ML18011A695
| ML18011A695 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/01/1994 |
| From: | Boska J, Costello L, Georgeson C CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18011A694 | List: |
| References | |
| HNP-I-INST-1045, HNP-I-INST-1045-R, HNP-I-INST-1045-R00, NUDOCS 9412010118 | |
| Download: ML18011A695 (66) | |
Text
SYSTEMS CALCe TYPE CAROLINA POWER & LIGHT COMPANY FOR Set Accu c Ca cu 1 L-473 th ou L-476 L- 8 L- 6 3 u -496 FOR S EARON S TECH S CS AND S OIN HESS &C YES NO SAFETY RELATED! 8 E3 SEISMIC C3 APPROVAL REV NO.
.. PREPARED BY DATE VERIFIED BY DATE PRO J. ENGINEER DATE PRIN. ENGINEER DATE I
t REASON FOR CHANGE:
REASON FOR CHANGE:
3 REASON FOR CHANGE:
9412010118 941123 PDR ADOCK 05000400 i P PDR
0 +r S List of-Effective Calculation Pages No. HNP-I/INST-1045 Page No.
Rev.
i 0
PAGE REV PAGE REV PAGE ii 3.
1 0
0 0
2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 19 0 20 0 21 0 22 0 23 0 24 0 25 0 26 0 ATTACHMENTS A1 0 A2 0 A3 0 A4 0
I Table W Contents Calculation No. HNP-I/INST-1045 Page No.
Rev.
ii 0
PacaPeo
- 1. 0 OB JECTIVE 2.0 LOOP FUNCTIONAL DESCRIPTION ~ 1
3.0 REFERENCES
4.0 INPUTS AND ASSUMPTIONS ~ 7 5.0 DETERMINATION OF UNCERTAINTIES 9 6.0 CALCULATION OF UNCERTAINTIES 10 7-0 DISCUSSION OF RESULTS 22 8.0 FIGURES 26
'IHIP\
z+
C ~
Computed by: Dates Carolina Power 4 Light Company Calculation IDc John P. Boska 6/1/94 HNP-I/INST-1045 Checked by: Dates Chris Geor eson Pg. 1 Rev. 0 6/1/94 CALCULATION SHEET TAR/PZD No. Files PCR-6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range I.evel:Low, Low-Low, and High-High Status c Prelim. Q Final QX Void 1 0 OB JEC~~
1.1 The ob)ective of this calculation is to establish the design basis for the steam generator (SG) narrow range (NR) level setpoints found in the Technical Specifications. These setpoints are found by taking the safety analysis limit (usually from the FSAR) and applying an amount in the conservative direction to account for the instrument channel inaccuracies (the total loop uncertainty) and then allowing for some additional margin. This calculation is being prepared to comply with CPQL commitments to Reg. Guide 1.105 as outlined in FSAR Section 1.8.
In addition, this calculation has been prepared to be consistent with the methodology outlined in ISA S.67-04.
2 ' LOOP FUNCTIONAL DESCRIPTION 2~1 Instrumentation is provided to indicate the narrow range level of the steam generators. The level transmitters are differential pressure transmitters, which measure the pressure difference between an external insulated reference leg. and the column of water in the downcomer region.
The reference leg is not sealed and is kept full of water by a condensate pot on the upper tap. The SG Low and Low-Low level trips protect the reactor from loss of heat sink. The SG High-High level trip protects the turbine and the steam lines from water impact damage.
3 ~0 ~RE 3~1 SHMPP Drawings 3 ~ 1.1 CAR-2166>>8-401 Sh.993 "Steam Generator Znstrumentation-CWD" ~
F 1.2 CAR-2166-8-401 Sh.994 "Steam Generator Znstrumentation-CWD".
3 ~ 1 ~3 CAR-2166-B-431 Sh.L-18 "Level Instrument Typical Impulse Piping Hook-Up To Local Instrument Rack".
3.1.4 CAR-2166-8-432 "Znstrument List" F 1 5 CAR-2166-G-450 "Containment Building E1.236'nstrument Arrangement".
3 ' ' CAR-2166M-451 "Containment Building E1.236'nstrument Arrangement".
3 ~ 1.7 CAR-2166-S-LFW0473 "Steam Generator Level Loop Diagram".
3 ~ 1 ~8 CAR-2166-S-LFW0474 "Steam Generator Level Loop Diagram".
3 ~ i+9 CAR-2166-S-LFW0475 "Steam Generator Level Loop Diagram".
Computed bye Dates Carolina Power a Light CospanY Calculation ID:
John P. Boska 6/1/94 HNP-I /INST-1045 IChecked bye Dates
'Chris Georgeson 6/1/94 Pg. 2 Rev. 0 CALCULATION SHEET TAR/PID Noi Pile:
PCR-6464 Pro)ect
Title:
Reactor Trip Setpoint Calculation
'alculation
Title:
Steam Generator Narrow Range LevelsLow, Low-Low, and High-High i
Status: Prelim. Final X Void 3.1+10 CAR-2166-S<<LFW0476 "Steam Generator Level Loop Diagram".
3.1 ll CAR-2166-S-LFW0483 "Steam Generator Level Loop Diagram".
3 ~ 1 ~ 12 CAR-2166-S-LFW0484 "Steam Generator Level Loop Diagram".
3 '.13 CAR-2166-S-LFW0485 "Steam Generator Level Loop Diagram".
3 ' ~ 14 CAR-2166-S-LFW0486 "Steam Generator Level Loop Diagram".
3+ 1 ~ 15 CAR-2166-S-LFW0493 "Steam Generator Level Loop Diagram".
3.1 ~ 16 CAR-2166-S-LFW0494 "Steam Generator Level Loop Diagram".
3.1 17 CAR-2166-S-LFW0495 "Steam Generator Level Loop Diagram".
3 ~ 1 ~ 18 CAR-2166-S-LFW0496 "Steam Generator Level Loop Diagram".
3 ~ 1 ~ 19 CAR-2166-S-2500 Section 90.1 "EQDP Instrument Loop Accuracy Calculations".
3 '.20 CAR-2166-S-2500 Section 8.18, 8.19 "Barton 764, Tobar 32DP1". Environmental Qualification Data Packages 3+1.21 CAR-2165-S-0544, "SFD-Feedwater System".
3 '+22 Emdracs 1364-46574 Sh.9 "Steam Generator Loop L-474 - IWD".
3+ 1+23 Emdracs 1364-46574 Sh.10 "Steam Generator Loop L-484 - IWD".
3+1.24 Emdracs 1364-46574 Sh.ll "Steam Generator Loop L-494 - IWD".
3 ~ 1.25 Emdracs 1364-46575 Sh.9 "Steam Generator Loop L-475 - IWD".
3.1 ~ 26 Emdracs 1364-46575 Sh.10 "Steam Generator Loop L-485 - IWD".
3 ' 27 Emdracs 1364-46575 Sh.ll "Steam Generator Loop L-495 IWD".
3 ~ 1 ~ 28 Emdracs 1364-46576 Sh.9 "Steam Generator Loop L-476 IWD".
- 3. 1+29 Emdracs 1364-46576 Sh.10 "Steam Generator Loop L-486 IWD".
