ML052000137
| ML052000137 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 06/30/2005 |
| From: | Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY-05-068 VYC-462A | |
| Download: ML052000137 (361) | |
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ATTACHMENT 4 TO BVY 05-068 CALCULATION NUMBER VYC-462A REVISION 0, MAIN STEAM LINE AREAS HIGH TEMPERATURE SETPOINT, WITH CALCULATION CHANGE NOTICE CCN-01 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
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To Pungesi J YANKEE NUCLEAR SERVICES DIVISION CALCULATION/ANALYSIS FOR TulE MAN STIAM lTNE ARPEAS I-UGH TEMPERATURE SETPOINT PLANT VPMONTCYCLE 20 CALCULATION NUMBER VYC462A THIS CALCULATION IS A MAJOR REWRITE PREPARED BY REVIEWED BY APPROVED BY SUPERSEDES ORIGINA L /DATE /DATE CALCJREV. NO. ORIGINAL W
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,D Willis CPsc 3S 9 YYC KEYWORDS MiinStenn PCISetpoint.UncerAinty-SteamTunnel.EfWHeaterlav lFER COMPUTER CODES: None EQUIPtMAG Nos.: TS-2-121AR C D TS-2-122A B- C e:TS-2-12.3 RC Do T.S-2-124A: B. C. D SYSTEMS: Nuclear Roiler (NMI System 2
REFERENCES:
QP 4322: Techncal Specficat ion Section 3214 2B Tables 3.2.2 & 4.2.2 FORM WE-103-1 Revision 4 WA S0W26.TGS
I Main Steam Line Areas Hipkh Tempnerature Settoint VYC-462A. Rev. 0 Table of Contents ! page LIST OF TABLES ................................................. ............................................................. 3 LIST OF FIGURES ............................................ 3 HISTORY OF REVISION ................ A 1.0 PURPOSE ....................... ......... 5 1.1 Calulation Objectives ................................ .. 5 1.2 System.Components . 13 Instrument Loop Function .6 2.0 MEMHODS AND ASSUMPTIONS .7 2.1 Creria .8 2.2 Assimptions .10 3.0 INPUT DATA ...................... ; 12 3.1 Proces and Loop Data. .12 3.2 Environmental Conditions .12 3.3 Switch Data .13 4.0 CALCULATION DETAILS.13 4.0 C CU nO DEAL ................................................................................. 13 4.1 Normal Condition Uncertainties ,. ...... 13 4.2 Test Uncertinty (ej. : 17 43 Normal Module Uncertainty (e.) .17 4A Accident Condition Uncertainties ..................... 17 4.5 Sepoint Evaluations ............................................................................................... 19 4.6 Margin Evaluation ............................................................................................. 21 4.7 Allowable Value (ITS) ............................................................................................. 24 4.8 Calibration Tolerances ............................................................................................. 24 5.0 RESULTSICONCLUSIONS .............................................................................................. 25 5.1 Total Loop Uncertainty .................................... 25 25.................... 5S Sctpoint Evaluation .............................................................................................. 25 53 Graphic Representation of Sctpoint Data ............................. 26 5.4 Calibration Criteria ............................ . 27 5.5 Measuring & Test Equipnent Requirements ............................ 27 5.6 Recommendations ............................ 28 5.7 VYDEP-15 Criteria ............................. 29
- 5. Evaluation of Existing Setpoint ............................. 29
6.0 REFERENCES
............ 29 7.0 AlTACHMENTS .......... 31 Page 2 of 31
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Temnrstumbrg 4Zetrvojnt v s , VV('.Ao V_ *V. v C_ A ID- A VJ LISTOFTABLES TABLE I Component Identification ................. 5 TABLE 2 EQ Matrix Data .7 TABLE 3 Process/Loop Inputs 12
-TABLE 4 Environmental Input Data ................... 12 TABLES Temperature Switch Input Data .13 TABLE 6 Total Loop Uncertainty Results .. 25 TABLE 7 Sc'oint Results ;................ ; . . . 25 TABLE 8 Cajibration Attributes .27 - TABLE 9 Recommended MATE ............. ; 28 .. . ptm LIST OF FIGURES rzuuznz I Graphic Representation of Setpoint (CTS) .26 FIGURE2 Graphic Representation of Sdtpoint (ITS) ........................................................................ 27 7
Page 3 of 31
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*: : O- Initial
.. Issue; incorporte plant-specific analyzed drift data and 7
new setpoufl methodology, support Improved Technical Specification submittal; VYC-462D Revision 0, supersedes VYC-462, Revision 2, (Calculation subset "D1 addresses the loop function of High Pressure Coolant Injection Line HELB
- . detection).
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Page 4 of 31
Main .tp*m T inp Areas Tlioh Temnerat-rie ePtnnint UVPYA.') 1D-. . nW 1.0 PURPOSE 1.1 Calculahion Obiectives This calculation is performed in support of the Vermont Yankee Setpoint Program and has the following major objectives: I. Document the loop function and the basis for the setpoint and operator decision points associated with that function.
- 2. Determine the normal and total loop uncertainty and verify consistency with the design basis.
- 3. Calculate the limiting setpoint and operator decision points.
- 4. Evaluate the adequacy of the existing setpoint, calibration limits and procedural decision points.
5 Provide as-left and as-found tolerances for use in calibration procedures; determine Measuring and Test Equipment selection and accuracy criteria; document prvoce:s corrections, instrument scaling, calibration methods.
- 6. VYDEP-1S requires that applicable operating procedure alarm responses, standard, off-normal and emergency operating procedures be included in the evaluadiL Ibis requirement is accomplished by the inter-disciplinary review that supp!ements the WE-103 review process and is documented in Attachment 0.
12 SVstemIComponents This calculation applies to the Main Steam Line Area's High Energy Line Break (HELB) detection switches in the Nuclear Boiler (NB) System. The specific components to be addressed are: TABLE I Component Identilkatlon ReE TAG Number Location Description MFG Model CWD 6.14 TS-2-121A Steam Tunnel Temperature Fenwal 01-1700204090 1100,1101, TS-2-122A El. 252' 6 Switch 1102,1103 TS-2-123A TS-2-124A 6.14 TS-2-121B TB 265'NE Temperature Fenwal 01-170020-090 1100, 1101, TS-2-122B Switch 1102,1103 TS-2-123B TS-2-124B 6.14 TS-2-121C TB 265'NE Temperature Fenwal 01-170020-090 1100, 1101, TS-2-122C Switch 1102,1103 TS-2-123C TS-2-124C . 6.14 TS-2-121D TB 265'NE Temperature Fenwal 01-170020-090 1100, 1101, TS-2-122D Switch 1102,1103 TS-2-123D TS-2-124D Page5 of3l1
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D_. ICV. U i 1.3 instnunent LOo Function 13.1 Normal Omerations There are no indicators or anticipatory alarms associated with these channels. Instrument output is a contact change-of-state at the setpoint; therefore, these channelslhave no normal operational function. 13.2 Off-Nonnal/Accident Operations High temperature in the space in which the main steam lines are located outside of primary containment could indicate Pbreach of a main steam line. Isolation Signal D (steam line high space tempeaturc OR high steam flow) results in immediate automatic closure of the Class A valves which isolate the following lines:
- All four main steam lines
- Main steain line drain
- Reactor recirculation water sample line High temperature in the vicinity of the main steam lines is detected by four sets (of four) of bimettalic tenperature switches located along steam lines and between the drywell wall and the turbine. The detectors are located or shielded such that they amc sensitive to the air temperature but not the radiated heat from hot equipment The main steam line space high temperature detection system is designed to detect leaks of from 1%to 10Y% of rated steam flow. The trip setpoint is set far enough above the temperature expected during operations at rated power to avoid spurious PC1S isolation yet low enough to provide early indication of a steam line break.
Associated with each set of detectors is an additional temperature loop (TE IOSA to D) monitoring the same space (Reference 6.19.6) and which provides:
- Remote temperature indication
- Alarm on HIGH temperature
- Alum on loss of power (Reference FSAR Sections 73.4.73, 73.4.83 and FSAR Figure 73-6.)
133 Accident Mitiaation (Harsh Environment) From Reference 6.7 and Table 2:
- Components will experience a Loss-of-Coolant Accident (LOCA) harsh environment but are not required to function, nor be LOCA qualified.
- For Main Steam HELB, components are required to function and are EQ qualified, with an operability duration of one hour for auto PCIS actuation. While a Small Break LOCA (SBLOCA) may exceed the one-hour qualified duration, operator action is credited for SBLOCA detection and manual isolation.
- For other HELBs outside the Main Steam Line Areas, the components will either not experience a harsh environment or, if in a harsh environment, are not required to function for that scenario.
Page6 of 31.
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__:__ - TABLE 2 EQ Matrix Data Loop Location Accident CA, TBNI, F1,3 Dumaton TS-2-121A,122A, Vol.41 LOCA C 36 00 N/A 123A, 124A MS.HELB A 4 1 I hr. HPCI-HELB C 36 0 N/A RCIC-HELB C 36 0 N/A RWCU-HELB A 36,87 1 1 hr. HHS-HELB C 36 0 N/A TS-2-121B, 122B, IM LOCA C 36 0 N/A 123B,124B MS-HIL A. 4 1 1 hr. TS-2-121C, 122C, HPCI-HELB E N/A 0 NIA 123C,124C RCIC-HELB E N/A 0 N/A TS-2-121D, 122D, RWCU-HELB C 36 0 N/A 123D, 124D _ _ HSHEL C .36 0 . N/A 13A Post-Accident or EOP Functions These channels do not provide any indication or any further function once PCIS isolation actuates when the protected areas reach the trip setoint. These channels are not identified as post-accident instrumentation in Technical Specification Table 32.6. 2.0 MFIHODS AND ASSUMPTIONS This calculation has been prepared in accordance with the ",Vermont Yankee Instrument Uncertainty and Setpoint Design Guide" (Reference 6.1), and WE-103, "Engineering Calculations and Analysis" (Reference 62). Standard methods employed in this calculation are explained in the Design Guide; special teclniques and criteria are explained below. The requirements of VYDEP-1S (Reference 6.5) are accomplished through the lnterdisciplinary Review process. 2.1 Criteria 2.1.1 Setpoint Class As shown in Table 2, these components are associated with Safety Function 1,"HELB Detection and Isolation." Consequently, per the Design Guide, these components' tin setpoints are Class 1, Nuclear Safety-Related. 2.1.2 Scaling Considerations Per VYC-462, Revision 2, and VYC-l 599 (Reference 6.15 and 6.10, respectively), the range of these switches is (.)100°F to (+)600°F. Therefore, Calibrated Span (CS) is: CS =600-(.)l00 0
-700 F Page 7 of 31
Main Steam Line Areas High Temperature Set0oint VYC-462A. Rev. 0 Individual error determinants will be calculated to two (2) decimal points, the degree of resolution used for Analyzed Drift (DA) output in VYC-1599. Output values (calibration tolerances, Allowable Value, calculated sctpoint) will be resolved to the most conservative whole degree F. Note: The range discussed above is dissimilar to that given in MPAC (Page 6, Screen 1). See Assumption 2.2.5. 2.13 Sinele Side of Interest In order to avoid impacting both the analysis value (module uncertainty e+) and plant operating margin (c), and since the Ibop approaches setpoint only in one direction (i.e., there is no low
-temperature setpoint), a single side of interest factor will be utilized as per Reference 6.1, Appendix F. For a 95% proportion the following "JI/W factor (J)will be used:
- K.;
J
=1.6511.96.
