Opti RESP: Nuc Ops Eng 900 397
DESIGN' BASIS DOCUMENT Page 55 ' of 91_
i
-Crystal River Unit 3 3
$YSTEM NAME ,
SYSTEM CODE
-POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: MAKEUP FLOW IN TAG NO.: MU-24-FI REF DWG:. 205 041, MV-06 Type and Category - 0,.3 Range 200 p H (Design - 115 gpm)
Environmen6al Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - UPS/DG Display - -Indicated in CR
- RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11 REASON:
The following position is a justification developed by the BWOG Reg. Guide 1.97 Task Force.
During design basis events ch as LOCAs, the Makeup and Purification System
-(MU) is isolated. Makeup flow is a backup variable.to the makeup line isolation valve position. Dur_ing normal operation and certain design basis events such as small break LOCA, the MU System is used to supply borated makeup water into the RCS to balance letdown flow out of the RCS. It also adds makeup water in order to maintain pressurizer level at its setpoint. Thus', makeup flow is an important variable for monitoring _ the operation of the MV System. For the reasons provided in .the Position Section for the variable, hakeup Tank Level (Page 57), it is suggested that this variable can be a backup-to Makeup Tank
' Level. ~ As a backup Type D variable, it is appropriate that Makeup Flow be classified Category 3.
148 RET' Cpit RESP; Nuc. Ops Eng. 900 391
Page 56 of 91 DESIGN BASIS DOCUMENT ""*'"
Crystal River Unit 3 i SYSTEM NAME SYSTEM CODC POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: LETDOWN FLOW 0VT TAG NO.: MV-4-FI REF DWG: 205-041, MV-05 Type and Category - D, 3 Range 160 gpm (Design - 140 gpm)
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - UPS/DG Display - Indicated in CR On Demand in TSC & E0F RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11 REASON:
The following pusition is a justification developed by the BWOG Reg. Guide 1.97 Task Force.
During design basis events such as LOCAs, the MV System is isolated. Letdewn
-flow is a backup variable to the letdown isolation valve position. During normal operation and certain design basis events such as small break LOCAs, the MV System is used to supply borated makeup water into the RCS to balance letdown flow out > , - he RCS. Thus, letdown flow is an important variable for monitoring ti operation of the MV System. For the reasons provided in the position seu on for the variable Makeup Tank Level (Page 57), it is suggested that this variable can be a backup to Makeup Tank Level. As a backup Type D variable, it is appropriate that letdown flow be classified Category 3.
For CR3, normal letdown flow rate through the block orifice is 45 gpm with a muimum flow rate of 140 gpm with both letdown coolers in operations. Having this maximum flow rate of 140 gpm the range of letdown flow indicator is 0 to 150 gpm which adequately meet ; the Regulatory Guide recomrtendation of 0 to 110%
design flow.
tDe RET: 0011 RESP: Nuc Ops Eng 900 3fs/
1 l
DESIGN ' BASIS DOCUMENT Page 57 of 91 .
""" l Crystal River Unit 3 3
$YSTfM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION' N/A :
-PARAMETER:
VARIABLE: MAKEUP TANK LEVEL i TAG N0.: MU-14-LIRI i REF DWG: 205-041, MU-07; )
08034039, Sh. 2 l Type and Category - D, 2 j Range 120 Inches
]
Environmental Qualification - Yes - SR portion Seismic Qualification - Yes - SR portion l
Quality Assurance - Yes SR portion
' Redundancy - N/A - 2 Channels Power Source - UPS Display - Recorded in CR On Demand in TSC & EOF RG 1.97. Position - Complies SOURCE:
0, 5 REASON:
The following position is a justification developed by the BWOG Reg.~ Guide 1.97-Task Force.
During normai (seration and certain design basis accidents where the MU System
-is still opni,Lle, the Makeup Tank Level is the key variable used to provide indication that tne MU System is operating properly.~ Makeup Tank Level information provides the first indication that a suction source for the Makeup-pumps is ava!1able. Since the Makeup Tank is a surge volume' for the RCS, Makeup Tank Level and Pressurizer Level indications can be used to qualitatively assess
. Makeup Flow into the RCS and Letdown Flow from the RCS.
Quantitative indication of Makeup Flow and Letdown Flow can be provided by flow instrumentation for these variables. However, in most instances, it -is more important to know-that Makeup and/or Letdown is established (qualitative) and not-necessarily what those flow rates are (quantitative) in order to determine the operation of the .MU System. Since Pressurizer Level instrumentation is Category 1 and the suggested Makeup Tank Level instrumentation be Category 2, then high quality instrumentation is available to provide information on the P
NA RET: Opti RtSP: Nuc. Ops Eng 9.C JU ]
_ . _ . . _ _ . _ _ __ . .. _ _ _ _ .. _ _ . .._... _ _ . _ _ _ . _ .~ _ __ _ _
f l
DESIGN BASIS DOCUMENT . Page 58 of 91 M Crystal River Unit 3 ""*"
SYSTEM CODE 3 ,
BY57tM NAME POST-ACCIDENT PONITORING 1NSTRUMENTAT10N N/A status and operation of the MU System. Flow rate anon provided for Makeup .
Flow and Letdown Flow can be used as confirmatory :kup information to Makeup Tank Level and Pressurizer Level,
. Meets intent of RG 1.97, 21" from bottom to 4' f < om top of vessel. Parts of safety system are seismic with QA. QA requirements meeting CR3 iicensing commitments were applied to safety related portions of this instrument string.