3 '.30 Emdracs 1364-46576 Sh.ll "Steam Generator Loop L-496 - IWD".
3 1 ~ 31 Emdracs 1364-46577 Sh.25 "Steam Generator Loop L-473 - IWD".
3 '.32 Emdracs 1364-46577 Sh.26 "Steam Generator Loop L-483 - IWD".
3.1.33 Emdracs 1364-46577 Sh.27 "Steam Generator Loop L-493 IWD".
tl Computed by: Dates Carolina Power & Light Company Calculation ID s John P. Boska 6/1/94 HNP I/INST-1045
!Checked by: Dates Rev. 0 Pg. 3 1
Chris Georgeson 6/1/94 CALCULATION SHEET TAR/PID No Files PCR-6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles steam Generator Narrow Range LevelsLow, Low-Low, and High-High I
Statues Prelim. Final X Void 3 ~ 1 ~ 34 Emdracs 1364-96736, "Model D4 Steam Generator, Thermal and Hydraulic Design Report, Revision 2, 12/1/93" 3 1.35 Emdracs 1364-53067, Rev 1, Westinghouse Setpoint Methodology for Protection Systems, Shearon Harris (Revision 1), July 1985" 3 '.36 IS/1-FW-286 "Isometric for LT-01-FW-474-IW".
3 ' ~ 37 ZS/1-FW-287 "Isometric for LT-01-FW-475".
3 ~ 1.38 S/1-FW-288 "Isometric for LT-01-FW-476".
3 ' ~ 39 ZS/1-FW-290 "Isometric for LT-Ol-FW-484-IW".
3 ' '0 ZS/1-FW-291 "Isometric for LT-01-FW-485" ~
3+1+41 ZS/1-FW-292 "Isometric for LT-Ol-FW-486".
3 ~ 1 ~ 42 IS/1-FW-294,'Isometric for LT-01-FW-494-IW" ~
3+1 ~ 43 ZS/1-FW>>295 "Isometric for LT-Ol-FW-495".
F 1 44 IS/1-FW-296 "Isometric for LT-01-FW-496".
3 145 ZS/1-FW-412 "Isometric for LT-Ol-FW-473".
3 ' ~ 46 IS/1-FW-414 "Isometric for LT-01-FW-483".
3 ~ 1+47 ZS/1-FW-416 "Isometric for LT-01-FW-493".
3.2 SHNPP Updated FSAR 3+2 ~ 1 Section 6.2.2.2.1.2.2 c) "Lowest. Containment Temperature".
3 ~ 2 02 section 9 4 0 "Air Conditioning, Heating, cooling, andg
~
Ventilation System" .
3 ~2 ~3 Figure 3.11B-1 "Containment Building E1.221' Parameters During Normal & Post-Accident El.236'nvironmental Environments".
3.2.4 Figure 3.11B-20 "Containment Building El.221' Radiation Doses To Equip. During Normal & Post- El-236'ntegrated Accident Environments".
3 ~2 ~5 Figure 3.11.4-3 "DBA Temperature profile Inside containment (MSLB)".
3.2 ~ 6 Table 15.0.6-1, Trip Points and Time Delays to Trip Assumed in Accident Analysis 3 ~2 ~7 Section 15, Accident Analysis
< 1
AJ a
Computed bys Dates Carolina Power fc Light Company Calculation IDs John P. Boska 6/1/94 HNP-I/INST-1045 Checked bys Dates Chris Geor eson Pg. 4 Rev. 0 6/1/94 CALCULATION SHEET TAR/PID No. File s PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High Statuss Prelim. Final X Void@
3.3 SHNPP System Descriptions 3 ~3 ~1 SD-126.2 "Steam Generators, Steam Generator Water Level Control System".
3 ' ' SD-103 "Reactor Protection" 3.4 CP6L Design Guides 3 ~ 4+i DG-VIII.50 "Instrument Setpoints" .
3 ~ Q ~ 2 Design Basis Document 300, nstrument Set Points 3.5 Vendor Literature 3.5.1 VM-ONY " TT Barton Technical Manual".
3 ~5 2 VMMSF "Westinghouse Analog Controls".
3 ~5 ~3 VM-MWV "Indicators and Instruments".
3 ~5 ~4 VM-PYC "NSSS Process Instrumentation and Control System".
3 ~5 ~5 Westinghouse WCAP-8687 Supp.2-813 Rev.2 "Equipment Qualification Test Report 'Process Protection System".
3 ' ' VM-BFL "Tobar Technical Manual".
3.6 SHNPP Procedures and Scaling Docssaents 3.6 ' MST-Z0034 "Steam Generator A Narrow Range Level Loop L-473 Calibration" .
3 ~6 ~2 MST-Z0023 "Steam Generator A Narrow Range Level Loop L-474 Calibration".
3 ~ 6o3 MST-Z0024 "Steam Generator A Narrow Range Level Loop L-475 Calibration".
3o6 ~ 4 MST-I0025 "Steam Generator A Narrow Range Level Loop L-476 Calibration" .
3 ~6 ~5 MST-I0035 "Steam Generator B Narrow Range Level Loop L-483 Calibration" .
3.6.6 MST-Z0026 "Steam Generator B Narrow Range Level Loop L-484 Calibration".
3 ' ' MST-Z0027 "Steam Generator B Narrow Range Level Loop L-485 Calibration".
3.6.8 MST-Z0028 "Steam Generator B Narrow Range Level Loop L-486 Calibration" .
~ g
'omputed by: Data: Carolina Power 6 Light Coapany Calculation ID a John P. Boska 6/1/94 HNP-I/INST-1045 Checked by: Date: Pg. 5 Rev. 0 Chris Geor eson 6/1/94 CALCULATION SHEET TAR/PID No. File:
PCR-6464 Pro)ect Titles Reactor Trip Setpoint Calculation
~
Calculation
Title:
Steam Generator Naxrow Range Level:Low, Low-Low, and High-High I Status'relim. Final X Void 3 ~6 ~9 MST-Z0036 "Steam Generator C Nax'row Range Level Loop L-493 Calibration".
3.6 '0 MST-I0029 "Steam Generator Calibration".
C Narrow Range Level Loop L-494 3.F 11 MST>>I0030 "Steam Generator C Narrow Range Level Loop L-495 Calibration".
3.F 12 MST-I0031 "Steam Generator C Narrow Range Level Loop L-496 Calibration" .
3.6 13 SCN-175 "Steam Generatox' Narrow Range Level L-473".
4 3.6.14 SCN-040 "Steam Generator A Narrow Range Level L-474".
3 ' 15 SCN-043 "Steam Generator A Narrow Range Level L-475".
3 6 ~ 16 SCN-046 "Steam Generator A Narrow Range Level L-476".
3 ~ 6 ~ 17 SCN-176 "Steam Generator B Narrow Range Level L-483".
3.6+18 SCN-041 "Steam Generator B Narrow Range Level L-484".
3.6 '9 SCN-044 "Steam Generator B'Narrow Range Level L-485".
3 ' 20 SCN-047 "Steam Generator B Narrow Range Level L-486".
3.6.21 SCN-177 "Steam Genexator C Narrow Range Level L-493".
3.6 '2 SCN-042 "Steam Generator C Narrow Range Level L-494".
3 ' 23 SCN-045 "Steam Generator C Narrow Range Level L-495".