0.85 (Rounded Value) Note that (fiis applicable only to random terms. 2.1.4 Calibration Effect Considerations Per the Design Guide, CE is typically taken as the sum of the vendor's Rated Accuracy (RA) and the As-Left Calibration Tolerance (Cl). Based on the number of samples used to determine DA (count - 199 as per VYC-1599, Table 4), a test will be applied to determine if credit can be taken for RA being encompassed by DA. Test methodology is described in detail in Reference 6.13. In essence:
- If DA < [RA2 + C 2
+ vendor's rated drift 2 + MTE'J"',
then CE CT 2
- If DA 2 [RAI + CT' + vendor's rated drift + M1EIiI, then CE =CT + A where:
CT Present Calibration Tolerance DA = Analyzed Drift from VYC-1599 RA = Vendor's Rated Accuracy MTE - the Measuring & Test Equipment used in calibration and where the vendor's rated drift is valued at 0 because the vendor has no published drift specifications. . Page8of3l.,
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).An t- T ,u .Ar- 14v Tpn-jVV'. nhy=-pr AD... AU 2.1.5 Sien Convention The sign convention used in the Design Guide is based on the effect of uncertainties on an instrument (or loop's) output signal. Foi this tpe of device, where there is no analog process input/signal output relationship the effect of uncertainties are manifested as a shift in the setpoint away from the Ideal value. This results in a sign convention which is the reverse of that which is generically defined in the Design Guide.
2.2 Assumptions 22.1 The aror term "Temperature Effect" (TE) is not applicable because temperature is the measured parameter ofthe device. 2.2.2 The effect on setpoint of harsh environmental conditions caused by LOCA/HELB are negligible (Attachment G&P). These include: 1
- Setpoint Shift
- Radiation Effect (RE)
- Contact Resistance
- Insulation Resistance (IRE)
- Humidity Effect (HE)
(Reference 6.7.1, Section X-2.3) 2.23 For Custom Technical Specification (CTS) applications, the CTS value is typically assumed based on normal operating conditions. However, in this case during the event for which these switches are credited (HELB) a pressurization may occur (see Section 22.6). Consequently, for CTS as well as ITS, this pressurization effect will be accounted for. 22.4 Per Reference 6.1 for Improved Technical Specification (ITS) applications, the 1S value is assumed based on the most limiting of HELB with TE and HE or Seismic Effect (SE). 225 Per the original plant design instrument data sheets (Drawing 225A5600, Sheets 94 and 95, these switches were Fenwal 1700240 (-)100°F to (+)600'F. Per the EQ program, these switches are Patel-Fenwal 01-170020-090, range not specified (QDR 9A, Appendix 11, vorksheet). Per the vendor manual (VYEM0029), these switches are EGS (Product Line Sold) 01-170020-090, no range specified. Per VYC-1599, Table 1, these switches are Fenwal 01-170020-090 (-)100 to (+)600 0F. PerMPAC(page 1 andpage6,scren 1)theseswitchesareFenwalOI-170020-090(-)40°Fto (+)200 0F. For the purpose of this calculation, the following is used as input based on approved engineering sources: MFG - Fcnwal (QDR 9A) Model 170020-090 (QDR 9.4) Range - (-)100 to (+)600F (VYC-1599) Page 9 of 31
Main Steam Line Areas High Tenmerature Set=oint VYC-462A. Rev. 0 2.2.6 Per Reference 6.7.1, there is a pressure effect of+31F per 100 psi. Per Rcference 6.72, the maximum protected area pressure rise is +5.1 psi. Where HELB pressure effect (OP,¢ ) is: N" - (3eF/ 00 psi) x 5.1 psi
= +020PF (Conservatively Rounded) and is manifested as a (+) bias in the nonconservative (relative to safety function) direction.
2.2.7 Per Reference 6.1, the following normal condition uncertainty terms are encompassed in the DA value:
- Measning & Test Equipment Accuracy (MTE)
- Drift (as a function of Jime) (DR)
- Temperature Effect(AT200 F) (TE)
- Pressure Effect (PB)
- Humidity Effect (HE)
- Radiation Effect(RE) ;
- Vibration Effect (non-seismic)
Based on recalibration, the above terms are taken as noncumulative. 22.8 For this type ofdevice, the following normal condition uncertainty terms are not applicable:
- Static pressure effects on span and zero
- Power supply effect 2.2.9 Per Reference 6.1, no uncertainty is credited against the relays controlled by these devices.
2.2.10 Based on the design location of these devices (see PSAR Sections 7.3A.8.3 and 73.5) the nonconservative affects of Process Measurement (PM) are negligible. 2.2.11 Per CTS, the specified calibration interval is "each refueling outage." Per Reference 6.9, this interval is typically bounded by 18 months and is taken as limiting (by the refueling event, not calendar days). To allow for a refueling cycle extended to beyond a nominal 18 months, this calculation will base extrapolated DA on a maximumn interval of 684 days (using the criteria of once per operating cycle +25% as a convenience). If the calibration interval extends, for whatever reason, beyond 684 calender days, an evaluation to determine the interval increase effect on setpoint is REQUIRED. 2.2.12 Per VCY-1 599, Section 5.4, the analyzed drift data for these devices (pooled Procedures OP 4322 and OP 4366) indicated little time dependency. Consequently, it is assumed that RSS extrapolation of calibration interval is appropriate. Page 10of31
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*3.0 INPUT DATA1 Data used to calculate loop uncertainties, setpoiyw and decision points are tabulated below wth the applicable refeen:ce or basis.
3.1 Procss and LoopData i:T. ABLE 3 Process/Loop Inputs Reference - Description Data (IF) 6.18. - - Analytical Limit I96 (outside steam tunnel) 6.22 . - : . ;: - - .' . . 200 (inside steam tunnel) 6A., Table 32.2 ; Custom Technical Specification Limit 5212 6.6 Existing Calibration Procedure Setpoint 18S *5 6A, Table 4.2.2 Calibration Interval f. Once/Refueling Cycle 6.4, Table 4.2.2 Functional Test Interval Once/Month 3.2 Enviwonmental CoWiditions TABLE 4 Environmental Input Data Reference Description Data (IF) 6.7.1 6.7.2 Normal Temperature 140 (MAX) (Steam Tunnel is Limiting) TS-2-121A to 104A - Steam Tunnel TS-2-121B to 104B - TB 265' TS-2-121C to 104C - TB 265' TS-2-12ID to 104D -TB 265' __ __ _- 6.7.1,6.72 HELB Temperature 300 (Steam Tunnel is Limiting) TS-2-121A to 104A - Steam Tunnel TS-2-121B to 104D - TB 265' TS-2-12ICto 104C- TB 265' TS-2-121Dto 104D-1B 265' . 6.7.1 Radiation Exposure 40 year normal exposure 3.5 x 10'R (steam tunnel is limiting) 2yearnormal exposure 1.75x 10WR Page II of 31
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K. V. A V 3.3 Switch Data TABLE S Temperature Switch Input Data Reference DescriptWn Data Section 2.2.5 Range -100F to +6W00F Section 2.1.2 Calibration Span 700"F 6.8 Output Signal - Contacts open on temperature rise 6.8, Section 4.13.1 Accuracy +5F 6.7.1 Pressure Eftect +3*F/100 PSI 6.10 Analvzed Drift 7.54-FIS44 days 4.0 CALCU'AXTION DETAILS 4.1 Normal Condition Uncertainties 4.1.1 Process Measurement Effects (PM) From Assumption 2.2.10, PM (thermal stratification) is taken as negligible. PM-0 4.1.2 Primarv ElenentAccuracv(PEA) There is no prinma element associated with these channels. PEA= N/A 4.13 Calibration Effect (CE) Per Reference 6.1, CE typically takes the form: CE-A+C r where: CE Net calibration effect A = Device rated accuracy CT - Calibration proceduretolerance Page 12of31
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From Reference 6.7.1 (Attachment P) the factory temperature setting tolerance for units that cose on temperLare rise is the greater of *3°F or *2% of setpoint (t4*Ffor a postulated maximum setpoint of 200F.) However, the calibration technique described in Reference 6.8 (Attachment D) infers an average repeat accuracy of +*5F. For the purpose of this calculation: A = *5.0°OF 4.1.3.2 Calibration Tolerance (CTM Per Reference 6.1, the basis for CT is the rated accuracy of the device, or *5°F. This is also the calibration tolerance presently in use in Reference 6.6 (Attachment E). CT.,c15.000 F 4.1.3.3 Expected Performance vs. Actual Perfonnance Ai discussed in Section 2.1.A and where there is no vendor-rated drift:
- If DA< 4IA:+CT2 +MTEVI" (Eq.I) then CE - CT If DA 2 [A2 + CT 2 + MTE2J" 2 (Eq. 2) then CE.-=CT+A Initially:
A t5.000 F (Section 4.1.3.1) CT - *50 F MTE = MTEAcTuAL (Section 4.1 A2)
=*4.12 0 F DA - *7.54'F (Section 4.1.5)
Thus: . . 2 d4A + CT2 + MTE 2 _ 415.0O2 + 52 + 4.12 2]n °F
=A.8.18F /
Equation I is satisfied, consequently credit is taken for A being encompassed by DA. Page 13 of 31
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4.1.3.4 CE used in Uncertainty Determnination Based on the results of Section 4.1.3.3: CE - CT
- *5.00°F 4.1.4 Measuring& Test EquiPmcnt Accuracv (MTE)
From Reference 6.6 (Attachment E), calibration is accomplished with an Omega Digital Thermometer (or equivalent), a Type K Thermocouple and a test beater. A review of previous calibrations indicates the typical use of an Omnical SA digital thermometer (MlE,). From Reference 6.11 (Attachment F), total error for the Omnical 8A is expected to be: MTE, -:L.OOS°F From Reference 6.17 (Attachment N), standard limits of error for a Type K T/C (nonspecial) in the application rangc of 0°F to (+)530°F is: MTE2 ' IF 4.1.4.1 MTE Rtguirements Per Reference 6.1:
- M TE uncertainty is encompassed by DA
- Total MTE uncertainty shall be S tated accuracy pf the device under tesL Given the relationship:
2 MTE e :k[MTE, + M+EN where: MTE - A (Limiting)
- 5°F MTE, *4o4F (Type K TIC, Limiting) then it can be seen by inspection that any MTE, with a total accuracy up to and including 43°F satisfies the 1:1 total MTE accuracy criteria.
Page 14of31
Main Steam Line Areas Hid-Temoerature Setgoint VYC-462A. Rev. 0
.4.1.2 ImDlenented MTE In support of Section 4.13.2 and from Section 4.1.A.1, the following is assumed to be representative of MTE used for calibration:
MTE, =-*1.00SF MTE2 - *4.00DF Consequently, 2 MTE,, Lo L.0051 + 4.00I 1F
=*4.13F, 4 15 AnalvzedDrift(DM.