1 1
1
~l tE6 PET: Octt RESP; Nuc. Ort. Eng 5% 397
, . _ . ~ .,
DESIGN BASIS DOCUMENT Pace 59 of 91 m " " "
Crystal River Unit 3 3 BYSTEM CODE 6Y$f tM t.AME POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABEE: COMPONENT C00EING WATER TEMPERATURE TO ESF SYSTEMS TAG NO.: DC-35-TI, DC-39-TI, RW-12-TI, RW-13-Tl REF DWG: 208 019, 00-02; 205-050, RW-01 Type and Category - D, 2 Range 200*F (DC Sys) 0 - 250'F (SW Sys)
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy N/A Power Source - UPS/0G Display - Indicated in CR RG'l.97 Position - Complies SOURCE:
0, 5 REASON:
Component cooling temperatures are important to monitor operation of ESF cooling systems.
The 0-200"F range is for the Decay Heat Closed Cycle Cooling Systems (DC) and the 0-250*F range is for the Nuclear Services Closed Cycle Cooling systems (SW).
This equipment was originally purchased without Quality Assurance documentation.
Future equipment will be purchased with the requirement to specify the applicable Quality Assurance practices.
1'43 RET; Opft RESP: Nuc Oca tr:q DX) 391
DESIGN- BASIS DOCUMENT Page 60 of 9L Crystal River Unit 3 3
Bf37tuNAME SYSTEM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: COMPONENT COOLING WATER FLOW TO ESF SYSTEMS (SYS1EM STATUS)
TAG NO.: DC-5-PI, DC-6 PI, DC-50-LI, DC-54-LI, SW-2-PI, SW-139 LI REF DWG: 205-019 DC-01; 205-056, SW-02 Type and Category - D, 2 Range - 10 ft. below to 4 ft. above normal WL (SW Sys);
from 11 ft. -3" below to 4 ft. above normal WL (DC Sys);
C - 200 psig (SW Sys);
O - 60 psig (DC Sys)
Environmental Qualification - Yes Seismic-Qualification - N/A i
Qtality Assurance - Yes Redundancy - N/A Power Source - VBDP-2 Display - Indicated in CR (SW temperature display is available on demand via plant computer)
RG 1.97 Position - Complies SOURCE:
0, 1,'5, 10, 11, 13 REASON:
Component cooling systems status u important to monitor operation of the ESF cooling systems.
There are presently no flow indications on the main control board for Decay Heat Closed Cycle Cooling (DC) and Nuclear Services Closed cycle Cooling (SW systems. Local flow indication for-these systems is available. Indicated flow) ~
. measure:aents in the Control Room are not deemed necessary because the DC and SW
. Systems surge tank levels provide better information to the operator. Tile wide range of. design flows to various ESF com representative of overall system performance.ponents would Service water not pressures header necessarily andbe remote actuated valve positions are available to the operator and along with the surge tanks -levels, which provide a better overall indication of system status.
QA requirements meeting CR3 licensing commitments were applied to safety related portions of this instrument string.
3 38 PET: Opti RESP Nuc. Ops. Eng guo 397
DESIGN BASIS DOCUMENT Page 61 of 91 ]
Crystal River Unit 3 ""**
3 SY$lthi N AM( SYSTEM CODE
)
POST-ACCIDENT MONITORING INSTRUMENTATION N/A l
PARAJ(ETER:
l l
VARIABLE: HIGH-LEVEL RADIOACTIVE LIQUID TANK LEVEL l TAG NO.: WD-76-Pr, WD 78 LI, WD-81 LI, WD 103-LI, WD 106-LI, WD-161 L1, WD-180-LI REF DWG: 308-813; 308-817; 308 339
)
Type and Category - D, 3 Range 100% j Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A I Redundancy - N/A Power Source - Instrument Air Display - Lo 1 WD Panel q RG 1.97 Position - Complies 1 i
SOURCE: ,
0, 5 -i REASON: -.
Level indication of conc : trued waste tanks, concentrated boric acid tanks, and i spent resin. tank is important to indicate storage volume. ..
Tanks covered by this variable are:
Concentrated-Waste Tanks (2)
Concentrated Boric Acid Tanks (2)
Spent Resin lloldup Tank Tne level indication for-tne concentrated waste tanks, concentrated boric acid tanks and the spent resin hold-up tank are indicated on the radioactive waste disposal control panel located in the Auxiliary Building. High level alnrms at this panol will cause a common alarm to actuate on the main control board. The
- controls for tF- liquid waste disposal system are all located at the local panel; therefore, indication on the main control board would not enhance operator control from the Control Room.
1/08 - RET: Opti RESP: Nuc. Ops. Eng 9CO 397
DESIGN BASIS ' DOCUMENT Page 62 of 91 Crystal River Unit 3 3
SYSTEM NAME. SYSTEM CODE POST-ACCIDENT kONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: RADI0 ACTIVE GAS HOLD-UP TANK PRESSURE TAG N0.: WD 16-PI, WD-17 PI, WD 18-P1 REF DWG: 308-806 Type and Category - D, 3 Range .150 psig (Design 150 psig)
Environmental Qualification - N/A
. Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - Instrument Air Display -- Local WD Panel l l
RG 1.97 Position - Complies i SOURCE:
0,.5, 10, 11, REASON:
Waste gaa-holdup-tank pressure is important to indicate storage capacity.