3.6 '4 SCN-048 "Steam Generator C Narrow Range Level L-496".
3.7 Industry Standards and Reference 3.7 ~ 1 ZSA Standard S67.04-1988 "Setpoints For Nuclear Safety Related Instrumentation Used Zn Nuclear Power Plants".
3.7 2 ISA Standard RP67.04 "Methodologiee For The Determination Of Setpoints For Nuclear Safety Related Instrumentation", Draft
~
9.
3.7.3 USNRC Reg. Guide 1.105 "Instrument Satpoints For Safety Related Systems".
3.7.4 ASME Steam Tables, Fifth Edition
~ ~
jl
. Computed by: Dates Carolina Power 4 Light Coapany Calculation ZDs John P. Boska 6/1/94 HNP-I/INST-1045 Checked bys Dates Chris Geor eson Pg. 6 Rev. 0 6/1/94 CALCULATION SHEET TAR/PZD No. Files PCR-6464
'ro)ect Titles Reactor Trip Setpoint Calculation
- Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High
, Status: Prelim. Final X Void 3.8 Other References 3.8 ~ 1 Equipment, Data Base System tEDBS) 3.8 ' Mechanical Calculation EQS-42, Rev 2, 9/22/86, SG Reference Leg Heat;Up.
3 ' ' Mechanical Calculation FW-022, Rev 0, 1/11/93, Evaluation of Steam Generator Level Setpoints" 3.8.4 Westinghouse Letter CQL-92-031, 6/18/92, "SG Water Level PMA Term Inaccuracies" 3i8 ~ 5 Proceedings of the 34th Power Instrumentation Symposium, June 1991, ZSA paper 91-722, "Delta>>P Level Measurement Systems" by Glenn E. Lang and James P. Cunningham.
3.8.6 Westinghouse Letter CQL-88-568, 5/23/88, "Veritrak/Tobar Transmitter Closeout" 3.8 ' FCR-P-4126, 6/3/85, "Reroute of FW Lines for Instrumentation of SGs" 3 ~8~8 Technical Specifications for Shearon Harris Unit 1, through Amendment 46, 3/3/94.
I 3 ' ' FCR-P-3637, Rev 2, 9/25/86, SG Reference Leg Insulation 3 ~ 8 ~ 10 Westinghouse Letter CQL-88-530, 3/7/88, "Equipment Qualif ication" 3.Soll PCR-6464, SG Water Level Inaccuracies 3e8 ~ 12 PCR-6986, T-Hot Reduction-3e8el3 Westinghouse Field Change Notice CQLM-10561 3 ~ & ~ 14 EMF-93-033(P), March, 1994, "Plant Parameters for Shearon Harris Nuclear Power Plant" 3 ' '5 EMF-93-163, March, 1994, "Shearon Harris Cycle 6s Disposition of FSAR Chapter 15 Events and Analysis of Plant Transients"
~ I Ccxnputod bye Datog Calculation John P. Boska 6/1/94 Carolina pmeer fa Light Company ZDc HNP I/INST-1045 IChecked bye Dates
- Chris Georgeson 6/1/94 CALCULATION SHEET Pg. 7 Rev. 0 TAR/PID No Files PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High Status! Prelim. Q Final QX Void@
4+0 I UTS AS ONS 4.1 Based on the scaling documents (eg. Ref. 3.6.18), the transmitters are scaled using the fallowing parameterse a reference leg temperature of 120'F and a SG process pressure of 983 psia. The typical range is 64 inwc to 230 inwc, so the span is 166 inwc. This varies slightly among transmitters. The high side of the transmitter is connected to the reference leg, and the output is 4'a at 0% level (maximum d/p) and 20 ma at 100t level (minimum d/p).
4.2 Unless specifically linked to a temperature, all to pressure in inches of water column (inwc) will be far inwc references at 684F.
4.3 Any uncertainty determined to be 10 times less than the magnitude of the greatest uncertainty will be considered insignificant and may be left out of this calculation.
4 ' When referring to a loop, the calculation is actually referring to the part of the loop that goes from the process being measured to the camparator (bistable) which provides input to the reactor protection systemo 4.5 The differential pressuro transmitters aro located the E1.236'evel of the Containment Building. This is an inside areaonwhich is exposed to temperature extremes from 804F to 1204F during normal operation and up to 380 F during an accident (Ref. 3.2.1, 3.2.3, 3.2.5]. The transmitters are Safety Class A. Only the SG low-low level setpoint is assumed to function during high energy line break (HELB) conditions (Ref. 3.2.7].
4.6 The PZC roam for all t is designed to maintain a temperature between 65 and 80~t operating conditions (Ref. 3.2.2]. The uncertainties associated with temperature and radiation in the PZC room are considered negligible per Ref. 3.5.4, and Assumption 4.3. The seismic effects on Westinghouse 7300 series cards in the PZC room are considered negligible per Ref.
3.5.5.
4.7 The Steam Generator narrow range level loops are classified as nuclear safety related. The loop components are expected to withstand both accident and seismic events. The HNP FSAR does not consider a design basis accident (DBA) occurring concurrently with a seismic eventf consequently, the uncertainties associated with a DBA will not be considered together with the uncertainties associated with a seismic event. Only those which represent a worst case condition will be considered.
4.8 The Steam Generator level differential pressure transmitters are ZTT Barton Model 764 and Tobar Model 32 3,483,493 only) with a typical maximum and calibrated span 166 inw Ref. 3.1.4, 3.6.13-3.6.24]. Uncertainties will be grou er for these transmittersg considering the most conservative in each case
I I I I4'
Computed by< Dates Carolina Power 4 Light Company Calculation IDc John P. Boska 6/1/94 HNP-I/INST-1045 Checked by<'ates Pg. 8 Rev. 0 Chris Geor eson 6/1/94 CALCULATION SHEET TAR/PID No Files PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High Status c Prelim. Q Final QX Void 4+9 Tolerance values given in percent maximum span will be converted to percent span by applying a factor of a turndown ratio (Max Span/Cal.
Span) or (166/166), which gives a value of 1.0 for all loops.
4.10 As an additional measure of conservatism, a margin will be included between the analytical limit and the trip setpoint.
4 ~ 11 There is no error associated with measuring the pressure of a liquid at the level of the transmitter, as opposed to measuring the pressure at the level of the lower tap since differential pressure is being measured and the sensing lines run together to the transmitter (which is lower than the lower tap) (Ref. 3.1.3).
4o12 The uncertainty associated with a change in the density of water in. the reference leg will be considered.
4 ~ 13 The uncertainties presented in this calculation represent. the deviation of the instrument reading from the actual parameter. For example, a negative error means that the instrumentation would read less than the actual SG level.
l Computed bys Dates e Calculation IDs John P. Boska 6/1/94 Carolina Power 4 Light Coapassy HNP-I / INST-1045
- Checked by: Dates jChris Pg. 9 Rev. 0 Geor eson 6/1/94 CALCULATION SHEET TAR/PID No Files PCR-6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation
Title:
Steam Generator Narrow Range LevelsLow, Low-Low, and High-High Statues Prelim. Final X Void 5 .0 DETERMINA 0 OF UN T INTIES The following uncertainties will be determineds F 1 Process Measurement Effect (pME) This will account for errors such as reference leg heating, process pressure and temperature change, downcomer subcooling and fluid velocity ef fects.