From VYC-1599 (Attachment H), switches calibrated per OP 4322 (the scope of this calculation) and OP 4366 (RCIC HELB Detection) met the criteria for pooled data The output of VYC-1599
- (per Section 4.2) is a 95% probability/95% confidence level value, which meets the criteria of a Class I setpoint as per Reference 6.1. The following data applies to DA:
- Average time interval is 544 days
- DA isi 7.549F
- Data is evenly distributed about zero with a slope on the time dependency line equivalent to
<0. % per approximately 550 days showing, consequently, little time dependency.
- The data is normally distributed with a highly peaked narrow distribution.
- The average drift value for this group is 0.008% CS; since this value is less than 0.1 % CS, bias effects are considered negligible.
Per Assumption 2.2.11 extrapolation of DA from a baseline of 550 days to a maximum of 684 days take the form: DA,,, DAs, [694/S44]'2 DA4 w *7.54°.F[6841544]w
-DAm - 48.54 F Page 15 of 31
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Ty pically, DA accounts for a 20F AT E: during calibration conditions. In this case, TE has the following considerations:
.Themeasured process parameter is temperature, for which the device is designed.
d v Calibration technique is to preheat the switch (and associated calibration T/C) and use a prefabricated test heater assembly to minimize any extenal influences and approximate ) normal operating conditions prior to temperature ramp-up to semoint Consequently, normal I TE as an error determinant is considered to be negligible. STENO 4.1.7 Radiation Effect (RE) Per Reference 6.1, normal radiation effect is encompassed by DA RE'0 4.1.8 Humidity Effect (HE) No humidity effect is specified by the vendor. In addition, per Reference 6.1, normal humidity effect is encompassed by DA. HE-0 4.2 Test Uncertainty (e From Reference 6.1 for this type of device, and where there are no significant testing condition biases: Initialty, et - & CE2 + DA2]"2 Substituting: e, 4-[5.OO°F 2 + 2 3.54OF ]l)
+ k9.S2F .
Accounting for a single side of interest approach as per Section 2.1.3: c, = +[9.82F x 0.85]
- 08347 0F Z To facilitate the calibration process, e, is conservatively rounded (with regard to setpoint development) to:
+/-8.00°F Page 16of31
M Main Steam Line Armas High Temp-erature Setpoint VYC-462A. Rev. 0 43 Normal Module Uncertainty (e in this cas, there are no additional terms to thosc accounted for in the unrounded eL e,, = el
- *8347F, conservatively rounded to:
I; 4A Accident Condition Uncertainties 4.4.1 LOCA Uncertainties (e,IA' Per Reference 6.7.1, these switches do not mitigate a LOCA and, while they may experience a harsh environment, need not function during a LOCA. A LOCA coincident with a HELB is not considerd to be ctedible i scenario. Consequiently: ew- N/A 4A42 HELB Uncertainties Per Reference 6.7.1 Section X-23 (Attachment P) following both the LOCAIHELB simulation and Humidity/Cycling Test, the specimens (Test Item Nos. 2 and 5) remained within the test acceptance criteria of *6°F. Indeed, the post-accident shifts were of minimrnu magnitude (+2.2?F and -02°F,respectively). For conservatism, this calculation postulates that the pressure effect, discussed in Assumption 22.6. is only manifested during the accident condition and would have been unmeasurable during post-accident testing. 4A.2.1 HELB Tannerature Effect (TEU) Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the tetst acceptance criteria after LOCAI1ELB simulation. In addition, temperature itself is the measured process parameter for switch actuation. Consequently, for the purpose of trip setpoint uncertainties: TEH"=NIA. 4.4.22 -iELB Humiditv Effect (HE, Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCAIHELB simulation and humidity/cycling. Consequently: HEage ° 1f Page 17of 31.
-Rm -- - R Main Steam Line Areas High Tenpmerature Setpoint VYC-462A. Rev. 0 4.4.2.3 Overvressure Effect (OR" ,,)
Per Reference 6.7.1 (Att? ^hmcnt G), a HELB can result in an area pressure risc. The worst-case pressure increase is (+)5.l psi, and results in a (+) bias shift in the setpoint, proportional to the extent of pressurization. From Assunption 22.6: OPwL9 - +0°20F 4.4.2A HELB Module Uncertainties (e.w.) Accounting Cor uncertainties which are negligible or not applicable: 2 eEU (CE + DAJ + OP l Substituting: [5.00F 2 + SA45oF 2 1j (0.85) + O0r0F 1
- + 8.SS3F1-S.35F f-4.4.3 Seismic Module Unceraintv (eas)
For HELB mitigation channels, em is determined by HELB conditions of over-pressure coincident with, or subsequent to seismic effect From Reference 6.7.1 (Attachment P)I post-seismic effect ranged fiam -3.1F to +42°F. For conservatism, the post-seismic simulation functional acceptance criteria of*51F is taken as limiting. Initially: SE - +5.00°F Accounting for uncertainties introduced by a seismic event followed by switch actuation caused by a main steam line HELB: e [tCE 2 + DA2+ SE1 2 + OP Substituting: em [5.0F2 + 8.45'F 2 + 5.00FP]2 1 (0.85) + 0.20F
+ 9.5PVF/-937°F 4.5 Setoint Evluations 4.5.1 Custom Tchlnical Specification (CTS)
LSP-TS-ITLUI However, because AL < TS, the AL becomes the more limiting condition. Therefore: Page 18 of 31
It-;- IVIACUI C#-.- I ;n-UOMcIS ],IAM, A U;io rC aLIa4'.3 54U54 Ta - nv%^titrm Qafr%^int vJ-'laz. IIIT V vvr4 A#: A D, -n U LJ1. F.VY. 4.5.1.1 TS-23-101.102.103.104 (B.C.D) LSP,,, =AL -ITLUI Where: LSPgm- The Limiting Setpoint TS - CTS Table 32.2 Trip Setting S 212°F (Not Used) AL= 196IF (labIl 3) TLU Total Loop Uncertainty which, in this cases reduces to:
- emm (+e, is the worst case vector)
Substituting: LSP 1o = 196°F-8.55F 187ASIF, conservatively rounded to: LSPBm - 187°F - 4.5.1.2 TS-23-101.102,103.104 (A) LSPIA = AL - I TLUl Where: LSPIA - The Limiting Setpoint TS - CTS Tale 3.2 Trip Setting S 212°F (Not Used) AL = 200IF (Table 3) TLU - Total Loop Uncertainty which, in this cases reduces to:
- em (+emx is the worst case vector)
Substituting: LSPIA =2000 - 85S°F 191.450 P, conservatively rounded to: LSPIA- 191°F Page 19 of 31
Main Stear Line Arecas High Tle-nerature Settoint VYC-462A. Rev. 0 4.5.2 Improved Technical Specifiation (ITS) LSP2 - AL -I TU I 4.52.1 TS-23-101.102.103.104 (B.C,D), Where: LSP2 "'The Limuting Setpoint AL The Analytical Limit TLU = Total Loop Uncertainty which, in this case reduces to: ed (+cm is the worst-case vector) Substituting: LSP2BCD 196°F-9.57°F 186A3°F, conservatively rounded to: LSP= 186°F a 4.5.22 TS-23-101.102,103.104 (A) Where: LSP2A The Limiting Setpoint AL The Analytical Limit TLU Total Loop Uncertainty which, in this case reduces to: em (+em is the worst-case vector) Substituting: . LSPA - 200°F - 9.57°F 190.A3F, conservatively rounded to: LSP2A - 190°F Page 20 of 31
- - 4 r. " ; *wI zs/: .. '
Mno;n Qtj2nm
-Vfll.t
;ne-SA. roen TUJ*5S wa Uioh
*WS*
Tf-mvwnerat e.Qtrnnnt VWPAA' I V a 'Tf A ID ^ flXV. n V 4.6 Ma-in Evaluation 4.6.1 Custom Technical Soecification 4.6.1.1 Nominal Margin (M,) to Existing Calibration Setpoint (SP) M, =LSP-SP TS-23-101.102.103.104 (B.C.D) r Substituting: MI 8TrF - 185F
+20F TS-23-lO1.102.103.104 (A)
Substituting: MjA -'l9l'F-185°F
= +6'F -
4.6.1.2 HELB Safety Mariin M, to Existing Aniiviical Limit (AL) Per Reference 6.18 (Attachment B), the existing AL inside the steam tunnel CA" switches) is 200°F and outside ("B, C & D" switches) is 196°F and includes a 6°F allowance for instrment enor. The existing setpoint from Reference 6.6 is 185F. The "nonmal condition" uncertainty applicable to CTS Ml to existing AL still must consider the HELB OP effect, therefore es (positive, vector) is used. Thus: M2 -AL-[SP i+ ] TS-23-101.102.103.104 (B.C.Di Substituting: M2SD = 196-F - [1 85°F +8.55F]
- +2.45F -
TS-23-101.102103.104 (A) Substituting: M1A = 2000F - [I 85°F +8.55F]
= +6A5.F -
Page 21 of 31
Main Steam Line Areas Hieh Tcmperaturc Set oint VYC-462A. Rev. 0 4.6.13 HELBMSeismic Safety Martin (M,') to Existing AL From Section 4.43 em (positive vector) is 9.57°F. TS-23-101.102.103.104 (B.C.D) Consequentdr M3jD ' 1961F -185F+ 9.571F]
,^. . .- +I13°F .-
TS-23-101.102.103.104 (A) . .Consequently: Mm 200-F - 1185F + 9.57VF]
-+5A3°F .
4.62 Improved Technical Seccifications (llS) From References 6.18 (Attachment B) and 622, the current AL is 196°F for o6tside the steam tuninel and 200°F inside the steam tunnel. For ITS: By inspection it can be seen that nominal margin from LSP2= (186° F) is +11 F and from LSP2A ( 190 F) is +5° F. Per Reference 6.16 (Attachment M), the original plant design was for an SP which was "95°F above bas tetmperature!" From a review of plant area temperat trends (Attachment G), maximum base temperature is assumed to be 140 0F. Since LSP2 accounts for the combined effects of HELB (as applicable) and seismic effect, no additional safety margin relative to ISP, is required. 4.62.1 Improved Technical Specification Opgrating Martin (Mi) For an e, of (-)8A°F (non-worst case vector), and a maximum base temperature of 140°F (TC.rm,operating margin is expected to be: TS-23-10l.102.103.104 (B.C.)) Substituting: M ,[= 1186-F - S.4F - 140°F
- +37.60°F
- Page 22 of 31
Main Steam Line Ares High Temrahr Setnoint VYC-462A. Rev. 0 TS-23-l0l.102.103.104 (A) Substituting: M,, - [I9OF- l -8.4Fl]-140°F
+41.60F _
4.7 Allowable Value (ITS) 4.7.1 LOOD Acceshnce Value (ACV) For a single component loop, the determination of ACV (the algebraic sum of each component's as-found tolerances) is not applicable. 4.7.2 Allowable Value (AV) From Reference 6.1: 4.7.2.1 TS-23-101.102.103.104 (B.C.D) AV LSP2KD+e, Substituting: AVBm = 186°F + 8.000 F
- 194°F 4.7.22. TS-23-101102.103.104 (A)
AV = LSP2A + et Substituting: AVA, 190F + 8.00TF
- . =198°F ..