The control and indications for the waste disposal system are located on the radioactive waste disposal panel in the Auxiliary Building. Indication of r6disactive gas hold-up tank pressure is not a necessary Control Room variable for thc post accident monitoring. In the event of an accident which results in signif t : ant failed fuel or significant radioactive gas release, the. manual transfer of radioactive gases to the radioactive gas hold-up tanks would rot be attemp'.ed since -the Reactor Building would be utilized as the hold-up tank.
There tre no automatic transfer operations involving'the radioactive gas hold-up tanks during post-accident. conditions is nnt necessary since these tanks are not utilized for accident mit-igation.
The radioactive gas hold-up tanks are equipped with relief valves which are set at 125 psig. The range of the pressure indication is 120% above the relier valve setting.
. tisa RET: Optt RESP; Nuc. 0% Eng. GrX) 5 4
DESIGN BASIS DOCUMENT -Pace 63 of 91_
r Crystal River Unit 3 3 6VLTEM CUDE SYSTEW NAMf POST-ACCIDENT ' MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: EMERGENCY VENTILATION DAMPER POSITION INDICATION TAG NO.: AH-382-KSI A, AH-383-KSI A, AH-384-KSIB, AH 746-ZS, AH-747-ZS, AH-748-ZS, AH-910-KSIB REF DWG: 308-847 Type and Category - D, 2 Range - On - Off Fan Lights; OP-CL Lights Environmental Qualificatior. Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy - N/A Power Source - UPS/DG Display - Indicated Lights in CR RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, 13, 29 REASON:
Dampers covered under this category are those used in ventilation systems for the following:
Emergency Diesel Generator Control Complex Decay Heat Pump Area Spent Fuel Cooling Pump Area The dampers in these systems are controlled from the fan start circuitry and do rot have individual control switches. Redundant systems are provided so that a single failure will not del' eat their safety function. Panel lights show when the fan circuitry is operating.
Back-up operational data is provided to operators by high quality commerci 1 grade low flow and high temperature alarms. The control complex dampers also have open position lights.
The above data should be adequhte to determine if an HV s'ystem is operational. !
Individual damper position would only be beneficial if isolation were required.
, 38 RET: Ontt MESP: Nuc Ops Eng ' 3rg S
DESIGN BASIS DOCUMENT Page 64 of 91 kN Crystal River Unit 3 3
BYSity H 4ME SYSTEM CODE ,
POST ACCIDENT MONITORING INSTRUMENTATION N/A.
PARAMETER:
VARIABLE: STATUS OF STANDBY F0WER
-TAG NO.:: EGOG -3A/3B VM & AM ON SSF INVERTER 3A/3B POWER AVAILABLE LIGHTS 4KV BUS 3A/3B VM ON SSF 480V BUS 3A/3B VM OF SSF
,. I?5V/250V 3A/3B F0WER.AVAILABLE LIGHTS REF DWG: N/A Type and Category - D, 2 Range - CR3 -
DG INVERTER 4160V 480V 250/125VDC 3A, 38 3A to 30 3A, sB 3A, 3B 3A, 3B Power Volts Amps Pwr Available Volts Volts Available Ind. Lts - R/G Ind. Lts - R/G NRC Plant Specific Environmental Qualification - Yes + Yes No -
Seismic Qualification - No not required, Quality Assurance - No -
No No -
Redundancy - Redundancy Based on Dual Buses Power Source - UPS -
Display - Indicated in CR RG 1.97 Position - Complies SOURCE:-
-0, 5 REASON:
Electrical meters for DGs, inverters and vital buses are important te monitor electrical system status.
t
/#~ RET:0911 RESP: Nuc. Ops Eno 900 397
Page 65 of 91 DESIGN BASIS DOCUMENT l
6YSTfM NAME 9m Nmer Crystal River Unit 3 POST-ACCIDENT MONITORING INSTRUMENTATION SYSitM CODE N/A 3
PARAMETER:
VARIABLE: CONTAINMENT AREA RADIATION - HIGH RANGE TAG NO,: RM-G29-RIR, RM-G30-RI, RM-G29-RI REF DWG: 205-049, RM-10 Type and Category - C, E, 1 Range - 1 to 108 R/hr Environmental Qualification - Yes Seismic Qualification - Yes Quality Assurance - Yes Redundancy - Yes - 2 Channels Power Source - IE Display - Indicated and Recorded in CR On Demand in TSC & EOF RG 1.97 Position - Complies SOURCE:
0, 4, 5 REASON:
Containment high range radiation monitors are important to detect and assess significant releases, and for emergency planning, t se RET: Octs. RESP; Nuc Ops Eng 900 397
-. -. -. . - -- - - - - . ~___ - .- ._ - . . . . . ..
1 u
DESIGN BASIS DOCUMENT Face 66 of 91 SYSitM ,d Apt N ystal River Unit 3 ""
3 SYSTEM CODE POST-ACCIDENT MON g ina INSTRUMENTATION N/A PARAMETERt VARIABLE: RADIATION EXPOSURE RATE INSIDE BUILDING OR AREAS WHERE ACCESS IS REQVIRED TO SERVICE EQUIPMENT IMPORTANT TO SAFETY TAG NO.: RM G4-RIR, RM-G9 RIR, RM G10-RIR REF DWG: 205-049, RM 02, RM 03, RM 04 Type and Category - E, 3 Range - 0.01 to 10 R/hr Environmental Qualification - N/A Seismic Qualification - N/A Quality issurance - N/A Redundancy - N/A Power Source - IE Display - Indicated and Recorded on MCB RG 1.97 Position - Complies SOURCE:.