F 2 Primary Element Accuracy (PEA) - Since there are no venturis, elbow taps, orifice, etc. in these loops this term will be zero.
5 ~ 3 Sensor Calibration Accuracy (SCA) - The transmitter calibration accuracy, also known as the Reference Accuracy, the Sensor Measurement and Test Equipment Accuracy (SMTE) and Sensor Calibration Tolerance are all included in this term.
5 ' Static Pressure Effects (SPE) The change in the transmitter output as a result of the difference between static head pressures at operating and calibration conditions.
5.5 Sensor Temperature Effects (STE) The change in the transmitter output as a result of normal variation i.n the local temperature.
5.6 Sensor Drift (SD) - The change in transmitter output over the period between calibrations (typically 18 months +/-25%).
5 ~7 Rack Calibration Accuracy. (RCA) - The process instrumentation calibration accuracy, including the calibration of all modules up to and i.ncluding the bistable. The Rack Measurement and Test Equipment Accuracy (RMTE) and bistable calibration tolerance is included in this term.
5 ~8 Rack Drift (RD) - The change in process instrumentation output over the period between calibrations (typically 3 months).
5.9 Rack Temperature Effects (RTE) - The change in process instrumentati.on output as a result of normal variation in the local temperature.
5 ~ 10 Harsh Environment Effects (HEE) - The change in transmitter output due to a harsh environment (e.g. after a HELB). It is applied only to instrument channels which must survive a harsh environment.
5 11 combination of terms - All terms will be combined into a total loop uncertainty (TLU). Random uncertainties will be combined as described in Ref.
3.4.1, -using the method known as "square root, of the sum of the squares"- Bias errors will be given an'arithmetic sign (+ or -) and will be combined separately. A negative sign means that the bias is such that the indicated level will be less than the actual level.
lg Computed bye Dates 'arol,ina Power ! Light Company Calculation ID!
John P. Boska 6/1/94 HNP-I/INST-1045 Checked bye Dates Pg. 10 Rev. 0 Chris Georgeson 6/1/94 CALCULATION SHEET TAR/PID No Files PCR-6464 Project Titlet Reactor Trip Setpoint Calculation Calculation Titlet Steam Generator Narrow Range Level:Low, Low-Low, and High-High Status a Prelim. Final X Void 6 ~0 CALCULAT ONS 0 UNCER I IES 6.1 Symbols used H vertical distance between the SG NR upper and lower taps at normal operating conditions ~ 19.55 ft (234.6 in) (Ref. 3.6.18).
L actual water level in the SG above the lower tap (in ft)
H= vertical distance between the lower tap to the water level in the condensate pot (at the upper tap) at normal operating conditions 20 06 ft (240 73 in) (Ref. 3 6 18).
vertical distance between the water level in the condensate pot and the upper tap ~ 0.51 ft (6.125 in) (Ref. 3.6.18) (B~H-H)
PU water density in the reference leg used for calibration scaling ~
61.88 ibm/ft~ (120'F, 983 psia) (Ref. 3.6.18).
Pt. water density in the reference leg.
Pr saturated water density used for calibration scaling = 46.45 ibm/ft~ (983 psia).
saturated steam density used for calibration scaling 2.20 ibm/ft~ (983 psia).
Pr saturated water density at the process pressure.
p saturated steam density at the process pressure.
Pwr = water density in the vicinity of the lower tap.
g gravitational constant for the English Engineering units ~ 32.174 ft-ibm/lbf-sec-.
steam flow from one SG at 100'ower ~ 1129.6 ibm/sec (4.07 MPPH)
(Ref 3.8.3).
W fluid flow rate normal to the lo~erft~tap (ibm/sec)
A flow area at the lower tap 5.74 (Ref. 3.8.3)
CR+ a circulation ratio at 100% power ~ 2.13 (Ref. 3.1.34)
CR circulation ratio at this power level dpo ~ fluid flow losses in the downcomer above the lower tap ~ .1 psi (Ref. 3.8.3) friction and form loss factor (unitless)
~
~
+1%
~ II I
t=ws
Computed by> Datea Carolina Power 6 Light Coapany Calculation IDe John P. Boska 6/1/94 HNP I/INST 1045 Checked by! Dates Pg. 11 Rev. 0 Chris Georgeson 6/1/94 CALClKATIOM SHEET TAR/PID No Files PCR-6464 Pro)ect Titles Reactor Trip Setpoint calculation Calculation Title! Steam Generator Narrow Range Level!Low, Low-Low, and High-High Status< Prelim. Final X Void 6.2 PME Term 6 ',a. Reference Leg Temperature reference leg temperature Changes - The transmitter is calibrated for a of 120'F. During normal operations the reference leg temperature may vary from 100'F to 130'F. Since the SG low-low level trip is used in the analysis of a Feedline Break (FLB) accident, an additional error is required for those conditions. Ref.
3.8.2 reports that the average temperature reached in the insulated reference legs (initially at 120'F) at 5 minutes after a main steamline break accident (MSLB) is about 160.6'F (density ~ 61.1726 ibm/cubic ft.). This is conservative since containment heats up less on a FLB, and FSAR section 15.2.8 shows the reactor trip on SG low-low level at less than 1 minute after the FLB. This is a bias error term, not a random error term. The error term- is calculated as followers The transmitter is calibrated by setting the d/p at 0% level to be 4ma and the d/p at 100% level to be 20ma. The maximum d/p is at 0% level (the transmitter high side is connected to the reference leg).
Calibrated dP (at 0% level) ~ pressure in the reference leg pressure in the steam generator.
<cpcc ~~c - <cp~ ~Fc Since g/g, is numerically equal to 1 for this application, these equations but it still is needed to derive the correct it units.
will be dropped from Calibrated hP (at 0\ level) -
H(pcc - p~)
Calibrated hP (at 100% level) Hc pcs - (Hpa + Bp~)
Calibrated span ~ hP (at Ol level) - dP (at 100% level)
~ Hpic - Hp~ - Hpcc + (Hp+ Bp~)
~ Hpa Hv Py + Bpge (B~Hc,-H)
Hp> - Hc p~ + H<p~ - Hp~
H(pr " p) dP(at level L) ~ pressure in the reference leg - pressure in the steam generator Hcpcc - [Lp> + (H< - L) pi ]
J I I
Computed byt Dates Carolina Light. Company Calculation IDt Penner 4 HNP-I/INST-1045 John P. Boska 6/1 94 Checked byt Date t Pg. 12 Rev. 0 Chris Gear eson 6/1/94 CALCULKTIOH SHEET TAR/PID No. File!
PCR-6464 Project Titlet Reactor Trip Setpoint calculation Calculation Titlet Steam Generator Narrow Range Level:Low, Low-Low, and High-High Status: Prelim. Final X Void fractional level hP(at 0% level) -hP(at level L)
Hcpcc H p
<<cpcc - Lptc H'P + LP ] L H(pt - pc,) H Assume the temperature of the reference leg changes (pic goes to pi).