4.8 Calibration Tolerances 4.8.1 As-Left Calibration Tolrance (Cfl As developed in Section 4.13.2: Cr-
- 5.000F Page 23 of 31
Main Steam Line Areas Hiah Temperature Setpoint VYC-462A. Rev. 0 4.82 As-Found Calibration Tolerance (AM From Reference 6.1: AFr - e, As developed in section 42:
, - 08.0OF Consequently.
AFTl-8.00F - Page 24 of 31
IS-' - I :--A .U;Ak ZYI4AJL.~I4lII AI ~ ~ LI5-. ).Z~U7
.~IL~JAI~
vvrW.. Af- A Dn
-u.gi
., n n V. U 5.0 RESULTSIMYOCLUSIONS r.
- 1 I C.m. .
5.1 Total LOOD Uncerints 11I 1 Total Loop Unccnainty (TLU) has been evaluated for the HPCI tubine steam line HELB I detection switches within the context of both Custom and Improved Technical Specifications and I, , dte results are presented below:
. ;- . TABLE 6 Total oop Uncertainty Results o
i.
.CcL hnteml . CI& EArS-HELBI=EISMIC Refceling Cycle +S.SSFI-835,F '9.57F/-937OF Iz.
5.2 Setpoint Evaluation For protected arcas inside and outside the steam tunnel, resuts ar presented below for the limiting setpoint (ISP), Alloivable Value (AY), relevant Margfim (s,) and baseline data. TABLE 7Setpoint Results Descrption Resots (0 F) Analytical Limit (ALJ) 200 200 Analytical Llmit (ALBD) 196 196 Allowable Value (AVA) NWA 198 Allowable Value (AV 3 a) NIA 194 Technical.Specifation Limit (TS) 212 198 (inside)
._ 1942 (outside)
Existing Setpoint' (SP) 185 . NtA Limiting Setpoint (LSPIA .I 191 190 Limiting Setpoint (LSPIWMMWD) 187 186 Recommended Setpoint (SPA) 185 . 185 Recommended Setpoint (SPwo) - 185 185 Margin LSP to SP (M,) . +6 , +5 MarginLSPto SP(M,9 - +2 +1 Safety Margin to Existing AL(MPAJ +6A5 N/A Safety Margin to Existng AL(Ms. +2A5 N/A HELBISEISMIC Safety Margin to Existing AL(M143 +SA3 NIA HELB/SEISMIC Safety Margin to Existing AL(M,s) 4 . . +1.43 . NA Margin AV to AL . N/A +2 ITS Operating Margin (M 0,)' N/A +41.60 ITS Operating Margin (MD)' *- - N/A : +37.60
- 1. Per OP 4322 Revision 12
- 2. For ITS the AV is the TS Limit ..
- 3. From (SP + ce.) to AL
- 4. From (SP + e 1 s^E~s to AL S. From (SP,)- cR) to mnaxinmum normal temperatur Page 25 of3l
Main Steam Line Areas High Temrerature Setioint VYC-462A. Rev. 0 5.2.1 TS 10.102.103.104 (B.C.D) - Outside Steam Tunnel From the above table it can be seen that, with calculated uncertainties, the existing setpoint would support (for b5I CTS and ITS) the present Custom Technical Specification Limit of<122F paradoxically lower Analytical Limit of 196" F resolution of which is outside the scope of this calculation. 5.2 TS-23-101.102.103,104 (A) - Switches Inside the Steam Tunnel The existing 185?F setpoint is acceptable for both the EQ 'rogram limit of 200°F and the Technical Specification limit of 212°F. 5.3 Graphic Reoresentation of Setoint Data FIGURE I
- Graphic Representation of Setpolnt (CTS)
Technical Specifi.ion 212°F Analytical Limit (ujside steam tunnel) 200°F Anabytical Limit (outside steam tunnel) 196°F LSPA 191F LSPIIScrD 18 0°F SP, SPA & SPew Normal (MAX) - steam tunnel 140"F
- 1. Calculated for nonnal conditions (to include OPmEu)
- 2. Existing sepoint per OP4322, Revision 12
- 3. Not to scale, provides relative position only Page 26 of 31
I Main Steam Line Areas Hieh Terrineritture Setnoint VWP-AK e 1 WS .vzrw. A ID-rvcv. A v Main tenm Line Areas HiRh Temnerature Setnoint W V('A) A D..., fl FIGURE 2 Graphic Representation of Setpoist (ITS Analytical Limit (inside stMam tunnel) 2000 F Analytical Limit (outside steam tunnel) -S6*F Alowable Value' (AVA) 198°F Allowable Valuel (AV>,o) 194°F LSPA 190°F SPO- 186°F SP.,SPA &LSPSCD .S°5F Normal (MA - steam tunnel 140°F
- 1. For ITS, the Allowable Value is the ITS value.
- 2. Ilhe exi SPper OP 4322.
- 3. Not to scame, provides relative position only.
- 5A Calibration Crileria In order to support and implement the results of this calculation, the temperature switches re to be calibrated according to the following table:
TADLE 8 Calibration Attributes Description ... -Value Units Setpont (CTS) Inside steam tunnel 185 OF Outside steam tunnel 185 . F Setpoint (ITS) Inside steam tunnel 185 OF Outside steam tunnel 18S _F As-Left Tolerance '5 OF As-Found Tolerance :*8 OF 5.5 Measurin, & Test Eouipment Requirements Testing is accormplished with the following equipment: Monitoring thermocouple (Type K) (Installed) TIC Reader (Digital Thermometer)
- Heat source (Fest Heater)
- Digital Multimeter
- Vanac For calculation purposes, only the T/C and Reader have relevant associated uncertainties, developed in detail InSection 4.1.A. Since the T/C Isan installed sensor calculation recommended MTE reduces to the TIC Reader.
Page 27 of 31
I - Man SteaMI-ine Areas HighTemperture Selpint VYC-462A. Rev 0 TABLE 9 Recommended M&TEj Ieci"nRequired Accray ~ Actual Accuracy ee OmcpaOmnical 4A & S 3A *1.005*F 6.11 Omnega CL-505A *30F *1l0050F 6.11 5.6 Recommendations 5.6.1 Subsequent to this calculation's approval, revise FSAR Table 7.3.2 as per Attachment K. 5.6.2 Revise 6P 4322 in accordance with Table 8 and Table 9. 5.6.3 Ensure that a calibration tracking system exists to evaluate consequences of a calibration interval greater thant 684 days.4Note: There are no planis to e'xtend the calibration interval beyond 684 days] 5.6A4 Add VYC-462A to the List of References in OP-43S8. 5.6.5 Evaluate the acceptability of an analysis limit that is less than the Technical MSpecification Limit for an increasing trip setpoint.
.6 Revise Section 7.5.3 of the EQ manual (various places) which use 2O00'F as the MSIV
*isolation trip setting. Thlisshould be the nominal sqvpint (existing and retained) of
.196F as implemented by the HELB analysis.The 200F applies to the steam tunnel only.
5.6.7 Review.and update MPAC pages for various errors and omissions. Tis includes erroneous setpointyolelce of 190 +IO'F. 5.7 VYDEP-I 5Criteria VYDEP-I. requires the impact to plant programs,4procedures and icning and design documents ame considered. TIls cakculation has been reviewed for impact considerations. To fully satisfy VYDEP-15 requirements, this calculation undergoes a review of all departments and programs that could be impacted by the results and conclusions. The following har been considered and Iseither addressed in this analysis or via the interdepartmental review process:
- FSARchanges
- Technical Specifications*(customn and improved Technical Specifications)
- Procedures
- Technical programs
* .rints
. Related Design Basis Calculations (input/output)
. Design Basis Do..ments .
Based on the aboveall impact considerations of VYDEP-I' are addressed. Page 28 of31 I .
Main Steam Line Areas High TeMperature Setpoint VYC-462A. Rev. 0
6.0 REFERENCES
6.1 'Instrument Uncertainty and Setpoin' Design Guide," Vermont Yankee, Revision 0. 62 WE-103, "Engineering Calculations and Analyses,. Revision 17 . 6.3 Vermont Yankee Final Safety Analysis Report. Section 73.4. 6A Vennont Yankee Technical Specifications, through Amendment I.S0. 6.5 Vermont Yankee Project Procedure VYDEP-15, "Calculations," Revision 2. 6.6 OP 4322, 'Main Steam Line Area High Temperature FunctionaLCalibration Test," Revision 12. 6.7 Vermont Yankee Environmental Qualification Progranm Manual, Revision 36. 6.7.1 QDR 9A, Revision 10. 6.7.2 EQDI 9S-55, "Draft EQ Manual Revision." 6.8 VYEM 0029, "Instructions for Patel Temperature Switches," Rcvision 0. 6.9 "Selected Definitions and Clarifications Associated with the Vermont Yankec Technical Specification." 6.10 VYC-1599, "Drift Calculation for Fenwal Temp SW Models 01-170020-090 and 01-170230-090," Revision 1. 6.11 VYC-1758, "Measuring and Test Equipment Uncertainties Calculation," Revision 0. 6.12 Memo, Hengerle to File, 'Improved Setpoint ProgramtCIS vs ITS Setpoint Evaluation," VYW 37/97, dated April 25, 1997. 6.13 Memo, Hengerle to Distribution, "Application of CT, CE and A for Single Point Devices," VYI 92/97, Revision 1, dated June 26, 1998. 6.14 MPAC. 6.15 VYC-462, -Fenwall (sic) Temperature. Switch Loop Acciuracy Review,! Re ision 2. 6.16 "Instrument Data Sheets," GE Drawing 225A5600, Sheets 94 & 95, Revision 1. 6.17 "Nuclear Power Reactor Instrumentation Systems Handbook," Volumc 1, Joseph Harrer and James Beckerly. 6.18 NED Analysis Matrix, dated January 21, 1998. 6.19 Plant Drawings: 6.19.1 Flow Diagram, Nuclear Boiler, G 191 167. Revision 56. Page 29 of 31
Mnitbn Qfwbm T ;ine Aia Uip;h Ti-mi-A-rtimre IQ-rehmint L~~ss-1ta b4: W
- ff~~~I UVO-Af'5
-Dfs
- t _J D-. n
,Jfa uyn. _u___
6.192 CWDl 100,'"PCIS Trip Logic, Channel Al", Revision 27. 6.193 CWD41 101, UPCIS Trip Logic, Channel A2", Revision 25. 6.19A CWD-1 102, "PCIS Trip Logic, Channel Bl", Revision 29. 6.19.5 CWD-1 103, PCIS Trip Logic, Channel B2", Revision 25. 6.19.6 CWD-748, "Steam Leak Detection System", Revision 4. 6.20 VYC-1347 Rcvision 0, "Main Sten Tunnel Heatup Calculafion" 6.21 Deleted 6.22 Memo VYE 9&214, GJ. Hengerle/E. Goodwin to RT. Vibert, "Assessment of VYC-462AC & D Tenperature Limits", October 5, 1998. Page 30 of 31
- U:nl Tm-1k ftn Ao~F A -1A n n a Main Steam line JA Areas ly 3IiJlIGLurx ,cIJuslq. _ V I
^l Xr.YV. U 7.0 ATTACHMENTS Attachment A, Loop Block Diagram Attachment B, NED Analysis Matrix Excerpt Attachment C, MPAC Data Excerpt Attachment D, Vendor Data, VYEM 0029 Excerpt Attachnent E. Calibration Data, OP 4322 Excerpt Attachment F, MTE Accuracies, WC-17S8 Excerpt Atachment G, EQ Manual and QDR Excerpt Attachment H, Analyzed Drift Data, WC4 599 Excerpt Attachment 1, CTS Data Attachment J, FSAR Data Attachment K, FSAR Table 7.32 Proposed Markup Attachment L, VY Project Memorandum VYW37/97 and WI 92197 Attachment M, GE Instrument Data Sheets Atichment N, Type K T/C Accuracies, Reference 7 Excerpt Atachment 0, WE-103 Review Sheets and Associated Interdisciplinary Reviews.