O, 5, 10, 11 REASON:
! The following position is a justification developed by the BWOG Reg. Guide 1.97 Task Force.
NRC RG 1.97, Rev. 3 requires area radiation monitors inside buildings or areas where access is required to service equipment important to safety. The NRC identified purposes for this instrumentation are: " Detection of Significant Releases, Release Assessments, and. Long Term Surveillance." This is a Type E variable with the overall purpose of beir.g monitored as required in determining the n,ngnitude of the release of radioactive materials and continually assessing such releases. The required range for these monitors is.0.1 to 10 R/hr.
RG 1.97. describes areas of concern as those where access is required to service safety related equipment. This implies that this instrumentation may be used for purposes other than those described above, i.e., for Health Physics Purposes.
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-l Page 67 of 91 l
9%
SYSTEM N AME M
DESIGN BASIS DOCUMENT Crystal River Unit 3 "'***"
SYSTEV CODE 3
POST-ACCIDENT MONITORING INSTRUMENTATION N/A for purposes of determining the magnitude of releases, the area radiation exposure rate monitors are clearly of very minor importance. Determination of l
release magnitude is done by other Type E variables associated with release !
paths. There is no useable correlation between area exposure rate monitors and 1 amount of release. l Detection of significant releases by area radiation exposure rate monitoring is I secondary to that provide by the release path monitoring. Nonetheless, area radiation levels inside the plant are monitored to verify compliance with 10CFR20. These instruments are considerably more sensitive (1000x) than required by RG 1.97 and are sufficient for supporting the detection of significant releases.
Determinations of accessibility of equipment for service or long term surveillance is the function of health physics personnel, generally using portable instrumentation. Monitoring of recordings of area radiation ex)osure rates from the Control Room is not a substitute for this health p1ysics function. However, exposure rate monitoring equipment in areas outside containment have an u)per range of 10 R/hr, which is adequate for initial assessments of accessi)ility.
These ranges are based on background reading in the areas in which they are located. Should' personnel entry be required in areas where these monitors have gone off scale or indicate a high radiation area a Health Physics Escort would accompanypersonne'sintotheseareasusingportableinstrumentationtoassesg radiation -levels. The high range for portable instrumentation at CR3 is 10.
R/hr. We do not anticipate even under emergency conditions, sending personnel into radiation fields of this magnitude.
taa ME'; Optt RESP: feuc 00s. Eng 900 397
Page 6B of 91 DESIGN BASIS DOCUMENT ."S *"
Crystal River Unit 3 3 SYSTEM NAME SYSTEV CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT OR PURGE EFFLUENT, NOBLE GAS TAG NO.: AH-717 FIR, RM Al-RIR-1, RM Al-RIR-2, RM-Al-RIR-3 REF DWG: 205-005, AH-04; 205 049, RM-06 and RM-06A Type and Category - C, E, 2 Range - 2 x 10 6 to 4.5 x 107 p ci/cc Xe133; O -65,000 cfm (Design - 50,000 CFM)
Environmental Qualification - Yes Seismic Qualification - N/A Quality Assurance -
No - (Radiation monitoring equipment was originally purchased without Quality Assurance documentation. Future purchases will specify QA requirements.)
Redundancy - N/A Power Source - UPS/DG Display - Indicated and Recorded in CR RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
Noble gas concentration and vent flow rate is required to detect a breach of containment and significant releases.
1 88 RET: 00U RESP Nuc Ops Eng 900 397
DESIGN BASIS DOCUMENT Page 69 of 91 Crystal River Unit 3 3 SYsitM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A
. PARAMETER:
VARIABLE: REACTOR SHIELD BUILDING ANNULUS TAG N0.: N/A REF DWG: N/A Type and Category - E, 2 Range - N/A Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - N/A RG 1.97 Position - Not in CR3 design.
SGCRCE:
0, 5 REASGN:
N/A in CR3 design.
118 RET; Opts. AESE Nuc. Ops. Eng 904 397
. DESIGN BASIS DOCUMENT Pago 70 of 91_
Crystal River Unit 3 3 BYSTEM NAM ( SYSTCM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: AUXILIARY BUILDING NOBLE GAL I TAG NO.: AH-32-FIR, RM-A2-RIR-1, RM-A2-RIR-2 RM-A2-RIR 3 REF DWG: 205-005, t"-C ; 205-049, RM 07A l
Type and Category - C, t ;
Range - 2 x 10 to 4.5 x JJ' y ci/cc Xel33; 0-200,000 cfm (Design - 156,680 i cfm)
Environmental Qualification - Yes 1
Seismic Qualification - N/A
-Quality Assurance - No -
(The radiation monitoring equipment was originally purchased without . Quality Assurance documentation. Future radiation monitoring equipment will be purchased with the requirement to specify the applicable Quality Assurance practices.)
Redundancy - N/A Power Source - UPS/DG Display - Indicated and Recorded in CR Concentration also displayed on demand in the TSC and E0F common plant vent, Category E2, from Auxiliary Building.
RG 1.97 Position --Complies.
SOURCE:
0, 5 REASON:
l ~ Noble gas concentration and vent flow rate .is required to detect a breach of containm_ent and ;ignificant releases.
1 j-..