Error due to the reference leg temperature change ~ ez (in 0 level) e~ ~ (new fractional level - previous fractional level) x 100 new fractional level ~ calibrated hP (at 0%) - new hP (at L) calibrated span HcPcc H P (Hcpc Lptc HtP + LP H(ptc Pge)
Hc(Pcc Pt) + L(ptc P H(Ptc Pgc)
Ht(pcc Pt) + L(pt P ) L(pt P )
(100]
ee <<Ptc Pyc) c(Pcc " Pt.)
H(ptc Pcc) e~ only depends on the density of water in the reference leg.
At 130 F, 983 psia, p~ 61.73 ibm/ft~
(20.06) (61.88 - 61.73) (100]
ee ~ 55 (46 ~ 45 - 2 20)
~
+ 35'9 At 100'F, 983 psia, p62.19 ibm/ft~
(20.06) (61.88 - 62.19) (100]
~ 55 (46e45 - 2+20) 72'9 At 160.6F, p ~ 61.17 (MSLB analysis, Ref. 3.8.2)
(20.06) (61.88 - 61.17) (10p] +1 65 19.55 (46o45 2.20)
4%
F E
Computed by: Dater Carolina Power r'ight, CoIspany Calculation IDs John P. Boska 6/1/94 HNP-I / INST-1045 Checked by: Dates Pg. 13 Rev. 0 Chris Georgeson 6/1/94 CALCULlLTION SHEET TAR/PID No File PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelrLow, Low-Low, and High-High Statues Prelim Final X Void Q 6.2.b. Process Pressure Variations - The transmitter is calibrated for a saturated steam/water condition of 983 psia. However, the SG pressure varies with power, reaching a high of about 1106 psia (557'F) at 0\
power and a low of about 869 psia (528'F) at 100% power. This introduces an error at the other operating conditions. This is a bias error term, and is calculated as follower Calibrated AP at 0% level ~ Hq (p~ - ps,)
Calibrated span ~ H (pq p~)
Fractional level at the calibration point = I H
Fractional level at the new condition ~
(calibzaced hp ac 0%level) - (ALP ac new level) cali braced span Hept.e H P ) - (H Pcc (~pr + (Hc L) p ])
(Prc Pgc) r(p H(P rc Pre) fractional level at) fractional level at e~ ~ the new condition I the calibration pointl (100]
Hs(p P + L(pr P )
[100]
H(pre - Pg ) H This error varies with SG pressure and 983 psia ( the calibration point ) .
SG level. It will be zero when the SG is at Power SG Pr L(ft)
Pressure (0 level)
(psia) 1106 45.51 2.51 0 (0%) 0 72%
1106 45 51 2.51 7.53 (38.5%) -.37%
oa 1106 45 51 2.51 16.11 (82.4%) -1 61%
1106 869 45 '1 47.35.
2.51 1.92 19.55 (100%)
0 (0%)
-2
-.65%
11%
100%
'3
~
100% 869 47 '5 1~92 7 (38 5%) 0 39%
100% 869 47 '5 1.92 16 11 (82 '%) 1.55%
100% 869 47.35 1.92 19.'55 (1004) 2.02%
25% 1047 45 95 2 36 16. 11 (82.4%) -0.85%
25% 1047 45 '5 2 36 19.55 (100%) -1 ~ 12%
a
~
~ P 1
A
I ~ ~
- Computed by
- Dates Carolina power S Light Company
'alculation IDs John P. Boska 6/1/94 HNP-I /INST-1045 Checked bys Dates Pg. 14 Rev. 0 Chris Georgeson 6/1/94 CALCULATION SHEET TAR/PID No File:
PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High
'tatus s Prelim. Final X Void 6.2.c. Downcomor Subcooling Variations - the transmitter is calibrated for a saturated steam/water condition of 983 psia. However, because some feedwater is injected at the auxiliary feedwater nozzle, the density of the water in the downcomer is somewhat more than what was assumed for the calibration. This will produce a positive error (the indicated level will be higher than the actual level). This is a bias error tenn, not a random error term.
Since the auxiliary feedwater nozzle is high in the SG, with a discharge pipe which directs the water upward, it will be assumed that the feedwater mixes uniformly with the recirculation water from the steam separators. .his will produce an average density o the water in the downcomer. The error term is calculated as followss Fractional level with subcooled downcomer ~
(calibraced hP ae 04 level) - (IP vi th subcooled downcomer) calibraced span Hs(psc " p ) [Hspm (Lpn + (Hs ]p )
H(p rc Pyc)
Hs,(P P ) + L(per P )
H(pr,- p )
Fractional level at the process pressure ~
Hs(p P ) + L(Pr P fractional level with) ( fractional level at e, subcooled downcomer I l the process pressure [100]
H (p - p ) + L(p - p ) H (p - p ) + L(pr - p )
H(pre - Pg ) H(pre - Pg )
L ( pn P r) (100]
(Prc Pgc)
This error varies with power level and with SG level. p~ is calculated as described in Ref. 3.8.3. The maximum error is at 100% power.
~ 4
~a
Computed by> Dates Carolina Power 4 Light Company Calculation ID t John P. Boska 6/1/94 HNP-I / INST-1045 Checked bye Dates Chris Gear eson Pg. 15 Rev. 0 6/1/94 CALCULATION SHEET TAR/PID No Files PCR 6464 Project Titles Reactor Trip Setpoint Calculation Calculation
Title:
steam Generator Narrow Range Level:Low, Low-Low, and High-High Status< Prelim. Q Final X Void Power SG Pressure Pr L(ft) BI (psia) (0 level) 100% 869 47.35 48 ' 0 (0%)
100% 869 47.35 48 2 7.53 (38 5%) 0 '4%
100% 869 47.35 48 2 16 11 (82 '%) 1.58%
100% 869 47 35 48. 2 19.55 (100%) 1 92%
25% 1047 45.95 46.2 16 11 (82 4%) 0 47%
25% 1047 45.95 46 ' 19 55 (100%) 0 '6%
6 '.d. Fluid Velocity Effects - The transmitter is calibrated for a static head of water. However, at power there is water flowing dawn the downcceer past the lower tap (the upper tap is in the steam space). The fluid velocity creates a reduced pressure at the lower tap. This will produce a negative error (the indicated level will be less than the actual level). This is a bias error term, not a random error term. The error term is approximated as follows (using Bernoulli's equation for frictionless, noncompressible fluids) s a'i r 2gc +
2gc
+ pZ a pz r~~ cr t gc Va 2gc
+ Pa Pa Since the static head hp has already been accounted for, only the hp associated with flow losses will be calculated. Since the flow area above the downcomer is much larger than the flow area in the dawnccear, initial velocity vl ~ 0 Also'i p~ Per 2
p, a v~
+ p~
pn 2gc Pn (ug-ui) pn ( 2 ) Vg 2
g+p W
p~ V2 Vg hP ~
P err
( Pm'
) ( )~
>8 Par 2F~
I i i ~
4
Computed bys Dates Carolina Power t Light Company Calculation IDs John P. Boska 6/1/94 HNP-E / INST-1045 Checked by: Dates Chris Georgeson 6/1/94 CALCUZATXQN SHEET Pg. 16 Rev. 0 TAR/PZD No. Files PCR-6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles steam Generator Narrow Range Levels Low, Low-Low, and High-High Status: Prelim. Q Final X Void Q e
hP [100]
calibraeed apaa gc
(-) '100)
Parr H(Ps'c Pyc>
Since frictionless flow does not account for flow losses in the downcomer, form it is recommended to increase this error by a friction and loss factor, 1 + Q. An equation for Q is given in reference 3.8.5.