Attachment P, Additional QDR Data Attachment Q. Telecon Record with VYE&C Page 31 of 31
YNMEATtOtcaELET. YCtWA1 I CALCULATION/ANALYSIS REVIEW CALCUIATP.-A NO _ A. CALCULATION N0. YYC46L REVIS10I u I un% nu. _ _ COMMENTS -RESOLUTION T'r5 CALC ISFi g iiJ A __ WE -103. No.3-1VAJ1AtAL GbA#4f __ cArV to N10r 1 1EMAL. _ _ _ __ _ t~s: _z01O ^ tCOSI o fls C a4SeFJA,-.rtv T'r3 AVJ0 A . SPHrp0W'T CU.-%LC-#-
- A ALt I
2.- s 2.1.4 : c. x .3I's. AVL (4i1-. (~ 5 e~V. 1. oF- S~&. s , A 14o -y X. .'Dse - A\t~SQCLD tmr IS /7AdfFX . ..- S. s% 2-2.t 'EF, F.5 I 3. AA-A AkFT&:+. Q;3 MnaI "X-2. 3S DoEStcAFM w -.& N ,..A 1c: A1t. e 4T° .d' 'wwtA4P~loA /flyr 7f/4/ ME fl7U* ASs~tM ytJ.. ____.. _ _ _ _ _ _
- 4. S'P Z2a.4 2 tK S DZ94 4.5L4.17A. G;L .ss A&r. . -L:-
Identify method(s) of review:
- Calculation/analysis review O Alternative calculational method' O Qualification testing t Resol utl on By* uit 9 Preparer/Date Comments Con ued on Page: 2 Concurrence with Resolution v<?/X/ /9/
Reviewer/Date WE-103-Z6 FORM WE-103 3 Revision 5 j(-e I I
I YANKEE ATOr.CEL aEG 'N I I CALCULATION/ANALYSIS REVIEW CALCU et ON
*c ItR CALCULATION NO. YYC.-49 REVISION NO. -
COMMENTS RESOLUTION pBiro~x M. Arr. & Does 46Or - ar. s A4. ? / (pp Z.Co 77W- sflA le3 q'l CII# Sr4'r ScnxNe. TlgIUA &43.c.4 w-~ AcmA-. IIS1 t'. XT t! oL. ,a SCAL' fferAIDt" 1 6, '4. PMC+X
& SEXBOI-1 e4.AO I
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- MOC' ts s" -~ 'L. 4k *s;4oL,C 9 A5
.S91: T . MP'C $ ..
i W - :
- C. /Qz ( 7hA (I '& B.^o I ij Identify method(s) of review:
- Calculatlon/analysis review O Alternative calculational method, O Qualification testing Resolution By:I . V4 k tb</9 Preparer/Date Comments Continued on Page: .5 Concurrence with R4 esolution 71- l/
/pB Reviewer/Date WE-103-26 FORM WE*103 3 Revision 5 I1.
YANEXE AAt EC R',"' C J I CALCULATION/ANALYSIS REVIEW 1i CAWTNN:IA CALCULATION NO. v Yc. 46LA REVISIDo i HO. COMMENTS RESOLUTION
>vi.r- i/E Anr F . _. r /
1a42 A3 A, 1'o~r bMotcatI(,ure AM C Nl IW'IAI/_ r STE r 4.~ 4. .- 1. 5o
- 13. t- 6resicm1 G.sP 5i6 Q40 r..c ® E 124rK S*LSC
. 43
#t aw-rZA106 !S3rc&
lLPRS6 SI7MC* l"C1c& Xf_.Czir4F Z eaege- Is ~rP Cc"NSIeATS _______________ Identify method(s) of review:
- Calculation/analysis review O Alternative calculational method O Oualificatlon-testing .
.Resolutlon,By-.1UU (.0 be+- //
Preparer/Date Comments C ued on Page: Concurrence with Resol7/3/5'S ReviewerlOate WE-103-26 . FORM WE-103-3
-Revision 5 I
YA.4E A70N60W I CALCULATIONIANALYSIS REVIEW cwuZxmrio wj- 4 WA CALCULATION NO. vYC -46A REVS101I NO. _ COMtIENTS RESOLUtON A! ,c A.(ms A. .o .- _ . __-_ ______, _________
- , -t . , -I ic,. sfrE4' 4 .(0,2J, r2;t t 6d, S1 ATY A, VbJST -CA3P VtFC FRLP.
i 6C5 S§r-fbi,4T PZc-FL ?O 0~J~~i - ,. ,, . Identify method(s) of review:
- Calculation/analysis review D Alternative calculitlonal method O Qualification testing . --
Resolution By:)4 Wr '7/-,LZ-,/7 Preparer/Date Comments Co nued on Page: . Concurrence udith Resolution _ //______,________ _ /__/_ Reviewer/Date WE-103-26 : FORM WE-103'3 Revision S ,- I
VERMONT YANKEE SETPOINT CONTROL PROGRAM A777c)C4r#J)70 tNTERDEPARTMENTAL REVIEW OF CALCULATION: VYC-462A Revision 0 VYC- 462A Revision 0 has been prepared and independently reviewed. The Departments impacted by this calcuaion ar requested to review the results of this calculation, coocur with the results and/or recommendations, and document thie deprunent's acceptance prior to the calculation being approved.
- i. Srnm : This calculation evaluates the uncertaintyh setpoint for Main Steam Line Hieh ener
(. EL Detection). 2- Calculation OD~i Items: AP-0028 to be Assigned 2.1. Non _-- 3, -n ent Review -; contact the Sctpoint Programn Manager (G. Hengerle) if not in agreement with the
.on..
conchstatements. 3.1. Ve ltmYankee E&C . ~ __ ___
.3.1.a Procedure OP-4322 Revision i2 will rquire the following (based on Custom Technidlecications
/,:a- srveillance sutd cycle):
*. t.ine roiowmg mn nc pruccaure aLscussaon:
a Limiting Setpoint
-7S-2-121A1122A1123N)24A - 19i OF.
7S-2-12tB-D/122B-D)123B-D/124B-D 1-87 'OF'
- b. As Found values:
.7S-2-121A-D/122A-D/123A-DL124A-D II F
- c. Revise Head to reflect: NA
- d. Insert the following M&TE requirements:
Omega Omnical 4A, 8A, or CL-505A, or T/C reader
- 2. In the body of the procedure and the data shedt revise as follows: .
- a. Calibration Tolerance - From To 7S-2-121A-D/122A-D(123A-D'124A-D +/-1 F J5 OF
- b. Trip Setpoint From T.
TS-2-121A-D/122A-D123A-D124A-D, . 185 OF 18S eF
- c. Revisecalibrmondatatorefletheadcoifetionof: NA Page s of 7Y
Vermont Yanrkee Setpoint Control Program Interdepartmental Review of Calcilation VYC%_462A Revision O0 I.. A IF % W7I'J~!
- d. Insut a 9-noint calibration forall analoe instnrnents: NA Tranilr . Recordrr I1AkOW Squa Ro Ccnv Oder fq4MO ID) . (Eqt ID] [Eq-0-M ID) (Equ4-en,,1 D) (ew ID]
.Inpt - O nutW Oubtd Oatpt NA Outpu 1npt OutPu 0% mVA 25%
SO% MA 75% - . mA 100% mA 3.1.b. The following commentslrecomiendations apply I. Incorpratethe above changes. Sign & Date Vermoq Yankee E&C Rrtative
- 32. Verl.tont-Yafikee Reactor Engineering Concur 32.. None Sign & Date %L4 Vermont Yankee RE Representative 3.3. VermontYankee Operations ---
3.3.a. Operations should administratively limit (standing orders) the maximum acceptable setpointto 196° F in lieu of the 212° F presently allowed by the Vermont Yankee Technical Specifications. An ER has been gen W to address this issue. Sign & Date Uii /WJ 9 Vermont Vakee Onerations Reirese i 3A. Vermont Yankee Systems Manager Concur Comments 3.4. Ihis analysis supports the design bases for the MS SystemL i Sign &Date VewntYnee Syft n gineerr.g9pe~ttv 3.5. YNSD Nuclear Engineering Concur Comments 5a Cudtnm Technical Sneelif'watinnst
- 1. Analytical Limit used in setpoint determination: 1 6%F
- 2. Potential accident trip (LOCA): NA
- 3. Potential accident trip (HELB): 1960 F VYC -
3.5. b. Improved Technical Specifications
- 1. Analytical Limit used in setpoint determination: 1960 F ci
- 2. Potential accident trip (LOCA): NA ci
- 3. Potential accidenttrip(HELB), 196 F ci
- e Sction 9.i i de en *V-/4 0ooF -Ai MS 7^/Agbt Sign & Date 4 . --
INSD NED Representative -- - Z Page G. of 7
z- .-. . ;. . - ; Vermont Yankee Setpoint Control Program Interdepartmental Review ofCalculation VYC- 462A Revision 0 477DdA4w-_.r ^ 3.6. Vrmont Yankee DBD Manager Yes No
*3.6.a The Main Steam or NBVI DBD should refarece this analysis.
-The DBD ii complete (an AP-002n to follow) 0 S I. Tle DBD is not complete. Incorporat refere ice to this analysis as app - -af-Sign & Date J J/-2? v rspESPProraiManager
,1o ,-a n.e.
3.7. Vennont Yankee Licensing Impact Yes No 3: 7jL FSAR Ohanges (AP-002s to follow) TabLk 7.3.2 0 0 3: .7.b. Other t on licnsing basis: 0 0 The C73 he a limit ofa]2 OF. The Anaf)&a Limit is 196F.It isnot tcqabk La have ancAL C73as diw allow the l tmenfUP0int to be above 196 F(ousidethe anaxyis limits). Either di NED anlrisneed to be revised to use a value of 212 -Forthe CISLmUk needr to be lawemd
'o 196 OF. An ER has been generatedto ades this condiion CrAPO6 r 7 ~ 'a A s-Z "b ~ Sirzg DaeD .