I 1 91.- RET: Optl. RESP; Nuc. Ops. Eng. 900 397 I
1
/] DESIGN BASIS DOCUMENT Paoe 71 of 91 Crystal River Unit 3
.Q
$YSTEM NAME SYSTEM CODE 3
POST ACCIDENT MONITORING INSTRUMENTATION N/A j
PARAMETER:
VARIABLE: CONDENSER AIR REMOVAL SYSTEM EXHAUST 1 TAG NO.: RM Al2-RIR-1 l REF DWG: 205-049, RM-05 '
Type and Category - C, E, 2
]
Range - 2 x 10*6 to 10 2 y ci/cc Kr85 l Environmental Qualification - Yes Seismic Qualification - N/A l Quality Assurance No - -(The radiation monitoring equipment was i originally purchased without Quality Assurance documentation. Future radiation monitoring equipment will be purchased with the requirement to speci fy the applicable Quality Assurance practices.)
Redundancy - N/A "ower Source - IE Display - Indicated and Recorded in CR On Demand in TSC & E0F
'RG 1.97 Position - Complies SOURCE:
0, 5, 10, 11, REASON:
Noble gas monitor in condenser air removal system exhaust is the key variable for detection of a breach of the primary to secondary loop boundary. 'The Auxiliary Building RM and flow meter are important to detect significant releases.
The udenser air removal system exhausts through 'the Auxiliary Building (See Pact 10) in which the flow The range of the monitor in the Auxiliary Building is 2 x 10'js monitored.7 to 4.5 x 10 y ci/cc Xe133.
The' range was corrected to ' confirm to the requirements of NUREG-0737, Item II.F.1.1.
149 6 RET:Optt RESP: Nuc Ops Eng 900 397 -
DESIGN BASIS DOCUMENT Page 72 of 91 9 '.m BYSTEM NAMg
?.F Crystal River Unit 3 """S**'
$YSTEM CODE 30ST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: VENT FROM SG SAFE"Y VA'_VES OR ADVs TAG NO.: Ri?-G25-RI, RM-G28 D./
REF DWG:- 205 049, RM-08 Type and Category - E, 2 Range'- 8.7 x 10'3 to 2.5 x 10 7 y ci/cc Xe133
- Environmental Qualification - Yes Seismic Qualification - N/A Quality Assurance - Yes Redundancy --N/A - 1 each ADV Power Source - IE Di spl a.v - Indicated in CR.
Recorded On Demand RG 1.97 Position --Complies-SOURCE:
0, 1, 2, 5, 10, 11, 30-REASON:
The four 24" main steam headers contain a ' total of 16 relief valves and 2 -
atmospheric dump valves. Each atmospheric dump valve discharge is monitored for radiation by monitors with readouts- in the Control Room. The system was calibrated -in terms of y ci/cc Xel33 in order to comply with NUREG-0737.
Radioactive releases are manually calculated.
This variable is only used during a S.G. tt.be rupture type accident. The results of this accident do not create a harsh ervironment. Therefore, they meet
- the environmental qualifications for the normal environment.
r 1.11a RTT: Gill. RESP: Nuc. Ops, Eng. 900 397 Page 73 of 91 DESIGN BASIS DOCUMENT
@m SYSTEM NAME
%wer Crystal P. ver Unit 3 SYSTEM CODE 3
POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: ALL PLANT RELEASE POINT - PAR'ICULATES AND HALOGENS TAE N0.: See Page 68 and 70 REF DWG: N/A Type and Category - E, 3 Range - 2 x 10 to 4.510 7p ci/cc Xel33 (RB); 0 65,000 cfm (RB)
(Design 50,000 cfm) 2 x 10 to 4.610, y ci/cc Xe133 (AB); 0-200,000 cfm (AB)
(Design - 156,680 cfm)
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - VPS/DG bisplay - Indicated and Recorded in CR RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To provide information regarding release of radioactive halogens and particulates, t Be RET: Opti. RESP: Nuc. Ops Eng 900 397
DESIGN t2 ASIS DOCUMENT l'aoe i4 of 91
- ( gI . . . . .
Crystal River Unit 3 SYSTEM CODE 3
JY$ TEM NAME POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARA,iETER: . Lg VARIABLE: AIRBORNE RADIO HALOGENS AND PAR'ilCULATES TAG NO.: N/A .
s REF DWG: N/A Type aric Category - E, 3 4 to 10'3 y ci/cc
, Range - 10
? Environmental Qualification - N/A Seismic Qualification - N/A -
Quality Assurance - N/A -g g
f Redundancy - N/A Power Source - Vital Bus Display - LAB ONLY K
_ Other - Portable sampling and onsite analysis.
RG 1.97 Pos; tion - Complies SOURCE:
0, 5 REASON:
To estimate release rates of radioactive materials during an accident, m
Various portable air samplers can be used to obtain the sample which is then taken to the Lab for counting. (Such as the Radevco H809 high volume air sampler. )
i Also have portable particulate monitors Eberline AMS-2 ar,'- AMS-3 on hand. (5) and (13) mini-scalers (Eberline) MS-2. Scaler up to 500K CPM, AMS-2 up to 50K m . CPM AMS-3 up to 100K CPM.
Once the sample is at the Lab, we have multi-channel gamma-ray spectrometer systems to provide the capability of onsite analysis.
r Er m- nwT: opii. RESP: Nuc. Ops Eng 900 397 -
u -.ga g-, y c :,-:. f.,9- . y ., 3
p.