288 g~ p~ hP>( )
V~ CR~
The 288 includes the conversion factor of 144 in/ft, so that hPe is in
's psi0 At 100% power, 4PD = .1 psi, p~ = 48.2 ibm/ft (see Ref. 3.8.3), so Ks ~
288(32 174) (48 2) ( 1) ( ~ 25 (1129 6) (2 13)
~ ~
.25 will be used for all power levels, since p~ and APE are the only terms that vary and they do not vary much with the power level.
"(-) (1 + Ki)
.25 (100) 2gc Pn >(Prc Pyc)
The fluid velocity error varies with power level. W and p~ are calculated using the methods of Ref. 3.8.3. W ~ water from the steam separators + water from the AFW nozzle ~ (CR-l)(steam flow) + .2(feedwater flow).
4 Computed by:
e Date: Calculation IDc John P. Boska 6/1/94 Carolina Pcnier k Light Company HNP-I/INST-1045 Checked by: Dates Pg. 17 Rev 0 Chris Gear eson 6/1/94 CALClKATZOM SHEET TAR/PID No Files PCR 6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range Level:Low, Low-Low, and High<<High Status'relim. Final X Void Power CR Feed Temp e
(
ibm )
sec (P) 0% -0 45 ~ 6 0 -0 N/A 80 20% 2462.5 46 ' -9.0% 45 ' 11.7 280 251K 2513 4 46.0 -9 '% 56.5 9 ' 310 30% 2507.7 46 ~ 1 -9+3% 67 ' 8' 330 50% 2372.2 46.5 -8.3% 113 0 5.0 370 75% 1990 9 47.3 -5. 7% 169. 4 3.15 400 100% 1502 4 47 ' -3+2% 225.9 2 ~ 13 435 This method assumes uniform downward flow around the downcomer, which is conservative. On the cold leg side of the downcomer, where the level taps are located, the preheater section blocks part of the entrance to the tube bundle and main feedwater is flowing into the preheater section. This means W is smaller in the vicinity of the. level taps. However, this can not, be quantified without detailed computer models, so uniform flow will be assumed.
I P J
4 f 1
'1 I
~ I ~
Computed by> Dates Calculation IDs John P. Boska 6/1/94 Carolina Power 6 Light Company HNP I / INST 1045
'Checked by: Date~ Pg. 18 Rev. 0
~Chris Georgeson 6/1/94 CALCULATION SHEET TAR/PID No. Files PCR 6464 Project Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High Statues Prelim. Final X Void 6.3 Sensor Cal ration Accurac SCA ITT Barton Model 764 or Tobar Model 32DP1, differential pressure transmitter:
As stated in Ref. 3.5.1, the reference accuracy is t 0.5% of calibrated span.
This includes the combined effects of linearity, deadband, hysteresis and repeatability. There are no humidity effectsg these transmitters can operate within their reference accuracy for 5-95% humidity. Since these transmitters will be within their reference accuracy following a seismic event (Ref.
3.1.20), there is no seismic allowance.
Sensor Measurement and Test Equipment (SMTE) Inaccuraciess The calibration of this transmitter depends on a digital Heise pressure gauge (Model 710A) for input and a Fluke multimeter (Model 8600A) to measure the output. (See Ref. 3.6.2.). The accuracy of the pressure gauge is 4 0.835 inwc.
The span of this transmitter is 166 inwc. The accuracy is a 0.50% span. The a lv to Sv signal (4-20ma)s accuracy of the multimeter is a 0.01 vdc. Converting this to percent span for a0.01v ( 1004 4v )
~ x0.25%
Calibration Tolerancec As stated in Ref. 3.6.1 - 3.6.12, the allowable range during calibration is
~0.02v. Converting this to percent span, for a lv to 5v signal (4-20ma)s a 0.02v x 100%
= ~ 0.50% span Therefore, SCA ~ a0.5 i.56 a0.5 ~ 41.56% span (a random error) 6.4 Static Pressure Efiects (SPE)
As stated in Ref. 3.5.1, static pressure effect is a0.2\ of span per 1000 psig. The maximum SG pressure is limited by the SG safety valves. There are 5 safety valves with staggered settings. The highest setting is 1230 psig (Tach Spec 3.7.1.1). The sensing line to the transmitter is at most 74 ft. high.
This adds (74 f(:) (62.2 2hng>
) (
1 144 fe' jn~ )
32 psi. The maximum pressure is 1230 + 32 ~ 1262 psig.
SPE a 0.2%( 1262 1000 ) = w 0.25% span
I \t lh
Computed bye Dates Carolina Power 4 Light calculation ID a Company I/INST 1045 John P. Boska 6/1/94 HNP Checked bye Dates Pg, 19 Rev 0 chris Geor eson 6/1/94 CALCDLATIOM SHEET TAR/PID No Files PCR 6464 Project Titles Reactor Trip Setpoint Calculation Calculation Tltlet Steam Generator Narrow Range Levels Low, Low-Low, and High-High Status c Prelim. Q Final QX Void 6.5 Sensor Temperature Effects (STE)
The temperature inside containment in the vicinity of this transmitter may vary from 80'F to 130'F. The temperature coefficient is kl% per 100'F. (Ref.
3.5 1)~ ~
STE ~ aO 50%
There was some concern in the past with a thermal non-repeatability problem on Barton transmitters, but that was fixed by a factory modification. (Ref.
3 ' 13) ~
6.6 Sensor Drift (SD) ~ ~p~.
As stated in Ref. 3.5.1, dri.ft is al.00% of the . per year.
The normal calibration cycle for this transmitter is 18 months, but may be extended to as long as 22 months. Allowing for a 24 month calibration cycle, 1% drift in the first year followed by 1% drift in the second year:
SD ~ (1 + 1 )>> ~ 1.41% span 6.7 Rack Calibration Accuracy (RCA)
As stated in Ref. 3.1.35, RCA (except for the bistable) ~ 10.5% span Rack Measurement and Test Equipment (RMTE) Inaccuraciesa A digital voltmeter a is used to measure the input voltage. The accuracy is iO 01 vdc so RMTE iO 25\
Calibration Tolerancee As stated in Ref. 3.6.1-3.6.12, the allowable range to set the bi.stable is -.01v, +.02v for the low-low 'level trip and i.02v for the low level and high level trip. Converting this to 0 span, for a lv to 5v signal (4-20ma) a 1
.Olv x 100\4v
~ .25% span *.02v x 100\
~ a0.50\ span Total RCA ~ 11.00% span.
6.8 Rack Drift (RD)
As stated in Ref. 3.1.35, RD a i1.00\ span.