Sign&Date ,v / zz2?S 3.8. Vermont Yankee ITS Manager - Yes No 3.8Sj This analysis provides an input to the MlS. An Allowable Value applies. C rj Allowable Value L94° ) 7%".kl 196rF &,- A s 3.8h. This analysis provides an input to Technical RequirevientsManuaL O Incorporate as appropriate. Sign & Date / 3.9. Other Department(syProgramn(s) ( None
..C~oncu 3.9.a. -impact assessmen/recommendations: A O Sign & Date , _/ ..1-21iTi
-IS? Progad mam -
- 4. Setpoint Program Manager
. . Completed 4.1. Concurs with above.
4.2 Interdepattmal Review form (copy/steps I through 3) incporat into calculation. 4.3. Calculation has been approved. .A provedon 1/-23-91? 4.4. AP-0028 commitments have been assigned and forwarded for incorporation into the Commitment Tracking System. Sign& Date - I/ //2X-ST 1?SP v1rofram Ma6ager Page 7 of "
Vermont Yankee Setpoint Control Program Interdepartmentalt Review of Calculation VYC-62A Revision ° , e o
- 5. Post-Approval Requirements
- a. E&C (perform as appropriate):
- Initiate AP0022 Sdtpoint Change Request
- AP0028 VYC0462AROOl
- Update MPAC
- Revise calibration/functional/logic tes. procedure
- Infonn the following after changes are hnplamtemd:
- Setpoint Coordinator
- Setpoint Program Manager
- Triining (notified via AP-0022 if initiated)
- Operations (notified via AP-0022 if initiated)
- Design Engineering
- b. Setpoint Program Manager. Update Program Manual AP0028 VYC0462AR0-02
- (after step Sa).
- c. Setpoint Coordinator. Update Setpoint Data Base AP002S VYCO462ARO-03 (after step 5.a)
- d. Design Engineering: Initiate FSAR/DBD changes, APOD28 'VYCO462ARO-04 as aq p opriate (if DBD has becn conpleted Comments:
I) An ER has been genemaed to address the condition weeAL<CIS
.. I Page 8 of 7.
VY CALCULATION CHANGE NOTICE (CCN) vVC- 4Q.A - Cc.- a CCH Number. Ol ClcuMonNumber. VY 62A Rev. No. O Initiating Doc t P 991 10-00: Commitment VYC30462AR0-03 VYDC TMMpcc. NoJ olr SafetyEvaluationuber. N/A Supersede DomenL: N/A Reason for Change: Provide a beiis for mcrease in Technical Specification Survcillac Interval from Mouthly to Quarterly. Description of Change:
- 1. Evaluate CIS Quarterly testing interval on calculation wotputs.
- 2. Address comi memo issus. -
SEE PAGE 4 FOR DETAILS Technical s cation for Change: Technical Specification proposed change No. 217 requests surveanc test inrval change frorm ontilyto quarterly.
== Conclusions:==
For CrS Quartcrly.
- 1. Existing setpoit and uwcrtainties support Quarterly functional testing of logic.
- 2. Sctpoie, calibrton attibutes reainunhanged.
SEE PAGE S FOR ADDITIONAL CONCLUSIONS Prepared By/Dae lintrdiscplinc Review By/Date Independent Review BylDate Approved By/Date Tte VV LW Fa .- _
%%.37-$" _ Alh/
Instalation Verifction /2
//Siature D//lDI Note: VYAPF 0017.07 should bc inlude imdiay following this form VYAPF 0017.08 (Sanple)
AP0017Rev.S Page 1 ofI DI #99-381
VY CALCULTION DATABASE INPUT FORM VYc.C -4 7CA --W _I A. VYC-462A-CCN 0 N/A N/A VY Calculation/CCN Number Revision Number Vendor Calculation Number Revision Number Vendor Name: N/A PONumber: N/A Calculation Type (Originating D VY DesiMn Engineering (EI&C) Implementation Required? No lIRY Asset/Equipment ID Number(s): Various A et/PfSvctrnimI u'nmherfk) 2 Keywords: No New Keywords General References Reference # RefemceTide rmcluding Rev. No. and DMtc, if anolicable) (See Arp.A. Section 3.1.7 fr Guidnnce) Critical Refernce ( I 1 .Technical Specification Proposed Change #217 Design Input Documents - The following documents provide design input to this calculation. Docurnent Donmrrt Title (including Rev. No. and Date. if applicable) Critical Reference No New Design Input Documents Design Output Documents - This calculation provides output to the following documents. Docmwt# Document Title Critical Reference t) No New Design Output Docunents VYAPF 0017.07 (Sample) AP 0017 Rev. 5 Page I of I
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- 1. Documed the loop fim.1ion a:d the basis for the sepoq i and opaiwc siises with that func.o.
I
- 2. DetCmlne theC oMal ndW ttld loop Mcany and vaiycmsecty WM td design bsii . .I-,
- 3. Caolaer the lig scipolnt and opeator dcision points
- 4. Evahsste the adeqwcy of die existng setpo, cathaton limits and _ dop&wza dccsioopoht
- 5. Provd a-left and asfod toleranes fr use in calbutio prmedcmine Ukasring and Test Equipnct seckxo wd accracy cdriazl d wc rpoessncdrtcm. it"i 1 zmw alodn methods.
- 6. VYDEP-15 sujuirs that applicable opraftig peoceders, alam nspoaccs, standad, off-omxal and emerxcy operati procedures be included in The c slnhimwhis r' quciti-rt is co'd 0y3thtebcnipmyreviewtasuppkmentsat pdWE-103
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=N SAscok t 1C441 7.i '!1q Uls.calcuntm apple to the 1Msa Sem Le Aas Ito E U Lin Brek (E ) dea switc hes fteacimhe Boilr OMB) Sys The secifi compnents to be a aw. 110i00 TABLE I S=Maz{
121Stem Tbmid Tempertu F *wal 01-17002D0.90 1100,1101, T-2-122A S it256 102,1103 6.1 TS-2-121B TB265'NE T. Fa 7000 11,1101. SwhSSc2-1221 1102,1103 6.1 1S21,23B TS-2-12 1C I Th26S'NE T pe ui e F amwl 01- 70 200 1100,1101, ujA - i TS-2-14B 6.14 T2-121C I B265 E TCMewume WM 01-170020 09 11041101, '*,'V4 TS-2-122C S . l1I0IA 1103 1S-2-123C elit _' TS-2-124C_ 6.14 TS-2-121D TB 265'NE Tempeau Fenwal 01-170920D090 1100,1101, TS2-122D Switch 1102,1103 TSC2-123D _ T152-124D ___ _ .,_
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*1 Mfi Steam Line Areas High Tezuea Setpoint VYC-462A RP. 0 trjo
_________ ~TABLE 2 EQ Matrix Datae____
.Lcation Accident CAT TBN12 P1," Dation TS2-12IA,122A, Vol.41 LOCA C 36 0 NVA 123AS12A HELB A 4 1 ir.
1 HPCIHELB C 36 0 NIA RCIC-HE C 36 0 M/A RWCU4ULB A 36.37 1 1 hr. _ HHS-HELB C 36 0 NIA 73-2-121B, 122B, Ta LOCA C 36 0 WAN cc4-123B, 124B MS-HELB A 4 1 1 br. TS-2-121C, 122C, HPCI-HELB E NIA 0 N/A 123C, 124C RCICHELB E N/A 0 WA OV4 TS-2-121D. 122D, RWCU.HELB C 36 0 WA /2IT~ft 123D, 124D HHS)HL C 36 N/A M S., 13A -Ae r P Functm These channels do not provide any Wnication or any fuittber function onePCIS isolation acuates wien the protected ws reah the trip aetpont Thee channels re no identified u post-wcidet in Technical SpecifcaticanTable 32.6. humentation 2.0 METHODS AND ASSUMPTIONS This calulation has been pred in with the T Vamont Yankee Insirument Uocrtinty and Sepoint Design Guide" (Rcfrc= 6.1). and WE-103, -Engineering Calculations and aLys (Rlfrence 6U Standard uitos mploye in i calculationm exicd I the Deg Gutde; speetchniqcsandal1ria we explioed beow. The requiements of VYDEP-I 5 (Reference 6.5) ame wcomplishea through the Intudisciplimy Review pro 2.1 C
. .1 2.1.1 SciLQ9 As shown in Table 2, these compoaeats are associated wih Safety Function 1," SB Detection and Isolati." Consequently. per the Design Guide, thse component' trip sepoltr.ae Cass 1.
Nucl Safety-Related. 2.12 M ing CoIMM12! Per WC-462, Revision 2, and VYC-1599 (Reference 6.15 and 6.10, respectively), the ran of dtese switches Is(-)1 00F to (+)600WMff Th. Calibrated Span (CS) in CS -600-(-)100
- 700rF Page 7 of 31
- .1
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*71 LIA 2.1.5 Sim Con The sign cvamd used inthe Design Guide isbased on the effect of ocatinties ea an WWrwnt (Or loop's) out SignaL For this tye ofdevic whete tm isno analog pocs hiPutAign output edaLanM* the effect of unc~erstates wre ninifsted as ashift inthe setpoiat awRy fromthe deW value. This reS hI a sign conventionwhich isthe reer of that which Is gnrahydefied in die Desg Gukk, 2.2 == 15etss Tv t- vt-- ICCe-2.21 The ero tmm -empeUrC Effec CM Is uot applicable becais temperaahe is the mueasind Iti?4 paimeter of the device. 11/f,6 2.22 The efect on setpoint of harsh emirmnmailal conditions caused by LOCAIHEL aweneghgiblbe (Atachment G&P). These include:
- Setpoint Shift
- Radiation Effect (RE)
- ContsctResi
- Inston Resistaice
- Humidity Efect O (Refcae 6.7.1, Section X-23) 2.23 For CQ = Technical Speffication (CTS)applications, fte CTS value i typically assuumed based on normal opeaaing coodidoos.However, ths case duriug theeven for which tbese switches we credited (H ) a prmsiadon may mm (seSection 22. Cm=ecety, for CIM as well as S, this pressurization efect will be acconted for.