DESIGN BASIS DOCUMENT face 75 of 3:
Crystal River Unit 3 3
$YSTEM NAyt $YSTEM CODC POST-ACCIDENT MONITORING INSTRUMENTATION N/A
, PARAMETER:
VARIABLE: PLANT AND ENVIRONS RADIATION TAG NO.: N/A REF DWG: N/A Type and Category - E, 3 i
Range - 10'3 to 103 R/hr Environmental Qualification - N/A
~
Seismic Qualification - N/A -
Quality Assurance - N/A Redundancy - N/A Power Source - Batteries i Display'- Portable RG 1.97 Position'- Complies SOURCE:'
0, 5,'10,;11 REASON:
To monitor radiation in plant and environs where range of normal monitor impractical for accident levels.
. Personnel not permitted in areas exceeaing 103 R/hr.
l Range of portable monitors is_ acceptable deviation to NRC required range of 10'3 3
to 10 R/hr.
l l
1 86 RET; Opti RESP: Nuc. Ops Eng 000 397
I DESIGN BASIS DOCUMENT Page 76 of 9? _
Crystal River Unit 3 )
3 ersuv uaue sysrev coot j POST-ACCIDENT MONITORING INSTRUMENTATION N/A 1
l PARAMETER:
VARIABLE: PLANT AND ENVIRONS RADI0 ACTIVITY TAG NO.: N/A REF DWG:
N/A Type and Category - E, 3 1
Range - Multi-channel Gamma-Ray Spectrometer Environmental Qualification - N/A Seismic Qualification - N/A
-Quality Assurance - N/A Redundancy - N/A Power Source - Batteries Display -
2 Channel portable gamma ray spectrometers are available _(Eberline SAM-2). Also a mobile multi-channel analyzer / computer contracted ,
with Dept. of Health and Rehabilitation.
RG 1.97 Position - Complies SOUKCE:
0, S REASON:
To monitor airborne radioactivity in the plant and environs where range of normal monitor is impractical;-for accident levels.
L o
i-Usa RET; Optt RESP: Nuc. Ops Eng 900 397
~
DESIGN BASIS DOCUMENT Page 77 of 91 Crystal R!ver Unit 3 3 SYSTEM NAME -
$YSTEM CODE POST-ACCIDENT MONITORING' INSTRUMENTATION N/A PARAMETER:
VARIABLE: WIND DIRECTION-
-TAG N0.: MM-13 MI, MM-18-SR, MM-14-MI, MM-19-SR REF DWG: .205 070, MM-01 and MM-02 Type and Category - E, 3 Range' 0 - 360' Environmental Qualification - N/A Seismic Qualification - N/A
. Quality Assurance - N/A Redundancy -'N/A Power Source - UPS/0G Display -
Indicated and Recorded in CR RG 1.97 Position - Complies S00RCE: -
0, 5 REASON:
Tofessess;impactofatmosphericreleases.
. It08 RET: Opti RESP: Nuc Ops. En.*. 900 397
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>ESIGN BASIS DOCUMENT Page 78 of 91 j Crystal River Utilt 3 3 SYSTEM N Aug SYSTEM CODE POST A. '0ENT MONITORING INSTRUMENTATION N/A PARANETER:
VARIABLE: WIND SPEED l TAG N0,: MM-ll-SI, MM 18 SR, MM-12-SI, MM-19-SR !
REF DWG: 205-070, MM 01 and MM-02 i Type and Category - E, 3 Range 50 M/sec
' Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy N/A Power Source - UPS/DG Display - Indicated and Recorded in CR RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To. assess impact of atmospheric releases.
l-1;88 RET: Optt RESP: Nuc. Ops Eng 910 397
DESIGN BASIS DOCUMENT Page 79 of 9}
""'S*"
Crystal River Unit 3 3_
lYSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: ESTIMATION OF ATMOSPHERIC STABILITY TAG NO.: MM 15-TI, MM-16-ii, MM-17-TI, MM 20-TR, MM-21-D REF DWG: 205-070, MM-04 1
Type and Category - E, 3 Range - -5' to +10*F Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - UPS/DG
-Display - -Indicated and Recorded in CR RG 1.97 Position - Complies SOURCE:-
0, 5, 10, 11 REASON:
To assess-impact of atmospheric releases.
In accordance with Regulatory Guide 1,23, Table 1, the measurement of temperature difference for estimating atmospheric stability requires a range j
from -l' 9'C to +4.0*C for the 100 meter height. The height distance between E temperature measuring points at CR3 is 142 ft. At this distance the RG 1.23 equivalent range of required temperature to estimate stability in degrees fahrenheit is -1.48'F to 3.12'F range, it is totally sufficient for providing an estimate of atmospheric stability.
r 1r88 RET: 00tl RESP: Nuc Ops En0- 900 391
DESIGN: BASIS DOCUMENT Page 80 of 91 _
. Crystal River Unit 3 3 SYSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:-
! VARIABLE: PRIMARY COOLANT AND SUMP - GROSS ACTIVITY (GRAB SAMPLE)
TAG Hn.: CA 54-CE
- REF DWG: 302-700 '
Type and Category - E, 3
-Range - 1 y ci/ml.to 10 ci/ml Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A-Redundancy -N/A Power Source - N/A
- Display - Local Panel RG 1.97 Position - Complies SOURCE:-
0, 5, 10, 11 REASON:-
To assess magnitude of radioactive releases, tr60 RET:00t1 RESP:Nuc Ops Eng 9tx) 3'J1
1 l
DESIGN -BASIS DOCUMENT Page 81 of 91 Crystal River Unit 3 3 SYSTEM N AME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRIMARY COOLANT AND SUMP - GAMMA SPECTRUM (GRAB SAMPLE)
TAG NO.: CA-54-CE REF UWG: 302-700 Type and Category - C, E, 3 Range - Isotopic Analysis Environmental Qualification - N/A Seismic Qualification N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - -Local Panel RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To verify mitigation of RC system high radiation from breach of fuel cladding, and to assess magnitude _of radioactive releases.