6.9 Rack Temperature Effects (RTE)
As stated in Ref. 3.1.35, RTE ~ a0.50% span
I I L J
~4
Computed bys Dates Carolina power a Light CoaEsany calculation ID s John P- Boska 6 1 94 HNP-I/INST-1045 Checked bys Dates Chris Geor eson 6/1/94 Pg. 20 Rev. 0 CALCQLlLTIQS SHEET TAR/PID No. Files PCR 6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-Hi.gh Statues Prelim. FinalQX Void 6.10 Harsh Environment Effects (HEE)
The only safety analysis for high energy line breaks which assumes a reactor trip on SG level is the Feedline Break (FLB) analysis. The reference leg heating effects were already calculated in section 6.2.a. The maximum effect is ez ~ +1.65% span. The transmitter may experience a temperature increase.
The error has been verified to be less than a10% error. (Ref. 3.1.20)
HEE ~ i10% e~ ~ +1.65t Cable insulation resistance is affected to some extent, by a FLB. Since the analysis vas done '"r a MSLB, this error is conservative. Since the leakage current increases the loop current, the error is positives E~ ~ +0.53%
6.11 Total Loop Uncertainty (TLU)
(SGL) + (SD) + (STE) + (SPE) + (RCA) + (RD) + (RTE) plus bias terms.
6 ~ lloa For the FLB analysis (the SG low-low level setpoint),
~
(1.56) + (1 41)
~ + (0.5) + ( ~ 25) + (1 0)
~ + (1 0)
~ + (0 5)
~
2 64%
+1.65% (e~ at 160.6'F)
+0.39% (e~ at 100% power, 38.5% level)
+0.74\-(e, at 100% power, 38.5\ level)
+0.53% (em for HELB)
+10% (HEE for HELB)
TLU ~ + 15.95t (SG low-low setpoint)
The SG loss of feedwater accident is most severe at 100% power, especially since the mass of water in the SG is lowest at 100'ower (Ref 3.1.34). Therefore, the worst case bias terms for 100\ power are used. Since a negative error is conservative (it means the indicated level is less than the actual level and the reactor will trip sooner)>
the bias for fluid velocity effects is ignored.
0
<<4
'1
~ ~
i Computed by<
John P. Boska Dates 6/1/94 M~1~ P~r Mght ~~+ i Calculation ZDc HNP-I/INST-1045 Checked bys Date: Pg. 21 Rev. 0 Chris Geor eson 6/1/94 CALCULATZ0N SHEET
, TAR/PID No. Files PCR-6464 Pro)ect Titles Reactor Trip Setpoint Calculation I
I Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High Status c Prelim. Final X Void 6 ~ 11.b. For the SG low level setpoint (loss of normal feedwater),
TLU ~ i 2.64% plus bias terms
+2.64m
+0.35% (e~ at 130'F)
+0.39% (e~ at 100% power, 38.5% level)
+0.74% (e, at, 100% power, 38.5% level)
TLU ~ +4.12%
Since the SG low level setpoint is not required for reactor protection during a high energy line break (HELB), no harsh environment effects are required. To be conservative, the fluid velocity effects are not
'ncluded.
6 ~ 11.ci For the SG high-high level setpoint, TLU ~ k2.64% plus bias terms.
A negative error will cause the indicated level to be less than the actual level, so the largest negative errors at levels close to the setpoint will be considered. The fluid velocity error of -9.4% at 251 power means that 25% power will be the limiting case.
TLU ~ -2.64%
-0 '2% (e~ at 100'F is conservative)
-0 85% (e at 25% power, 82.4% level)
+0 '7% (e, at 25% power, 82.4% level)
-9.4\ (e, at 25% power)
TLU ~ -13.14%
Since the SG high<<high level setpoint is not required for reactor protection during a HELB, no harsh environment effects are required.
+ sa Computed by: Date: Carolina Power 0 Light Coapany Calculation ZDs John P. Boska 6/1/94 HNP-Z/ZNST-1045 Checked by> Dates Pg. 22 Rev. 0 Chris Geor eson 6/1/94 CALCDLATZON SHEET TAR/PID No File!
PCR-6464 I
I I
Pro)ect
Title:
Reactor Trip Setpoint Calculation
- Calculation Titles Steam Generator Narrow Range Level
- Low, Low-Low, and High-High I
I Status: Prelim. Final X Void 7.0 Discussion of Results To determine the Technical specification parameters, the following terms will be usedc S = Sensor error term ~ SCA + SD (in 0 span)
A ~ the sum of the squares of all random errors that are not associated with SCA, SD, RCA, or RD.
SAL ~ Safety Analysis Limit TS ~ .rip setpoint in Tech Specs TA Total Allowance TS-SAL (in 0 span)
Margin ~ TA TLU T ~ Rack trigger value ~ .TA - [(A+S')" + all bias errors] or (RD+RCA),
whichever is less.
AV ~ Tech Spec Allowable Value TS - T (this allows for rack'rift but has no allowance for sensor drift).
Z ~ Q + any bias error terms, (in 0 span), the statistical suamation of errors excluding those associated with sensor drift, rack drift, sensor calibration accuracy, and rack calibration accuracy.
~
I )
I'
Computed bye Datsun Light Calculation ID t John P. Boska Carolina Power 4 Coapany I/INST-1045 6/1/94 HNP Checked by: Dates Rev. 0 Pg. 23 Chris Georgeeon 6/1/94 CALCULATION SHEET TAR/PID No Files PCR-6464 Project Titles Reactor Trip Setpoint calculation Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High Status> Prelim. Q FinalQX Void 7 ' SO w- ve S ~ SCA + SD ~ 1.56 + 1.41 ~ 2.97%
(0.25)i + (0.50)~ + (0.50)i 0.56%
TS ~ 38.5% (Ref. 3.8.8)
SAL ~ 19. 3% (Ref . 3.8. 14)
TA ~ TS - SAL ~ 19.2%
T = RD + RCA 1.0 + 1.0 2.0% span 2 ~ A" + all bias terms (0.56)" + 1 ~ 65 + .39 + .74 + .53 + 10 14.06'pan AV s TS - T ~ 38.5% 2.0% a 36.5% span Margin ~ Th - TLU ~ 19.2% - 15.95' 3.25%
comparison with current Tech Specs (Ref. 3.8.8)s TS N/A 38 5%
AV 36 '% 38.0%
S 2.97% 1 '%
2 14 06% 18 18%
TA 19. 2't 19.2%
Since the calculated values show margin to the Tech Spec trip setpoint, there is no need for a Tech Spec change.
C lf
Computed bys Dates Light Calculation IDs Carolina Power 4 Coapany HNP-I/INST-1045 John P. Boska 6/1/94 Checked by> Dates Pg. 24 Rev. 0 Chris Geor eson 6/1/94 CALCULATION SHEET TAR/PID Noi Pile:
PCR 6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High Statuss Prelim. Final X Void d s S ~ SCA + SD ~ 1 ~ 56 + 1.41 ~ 2.97%
(0 '5)s + ( 5)' (
5)'.56%
TS ~ 38.5% (Ref. 3.8.8)
SAL ~ 19.3% (Ref. 3.8.14) [Not used in Safety Analysis but use same value as SG Low Low SAL for conservatism)
TA ~ TS - SAL ~ 38.5 19.3 ~ 19.2% span T ~ RD + RCA 1.0 + 1 0 2.0% span Z ~ A" + all bias terms 0 56)s + 35 + 39 + 74 2.23% span AV ~ TS - T ~ 38 '% - 2 '% ~ 36 USE span Margin,~ TA.- TLQ. ~ 19.2\ 4.12% ~ 15.08%
Comparison with'urrent Tech Specs (Ref. 3.8.8)
C te Cu e t Tec'%
S TS N/A 38 AV 36 5% 36 '%
8 2.97% 1 '%
Z 2.23% 6.68%
TA 19 '% 19 '%
Since the calculated values show margin to the Tech Spec trip setpoint, there is no need for a Tech Spec change.