2.2A Per erence 6.1 for kaproved Technical Specification (S) applications, the TS value Is assumed based on the most limting of HEL with E and HE E Seismic Effect (S). 22.5 Per the onal plant design instrument dab sheets (Dawing 225A5600. Sheets 94 and 95, thesc snitesee Fonwal 170-40 (-)lO"Fto(+)600F.PerteEQpmgramth s swichesae Pal- al 01-170020.- ,range not pecified (QDR 9.4 1 ci xIL worshet). Per the veadornanual (VYEM-02) ft eswitches aro$, (Poduc Line Sold) 01-17 1704-9no range specified Per VYC-1599, Tal 1, these switches am Fenwal 01 -170020-090 (-)l00 to (+)600VF. Per PAC(pa 1 and page 6, e 1) thse wsds are nwal 0 1-170020-090 (-)4F to (4 20F . For the ppse of th caulatio, he following is used as p bsed on approved eang eing sources: MFG - Fenwal (QDR 9A) Mode 171020-0 (QDR 9A) Range .(-)IOOto(+)600(F(VYC-1599) Page 9 of 31 .. . a.-
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?&I t3is -- Ae41 4ik12 Main Steam Line Areas High Te ganpe Setnoint VYC-462k Rev. 0 2.2c6 Per Refrnce 6.7.1,there isa presse dect of+3F per 100 psi PerRefeence 6.7.2, the maximum protected area pressure rise is +5.1 psL Where HELB pressure cffect (OP,,) is:
P a (31FIl0psi x 5.1 psi 4c20F (Conservativly Rounded) And Is manifested as a (+) bias in the nonconservative (rative bo safety fcion) diection. 2.2.7 Pr Reference 6.1, tie following normal condidon uncertainty terms ar awompassed Inth DA
- Measuring& Test Equipment Accuracy (MM
- Dift (as a finction of time) (DR)
- Tcmpztre Effect (AT 20-F) CT
- ftesure Effect (PB)
- Humidiy Efc (HE)
- Ra = Effect (RE)
- Vibration Effect (non-seismic)
Based on rcczlibraio, the above terms are te as noncuubdw. 22 For titype of dice, t follwg normal condionUctaintytems enot applicabl
- Static pressure effects on spa and zero
- Powersupply effect 229 Per Rcfece 6.1, no uncertainty is cedted against the rlays cortolled by hese devits.
22.10 Based on the design location of these devces (sce FSAR Sections 73A3 md n 73.5) the noncouservative affects of Process Measurement (PM) arm negligble. 2.2.11 Per ClS, the specified calibrion Interval is "each rfuding outage' Pt Reference 6.9, this interval Is rypical bounded by Is months and is Wma rnmiting (by the rdfelig cv not calen~dar days). To allow for a rfteflg cycle extended to beyond a moSnhs. this calladon will base extrapolated DA on a maximum interval of 6c4 dys ( i eria ofoce per operaing cycl +25% as a coavenice. 1 f tbe cal ineral ds forwhareason beyod 634 cal dra an evaluation to determin the interval increase ee n scpolt is 2.2712 Per VCY-1599, Sction 5.4, th ana d drift da fr se dvic I(pooled Proced OP 4322 mid OP 4366) indicae litedtime depeiidacy. Consequently, h Is ed hat RSS 413;L Ift trapowbon of acaraton interval is 77paitefo oe v.e I ',A4L. c.. (7 %whow 4Ws-5tz0f3 l4t ~soJ~c
.I. A 15 e %..'r to
r - e".... VY'A C-ZA-CZ-o& Vc-646M ofR41ev. Main Stam Line Areas High Tenmerature Setboint VYWC-462& Rev. 3.0 INPUT.DATA Daft used to calceht loop uncertahxtics, Selpoint and decision points are tabulated below with doe ippicable reference or basis.
! 3.1 Pmom an Low Date
_ __ __ _ _ _ _ _ _ _ _ _ T A B L 3 p ioe s~L op Inputs _ _ _ _ _ _ _ _ _ IlReavoce Descripiom Dafta (OF) 6.18 Amytca Llmit 196(otside atm t0e) II 622 2006(isid mno lunel) 6A. Table 32.2 Qtm Tedmical Specif6cion Linmt S212 66.6 Exkflg Calibatio Phrocedure Sdtpoit Its :t5 6.4, Table 42.2 Calio Inevl I R eiigCyc 6.4, Table 422 Functional Test Internl Ondlloh -
= _ - - , 3..e- . A :
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?"e, MSoef441 4Ik Main Steam Line Are Hih Tetm = welSdoint _ C-462A. Rev. 0° 4.IAA2 bnokmer t1E In suppott drSectlon 4.133 and from Section 4.1A.1, the folgwin is d tobe rpresenstaie otMTE dforcaLtwution:
MT 1 - *I.0S0F MTE2 - 4.00F Caosequeatly,
*IME4 - &1.0052+ 4 O00 F
-*413*F 4.1.5 d Drift (DA)
From VYCG1599 (Atachment H), swritces calkamed per OP 4322 (the scope of this caulation) and OP 4366 (RCIC HUB Detection) met he ariteria for pooled da Toe output of VYC-1599 (per Secdon 42) isa 95% probabilit9% condc level vaUe, wi meets tie cti ofa Cass I sctpoint as per Referenc 6.1. The foowing data applies to DA:
- Avea time Inteal Is544 days
- DAis* 7.54'F
- Data is evenly disbtd about wt a slope ohetime de ncyne equvalntto
*<0 % per approqhoaty 550 days sowing, consequently, little time depedecy.
- Tbe data Isnormally distruted with a higy peaked nmaow dribto
- Mm average drift vahle for this group is 0.008% CS; since dtis vahlu is lesthan 0.1% CS, bis effects ar considered negligib 4
Per Assumption 2.211 c ofDA frn a bwS SlO550 days to a m=xmm of 684 xAtpolaion days take te form: DA,, - DA,. 16945441112 DA,,-+/-7W54 F[6W544'l DA."3.45 IaC.e- A ASe.A- 9 -14 Page IS af3l
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a-_ 1vimn T!_2-:_ ie am LAUC A - IAXa ;- 1 -r VUJIe I T _.II n-WamLtL44,L VYC-462A.CV. 0 lejt'o 4.1.6 ea-M = Effect 1 T1pically, DA accoa for a 20F ATl during cariondito In this case, G has dto followingecosldrtions:
- The easured process patimeter is temperature, for which the device is designed.
- Calirstion technoque Is lo preheat the swtlch (and associatd calibration Tn and use a prefabricazed test heater asmbly to minmibs any acx a influences and aproimate normal operating condition pror to tempmxtw rmp-up to setpoit Consequcmly, normal Tf as an emrvo determinant is considered to be negligble.
4E 0 PerReftence 6.1, noralrdiadon effect iencompassed by DA. RE-0 4.18 !frnidity Effet (HE) I No humidit effect is specified by the veadr. In addition, pe Refeence 6.1, normal humidity effet is encompassed by DA. HEW.( 42 ;r dUncerbitaw c) From Refence 6.1 for this yp of device, and wber there are no sikntesting condiion blaes: bi. e- * [C + DAlIW _btiuni-F I I""IttA-I 4
"' [I 1 1
- *912*F -
-x o t114t Accounting fr a single side of interest approach ss per Section 2.13: 2C I/co Aj-E Z17 I
e, - *!92F x0.S5
- itL347F /
To facilitate the calibrztion process, ;,is conservatively rounded (with regard to szpoit devcomcat) to: e, - +/-S.OOF¶ I Page 16 of31
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-^^---- _
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Amas Hikh Temnerature SetDoint VYC-462A. Rev. 0 q04 4A.23 msure Effect (OPm i PerRefewc 6.7.1 (Aftadut G), . HELB can =Utt Inan area presuri msTe wvort-cm pressme Incoease is(4-)5.1 psi and rults in a (+) bias shift i thes int Jopq=6o to te eiett of prswimio. From A2mptim 22.6: OPmSU - 0.20.F 4A.2E4 HEB Modk Un ( Accwti for imcerainies wWhch ar negligibke orot applikabk:
-*[cEC t + DAJ + OPums; Substiuting:
, -
- I5.OO°F + B4SF 2 1A (0.5)+ 02oF Dt 8.55OFV135'F e-4A.3 Seismc Module Uncertainw (' Q For HELB mniiation chames, em is deimmined by HELB conditios of over-press coincident wit, or sbqen to seismic dfcL From Referce 6.7.1 (Avzchmai .),
post-aelsmlc effect omged om -3.1"F to +442?. For csavwtim, the post-seimic simulaon fucon accc criter of*50F istken as limiting ev-v :L4h' c CA - (See. = Q e) ,'Vtiqq I i Accaung foruncertainhti itrd by aseismic cve followed by switch actfton caused i I by a nuin stem fine HELB: i i 2 [*CE + DA2 + SW -+OP
=* [5M12 + L4S + SMFuz (0AS) + 020.F
- + 9.57F1-93rF 4.5 SCin-t Evhnf 4.5.1 Custom Techncl Scicifatlon (CT$!
LSP -Is-I TW I However, because AL < TS, the AL becomes the mo lkitmg condition. ICCA-j Pag e IS of 31 t A- f -C~er qft, e)l7Sol
WiC.-44GZA -cc i co - VY CALCULATON SMEET Calculatfion Number: I'{L-4 zA Revision Number. - CCN Number: O Page.4%0f *e'47
/ ~>* ~
c~ct4
* / T\5
+ 4~~s)t
~C 2/3/VSXSt4
>, tG w^P~el to.>t~rc-5LL btere *
(A ,rJ ; ^ 40- e 44-tz-vc -sr; 0.5 oS sr lc~ A4 I*5 r ea U _ wVj-A A ko' ksc5 a.c lo AL.,V. A4C)O 4 ( At, A.Ls -fi4t4Zo-ce ( 5* e;-t... >^$,rLLe- 3 ereuce~so1.) 4 '5 CTS C.Lti) __ @r so 5vic.-.& 2 -r IT$ VYAPF 0017.03 AP 0017 Rev. 5
'JYc-4-6A -cc" - o&
? . 2.o of 4f41 CU14 mVamI Sf aUm ILJ.IQ C4-- -n A- T-;nhI IZLcI am N TnhL #ntL, WC-602& R. 0 'tiVfo 4.5.1.1 ( 43 . Q II-1, s-e-'.M I 4',. L- IiuL -I 3fi 3 dI-'I .
Where:' bc The Limiting Setpoit t4AserAj OA 4 -?Uces IS - CIS Table 322 Tkip Setng s212?F(NocUsed .1% AL- 196-FTable3) TU - Total Loop Uncertainty dfichm tbis csesmrices to:
-CM~A (+%" is the worst case Vctor) 34X700
_ . 1966F - 8550F
- 187.450F, conseratvely unded to:
LS 17F s C-CAI - 4.5.12 _ _A__ _ _
- 1s L - Inu TLUu I Where:
_IZ44.1 4 Aa.P-4
$e.%V5 TS - CrSTable322TripSetting ,24 *Jifc 5212'F(Not Used) \ tze k.o*
AL -200-F(Td"3)
- Total Loop Uncertainty wh, inthis cases redces to:
- qmzL(+em 3 is the worst caue vector) 1'GrA -4 Substlin Ic~c~i.~i LS 200 - 855F
- 191A5*F, conseratively rounded to:
LS"A 191F yEo. Page 19 of 31
I- *41c- 4G2J9 -cc-A - o -i IS-'n flA .
- m
.3I&.C... 1 f#-.;n
£11 A-.
f lfG j
- in Mml t
m nhOt fl in. 1 YC-462A. Rev. 0 )*(Dv 4.52 Imrnoved Tecdmial Speification flM LSP 2 AL-ILU I 4 S.21 O Where: I t~q;-The Limiting Seq~tpo AL = The Anlyfta Limit tX%5eik- i V 3 pk-o-e- T1 - Totd Loop Uncatatywh's, Indti5 a eredcesto::
- cws (+eln is the worst-case vector)
- 196@F - 9.7F I
= 16A3, conservatively romm
- 16086F
*Ic^c.-4 C-CA - I 45to Wbaere O LS Tbe Imitaling Seq*W AL - The Adatkal Umit TI,5e4 F a0
? TNU - Total Loop Uncertait which, in this Case dt ° ,..i CM (4c, is the worst-csevec) 3 I? t4 t-S 16/64/ov Substit:h ,: er e da c es w I LSM- 200°F - 95rF 190.43F, cousenvaively rounded to ILI'7-4If
$azf.of LS 190MF Pagc20 oF3l
VIC- - 'r(, - -c-c - CL.