l 088 RET: Opti RESP: Nuc Ops Eng 900 3W
DESIGN BASIS DOCUMENT Page 82 of 91 Crystal River Unit 3 3
StBTEM N AME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:-
VARIABLE: PRIMARY COOLANT AND SUMP - BORON CONTENT-(GRAM SAMPLE)
TAG NC.: CA-56 CE REF DWG: 302 700 Type and Category'- E, 3 Range 6,000 ppm Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy N/A Power Source - N/A Display - Local Panel RG 1,97 Position - Complies '
SOURCE:
0, 5 REASON:
To-assess magnitude of radioactive releases.
L l
l i
t!68 RET: 0011 flESP: Nuc Ops Eng 900 197
DESIGN BASIS DOCUMLWT Page 83 of 91 Crystal River Unit 3 3 SYST[M NAM ( SYSTEM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRIMARY COOLANT AND SVMP - CHLORIDE CONTENT (GRAB SAMPLE)
TAG NO.: CA-57 CE REF DWG: 302-700 Type and Category - E, 3 Range. 20 ppm Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - Local Panel RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To-assess the magnitude of radioactive releases.
U8a RET; Opti. RESP: Nuc Ops Eng 900 391
Pago 84 of 91
, m DESIGN BASIS DOCUMENT " " *
- aower Crystal River Unit 3 3 SYSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRIMARY COOLANT AND SUMP - DISSOLVED H2 OR TOTAL GAS (GRAB SAMPLE)
TAG NO.: CA-55-CE REF DWG: 302-700 Type and Category - E, 3 Range 2,000 cc (STP) /KG Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance N/A Redundancy - N/A Power Source - N/A Display - Local Panel RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To assess the magnitude of radioactive releases.
W AET: Octi RESP: Nuc Oos Eng 900 397
DESIGN BASIS DOCUMENT Page 85 of 91 S Crystal River Unit 3 * * ' "
$YSTEM N AME SYSTEM cot >E POST A".CIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRIMARY COOLANT AND SUMP - DISSOLVED OXYGEN TAG NO.: N/A REF DWG: N/A
' Type and Category - E, 3 Range - N/A Environmental Qualification - N/A
-Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A-Display - N/A RG 1.97 Position - Not Mandatory SOURCE:
0, 5 REASON:
Ref: NRC Criteria Guidelines on NUREG-0737, item II.B.3, Post Accident Sampling System, dated July 12, 1982 l Criterion 4 of the reference stated that the measurement of oxygen is l recommended but is not mandatory.
I 1!88 RET: Optl. RESP: Nuc, Ops Efig 900 391
i i
DESIGN BASIS DOCUMENT Page 86 of 91 -
w:
OM Crystal River Unit 3 3 GYSTEM NAME - . SYSTEM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: PRIMARY COOLANT AND SUMP - pH (GRAB SAMPLE) !
TAG NO.: CA-56-CE REF DWG: 302-700 Type and Category E, 3 Range 13 Environmental Qualification - N/A
' Seismic Qualification - N/A Quality Assurance N/A Redundancy - N/A ,
Power Source - N/A Display - Local Panel RG 1.97 Position - Complies SOURCE:
0, 5
-REASON: 1
-To assess the magnitude of radioactive releases.
1 i-L L
liS8 RET: Opts. RESP:Nuc Ops. Eng 900 397
_ _ . - _ . . . - .. ~ . . ~- -
DESIGN BASIS DOCUMENT Page 87 of 9]
Crystal River Unit 3 3
SYSTEM NAME SYSitM CODE POST ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT AIR - HYDR 0 GEN CONTENT (GRAB SAMPLE)
. TAG N0.: WS-10-CR, WS ll-CR REF DWG: 205-062, WS-01, WS-02
-Type and Category - E, 3 Range 10%
Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source _- N/A Display - Local Panel-RG.1.97 Position - Complies SOURCE:'
0, 5 REASON:
l.
.To. assess the magnitude of radioactive releases.
l 1!O4 RET: Opu RESP Nuc Ops Eng 900 397
DESIG N B ASIS DOCU M ENT - Pa
-_ o* 88 of 91 9....... ..
$YSTEM NAME Crystal River Unit 3 SYSTEM CODE p
POST-ACCIDENT MONITORING INSTRUMENTATION N/A PAPAMETER:
VARIABLE: CONTAINMENT AIR - OXYGEN CONTENT TAG NO.: N/A REF DWG: N/A
-Type and Category - E, 3 Range - N/A Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - N/A RG 1.97 Position - 0xygen content is not required.
SOURCE:
0, 5 REASON:
The NRC RG 1.97 required that Containment Oxygen be measured from 0 to 30% by vol ume. The category of the variable is 3 and the Type. is E. A Type E variable is one that is " monitored as required for use -in determining _ the magnitude of the release of -radioactive materials, and for continuously assessing. such releases." For a Type E variable, Category 3 items are considered as backup variables.