[ ~
y4 h
lk
'h
Computed bye Dates carolina power a Light Colipany Calculation IDx John P. Boska 6/1/94 HNP-I /INST-1045 Checked by> Dates Chris Geor eson 6/1 94 CALCDLATIOM SHEET Pg. 25 Rev. 0 TAR/PID No. Pile!
PCR-6464 Pro)ect Titles Reactor Trip Setpoint calculation Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High statusc Prelim. Q Final X Void Q 7 ~3 SO I
S > SCA + SD > 1 56 + 1.41 > 2.97%
(0.25)~ + (.5)i + (.5)i 0.56%
TS ~ 82.4% (Ref. 3.8.8)
SAL = 97.4% (Ref. 3.8.14, p. 2-32)
TA ~ SAL TS ~ 97.4 - 82.4 ~ 15.0%
T > RD + RCA 1.0 + 1.0 2.0% span 2 ~ A" + all bias terms (0.56)>> + .72 + .85 - .47 + 9.4 11.25% span AV ~ TS + T ~ 82@4 + 2 ' ~ 84 '
Margin ~ TA - TLU ~ 15.0% - 13.14% ~ 1.86%
This calculation shows that margin exists to the Tech Spec trip setpoint based upon the TA of 15% for the SO high high level provided by the Cycle 6 fuel vendor.
Licensing plans to submit a proposed revision to'he HNP Tech Spec. Table 3.3.4 based upon this information.
Comparison with the current Tech Specs (Ref. 3.8.8)
TS
~C~t~
N/A 82 4 S c AV 84.4 84 2 S 2.97 1.5 2 11 25 4.28 TA 15.0 7~1
( I ol l a
Computed by> Dates carolina power 4 Light Company Calculation IDe John P. Boska 6/1/94 HNP-I / INST 1045 Checked by< Dates Chris Geor eson Pg. 26 Rev. 0 6/1/94 CALCULATION SHEET TAR/PID Noi Filet PCR 6464 Pro)ect Titles Reactor Trip Setpoint Calculation Calculation Titles Steam Generator Narrow Range LevelxLow, Lo'w-Low, and High-High Status t Prelim. Q Final QX Void Q 8.0 ~Pa~~
- 8. 1 Loop L-484, SG Narrow Range Level Steam Generator Differential Pressure Transmitter LT-0484 4-20 ma Channel Test Card LS/484 Loop Power Supply (Isolated)
LQY-484 0-10 vdc Lead-Lag Circuit LY-484A 0-10 vdc (Channels 474, 484, 494 only)
Signal Comparator LS-484A Set at 38.5% level Channel Test Card LS/484 SSPS Input Bay
e s A
~4s7= /ofS gev 8
/~et ~~~+ +
//
DISCIPLINE DESICR VIQtZPZChTZOH RECORD Instructions to Vertffcatfon Perseuwl
! ant ~ Q (Class Al
-~ ~hl7 57 opec C.tJL, OPJ5 Q ( ) Seismsc IClass Sl F:."e nc. 0 Level I ) FP Q iClass Dl
=ac~ant No.g Rev i l Other Design ver]I:catton snould be cone tn accorcance rich ANSI N45.2.11. Sect)on 6. as amended by Regulatory e .>>se>> nev pec:d. nstruc 'ons:
Discsptine Pro)ect Sngtneer ver1f fcatioa pocumatatkon
~conan:ca. Cs vt I St ruct ura l
'VA sessmsc Equip. Qual ~
Electr:cal Civil Stress
- CC Fire Protect lon Environmental Qual iiicat ]on Human Faccors Natertals >> 5 ner
!er:.':cat>on Nethodh Used'p(
Design Rev:er J Alternate Calculat lans Quaiiftcatson Test tng as 1gn Ver' er Date Actnorsecgement" ot Verification:
c ~4 ItI. Resolution ot Cemeatas
.=ments Reso l At hedl:
Ac 'cn taken aea c nts Acceptaole:
=estgn Vert :er Date P C '04 / Rev. 9
~ g ~
OXSCZPLXÃS OSSZCW VERXPXCLTXOS %@CORD CDNNENT SHEET
?lant
?ro7ect
?ile Ho. us7= oft
////P W/Z-AINT-/4 )CAN It d.t
.His sneer is cniy required wnen comments are being made.
Comment Resolved No. mment Resolution :nit ial/Date gL /I lc. iia4.l~l <
ot o&
Ul cl W at'l+
oY sk >id ~ s~ //, Q ws
~~0 ftl~ ~ ////
Proc 309 / Rev. 0
1 g h
+Nf+jz<'57 -4 &'s, ge v, 8
~CLuuc w.+ k DESIGN RKVIZN CHECK SHEET
~lant nJI Document Type 0 LCC)4+7 Jd N Pro j ectg ULA7TdAJ 5 Document No. -K M+57 Jd
.""ile Nophll 2 ~- GI~S qevision
==
Description:==
Mark each item yes, nc, or not applicable and initial each item checked by you.
- 1. Were the inputs correctly selected and incorporated into design? ~s88-2- Are assumptions used in the design adequately described and reasonable?
NOTE: Review snail 'nclude but 's not limited to applicable
'nputs specified in NED procedure 302, paragraph 302.4.
Are the appropr'ate quality and qualit" assurance requirements specified?
4 ~ Are applicable codes, standards. and regulatory requirements including issue and addendum properly dent fied, and are their reauirements for design met?
Has appl'cable construction and operat'ng experience been considered?
> ~ Have des 1gn -'" er face equirements been sat isf ied?
?. 'alas an appropr'ate design method used?
- 8. Is the output reasonable compared to inputs?
Are the specified parts, equipment, and processes suitable for the application?
- 10. Are the specified materials compatible with each other and the design environmental conditions to which the materials will be exposed?
- 11. Have adequate maintenance features and requirements been specified? A>A W
- 12. Are accessibility and other provisions adequate for performance of maintenance, repair, and any expected in-service inspections?
Has the design properly considered radiation exposure to the public and to plant personnel (ALAN&)? gems 14 'as the design properly documented changes in radiation affecting post-accident plant access and/or affecting EQ? + ~A
- 15. Has the new design properly considered all system modes of operation-Proc 309 i Rev. 0
( > J ws7. r~fS, p v. 4
~p A'/
Document Type LK ~
Document No. -X Are acceptance criteria in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished? 5
- 17. Have adequate preoperational periodic test requirements been specified?
and dk
'S. ate adequate stoning. handling, cleaning, shipping, and identification requirements specified? N g
'9. Are reouirements for record preparation, review, approval, retention, etc .. adequately speci f ied2 "0. Have all problems with this desian known from prior application been considered and resolved2 45
.=or each question on the check list not answered yes, explain below. Ef "Not Applicable" aive reason.
Signature Date (Design Verifier)
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proc 309 / Rev 0
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