In discussions with the NRC, it was determined that the NRC expects the operator L to; compare the oxygen percentage with the hydrogen percentage to determine if l
the hydrogen formed is being caused by radiolysis or by, metal-water reaction, l' which would be indicative of core damage.
-Percentage of oxygen in the containment atmosphere is classified as a Type E variable. . The definition of a Type E variable .is that it is to be " monitored as; require) for use in determining the magnitude of tne release of radioactive Ematerials, and for continuously assessing such release 4 However, the percentage of oxygen .in the containment atmosphere does not provide the
- necessary information to determine the magnitude of releases of radioactive materials. At best, it provides a very indirect means of arriving at an order of magnitude estimate. There are other systems in place that can be used for id88 RET
- 0p0 RESP: Nuc. Ops Eng 900 397
DESIGN BASIS DOCUMENT Page 89 of 91 m * * * "
Crystal River Unit 3 3
$YSTEM NAME SYSTEM CODE POST-ACCIDENT MONITORING INSTRUMENTATION N/A _
this purpose. Some of these would be Containment Area Radiation, Radioactivity Concentration or Radiation Level in the Primary Coolant, Analysis of the Primary Coolant, Gross Activity and Gamma Spectrum of the Primary Coolant and Containment Sump, and. Gamma Spectrum of the Containment Atmosphere. All of these systems provide a more direct means of determining the magnitude of the release and in addition most are Category 1 variables which means they are qualified to the same extent as a safety-related system.
The only other purpose of this variable then would be to allow the operator to -
determine what physical process is occurring that is forming the hydrogen in the 1 Containment. Radiolysis occurs at all times, and is a slow process. It causes oxygen and hydrogen to be formed from water, so the percentages of both would increase providing no other processes were happening.
However, during a LOCA, a large amount of steam would be generated along with various other gases and the percentage of both hydrogen and oxygen would tend to be in a very dynamic state, rendering a reasonable decision based on that information virtually impossible.
- A decrease in the percentage of oxygen along with an increase in hydrogen would be indicative of a metal-water reaction which in turn indicates core damage.
- Again, however, much better qualified instrumentation is available that provides a direct indication of core damage, rather than an indirect indication of core damage. Some of these systems'are: Hot and cold Leg Water Temperatures, Core Exit Temperature, Coolant -Inventory, Degrees of Subcooling, and the systems mentioned for determining the magnitude of the release. Additionally, the problems with a dynamic situation in the containment would also hold true in this case.
The requirement for providing the means of measuring containment oxygen content is not necessary because existing instrumentatinn provide more direct indication -
and are better qualified to perform the function of the required variable.
L V86 RET: OrAt RESP: Nuc Oct Eng 900 397
Page 90 of 91 m DESIGN BASIS DOCUMENT S'
osuu vue NMe.r Crystal River Unit 3
's7Etu coot 3
I POST-ACCIDENT MONITORING INSTRUMENTATION N/A PARAMETER:
VARIABLE: CONTAINMENT AIR - GAMMA SPECTRUM TAG NO,: WS-13-CE REF DWG: 302 694 Type and Category - E, 3 Range - Isotopic Analysis Environmental Qualification - N/A Seismic Qualification - N/A Quality Assurance - N/A Redundancy - N/A Power Source - N/A Display - Local Panel RG 1.97 Position - Complies SOURCE:
0, 5 REASON:
To assess the magnitude of radioactive releases.
1@l REY:Opti RESP: Nuc. Ops En0 900 397
DESIGN BASIS DOCUMENT Page 91 of 91
@m SYS?tM NAME W! Crystal River Unit 3 St& TEM CODE 3
POST-ACCIDENT MONITOR'.NG INSTRUMENTATION N/A SOURCE DOCUMENT
- 0. FPC letter #3F0884-07; 08/21/84
- 1. FPC letter #3Fil85-17; 11/15/85
- 2. FPC letter #3F0386 ll; 03/27/86
- 3. FPC letter #3F0687-09; 06/12/87
- 4. FPC letter #3F0188-03; 01/06/88
- 5. FPC letter #3F0388-18; 03/21/88
- 6. FPC letter #3F0688-06; 06/08/88
- 7. FPC letter #3F0988-06; 09/09/88
- 8. FPC letter #3F1089-26; 10/31/89
- 9. FPC letter #3F0190-06; 01/10/90
' 10 . NRC letter #3N1085-12; 10/24/85
- 11. NRC letter #3N0687-12; 06/16/87
- 12. BWOG RG 1.97 Task Force
- 15. MAR 82-05-03-20
- 16 . MAR 82-05-03-21
- 17. MAR 82-05 03-24 (Refuel 8)
- 18. MAR 83-11-14-01
- 19. MAR 84-08-10
- 20. MAR 84-08-10-02
- 21. MAR 84-08 10-04
-22. SER 50-302; 01/13/84
- 23. SRP-6.2.4 - 6F, SRP-6.2.4 - 6J, NUREG-0737
- 24. FPC letter #3F1289-12; 12/15/89
- 25. MAR 80-11-17-03
- 26. MAR 89-10-23-01A
- 27. MAR 82-05-03-16
- 28. MAR 82-09-19-02
- 29. MAR 84-08-10-07
- 30. MAR 85 10-16-02
- 31. SER 50-302; 9/6/83
- 32. EQ 89 2613 t/46 REL Opti RESP. Nuc Ocs Eng 900 397
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