?&IGZZ. of 41 j Main Steam Line Aeas Hifh T fture S&ioint VYC-462A.Em. 0 Y 4.6 M1n ahmioI 4.6.1 Custom Tcchncal Specification M,-LSP-SP
,-~ i ;.q_
1e' -t%
-- O.+rF 1I nF - I WSF IC--tA-~
XsA- Z.L M9 .A, . Y
-. V-.
Stnbin& -oS4S+ Z -s tlt o~b.7s/06 91'F- 195 F W.46F ,
,tc(f-o 1 5Cb%4 2.4-4.6.12 HEM SEty Mf min M. to Exfti Anlytical Umh (AL Per Refereace 6.18 (Atadrcm B1 1 Me euist AL imide ft s Celgjr-
.Wische. 2001FadoutsieDC ird1961F'd Ides&6 ' 14-i.t r
allowance for lnstimuz error. Tbe exstin setpoit fom BRferaecc 6.6 is 1551P. ,s Ihe 'normal coondtioe encertauity applicable to CIS J4 to eding AL tiR T4' dmust "s"' consider gme HEL1 OP effect, thereore (posite vector) Is uwed. Us M,-AL-[SP lI
- -+2S1 eO
,. .) .i -,
Su_ ifr>IV , "ItL S~I *. _t L W y A I tNO' 200'F-(I2S-F+USS'F] I - A. 4o-- ful"f 6 ,\+6.4S'F - 41o ! I Page21 of 31
I Vyc. - 4caA -c..cA -oj..
?61 eZ of O41 Main Steam Line Armas Hid Temerut Setvoint WYO46ZA ReV 0 4.6.13 HELD/Seisnic Safcv Munin (M,) to Existing AL From Se&icm 443 cm (poskive vector) is 9.57'?.
IC-CA-tl 14 .0 :t,41 3T_
- ,-~ I6F -11 85F + 9.57 11.1 tX-A -&r I 4=1,
-+143'F -
- xtFsev~k 3j 3
_; T +2OO4F-[15F+ 9-7F]
-+5.43'? T.I 2:*1/62 'Ist 3 2- -
4.6.2 Immoved Technical Specifiocaions (ITS) F Refere s6.18 (A 3hmetB) and6 22, the curentAL is 196 anud 200*F inside thc stan tunl. Fo ITS;: iF oratside the se n i 3 *FytioB p it cansbe cen that nominal margin fiom LS 1" F) is +10 F nd f(vme 3 10 190t F)Is +5- F. LS&nk~9
. ST* Per Reference 6.16 (AtaI ent M), tie ogi plant sigwas foran SP wh was '95'?
above basetempereumrtw From rvwof a platra m trends (Attdw= G), Thsr1t- mai4 aassmertteisnmed to be 1400?. Since Ls 2 ccounts for tge Combined ef of HELB(as applicb) ands c effect no a # main retive to LSP, is reqaired. 4.6:t1 Impoved Technical SoEificat Onerine !dvb( For an e,, of (-)$A*F (non-worst case vectort a maximmi be temCrgr of 1406FCr>),Aoperating sargin h expected to be: M,-[ISP- lI]ez1I- T..A Subsdg:n -r_ . I -_
-J-%5e-%-T 3!;
. a T186 - I - 8AFI I - 140'? Icc-L
_ T -+37.60'F _ _.,.IZZ1ff0 2.. Zht/0 ,MhL5Cvk4 3 Ce Page 22 of 31
vc,- 4-(zA -c.c4-oL
%"tz(4 of 49A1 A*1 i Main Steam Line Areas MlAb Teraneratwue Setweint VYC-462A.ofv-O 4slSO 5- 3iseseA- 313 I V [90_F- I- 8.4MF1 1W0'F 3V7V le,-LAL
_-WII~
-S~f I 3@.ie
;e L7 4 -b -V441JU Alowsbleyulupl1SM F.-
4.71 Lc Acceyance Vu (ACM Fora singk companec loop, thoe damuao of ACV (Ihe kAgebric mtof each componew' as-fov d tolemnes) is wt applcb. 4.72 Allowable Va A Ft=> Refeene 6.1: 4.7^.! ; A 3c ClC^X- -I. b'XheiA 40 AV -1u5n p J-Ci eX X
< e 39 - a7l"O 7x/5ho
& .~
AV;-1W6F + B.OOV IC-Cr-A Suh t i 6Futh 2t3t iw..1 .. 4o =1941F,
- FF/e/:p 4.722 e To ^* 1ll.~e"
/ ' _s Xt5eA 4-4. A- Su tutiag: o+4 Twsfe.s- Ar
. A.
. V.,7,ct;-,
_ 1908 F1 .:y;w-xt . A - 198BF z- Itill.. 4it alibration Toleacs 4.8.1 As4Lft Calrib n ToLenet (C As deceloped in Secion 4.132: j C1 - 5.008Fj i II I Page 23 of 31 I
I1
'IYc -4 r.7A - c-c- -cL WI c Z.5 o 4z41 IX..-n O. I - A me Uh16 T.hlmp Ct^n;n.
VYC-AL2A. Rev. 0 t4,Ie 5.0 RESULTSON-CLUSIONS 45 4- CLY-I!A 5e2 Iqmn Ebgm Faprotected areas hide and outd the sten tuncr s p ted below dIhe finifg setpoimfl (SMP Allowable
, Value (AV). relma Macgls (M.) ud baseline dam.
TABIA 7Sd riolt Results Vc Desatution Rmuts (-F) cr m } Anakitkal'UItA P .4 200 200 Anal Unit ( 196 196 I abcv (AVA) (5e. bA5 e) N/A 19S bVale (AV) )_ NIA 194 t) (1) M 212 3-3 (lirnide) J, M1zW' Exsftcn Setpowne (Sp) 185 N/A a191 190 ii ySe lsp l w187 136 oosmA e e, Its" , 195 A_ 165 Its Mae lm; to SP NOU +5 Mai SP toSPz - .4 +2 .!-~ ; +l Saey Main to xi AL(MvY +6A5 NIA Saty Marcin to istingA14 +2.45 NIA Mar to E A +53 VWA M--V NA -+2 Ic ij tI frOpe iM t L 4v NJA 441.60 hmopet Margin LiEf WA +37.60
- 2. Forfl the AV hdwTS Unk I
- 3. Fxm(SP + em,) to AL
- 4. From (SP + Csm to AL S. From (SP, - e.) to auximam ormal lemW_ _
Page 25 of3t
.--....-. - .- - -..- - .. -..-- A-- .- - --
VY CALCULATION ShEET c-4=. c Cluldation Number. -JIc. - 447Z ARe-vision Number.0 ~CCW Numter: b3. PageZ.C of 4104I uIi-yxII.'0 4f AU-to-1Aa. Vo...U.t.. C AVSt) Vc~c-
>%-AgMeiA- (ALL SVJ% Ir-ES) -
~ t.~.~bI+0 E t% ; !jAL CtAT RCS51~-I 5 t.Aet-i'A ADoel %A1
~~ 1 e'AL Cm 3j' VYAPF 0017.03 AP 0017 Rev. 5
VicC- 44ZA_-cct4-o
" e Z-1.f *4k 1 A Main Stm Line Areas Hih TMRe Setkoint WYC46 Rcv. O $,to 521 WS MAWAHA3.t o Outside Sea T*el 4a, Iv CxcA-&i I7Z*Wf 5Xlse 49 From the *bove table it cm e eo ta with calcuLited tmtintim th esting 747 x sctpoint would slport (for C3 1mnd rFs) the prvst Qastan Tcedzical i ~ bn OfamF L~S
¢ M aloUWer o ~
l Analytc Limit
- of i960 l reoui t CC.
,& t.,
522 In101 3 W.404W0=M- Switel Inside the Stcam T C.- i The existing IWF setpoint is wombale for both the BQ Pogm limit ofM 'W 1ad Technka Specification limit f2l2?F. 5.3 Granpic Representation of SDOi1a FIGURE I Grphik Repsentatbas of Setpohit (CrS) Technical Specincation - 212F Anlical Limit (_nie acaam tunnel) 200F (outsid steam OLiit tnne1) - 1967F j-C LS. _- 191F LSPA l8_ F c- A 3P1 3tA & 5 9c 1857 ( X) - stcam tunnel (Nmal - 14F
- 1. Calculated fbracomal conditions (to nclud OPmx)
- 2. Existing stpofapcrOP4322Revision 12
- 3. Not to sale. pvides rlative position cny
( SP 2 5PV'eccvvwna.,j, aL 5t";4-ce3 5 eALv.+ 5oC CVA Page 26 of 31
'V~c-- 4 (PIA- ccA - od.
?Ale. Z.8 f 401 AgL)j Main Steam Line Areas Hinb Tenmemtare SetDoint VVI'r. QA f
'Rev s A/3.) 5e*.~-t 4 4ce-)
n#4 If. C.Cft - In order to support and implement te resuhs oftdds calculatio, the temperature swikdes ar to be cdlbatd acordin to the fovAng bble: "lZ ff7 TAME S CaBbratlon Attribtes Descrlptim Vale U.its ~z~p'o Stpoint(CI InsideStem tunel 185 OF Outsieaubnetultl its OF s tpir Inside s am iand 135 O Outside cm untoel 185 OF As-left Toluance d5 ' a-FoundTolce . . IF .
~~~- 51, 3( 6 ken I 4LA-f 5.5 Meswa&TstEu -=e eoinzs~1 j-tt /e Testing is aomplisecl with e foowi
*Monitg thocoupk (Typ K) (Installed) eqpmen 75IJD
- T/C Reader (gtal Theromeife)
- Heate sourceCratHeter)
- Digital Mutimter
. Varic For calculadon pupes, only the TIC and Reade have relevant associatd unccrtabies, developed in detail in Section 4.1 A. Since the TIC is an Installed senor calculation r=Om nended
)AT reduces to the TIC Reader.
Page 27 of31
,V9l - 4(zA - cc.9 - o L VY CALCULATION SHEET Calculatio Nuber: VC. A Revision Number. _
CCN Number_o L Page Z2 of 5 -it 4 7 '& 5.4 A.~ettv Cr&e;, 3%.AO CCN- I tl 11z,1. Il/6 NE:h5e S2-s..4. Z FIncAXo4.. Tes 4 5b- We40 g @-t of 4 1 L-hFVL 4ev: Al 53;5X go+ t ezS.3J sr VYAPF 0017.03 AP 0017 Rev. 5
F r VYc, - 4(.LZA -cc.4- 0 j Main Steam Line Areas High Temrrate Setint VYC 462 Rev. 0 TAME 9 Recommended M&TE me tqukvdecanrcy ActWaAcemey . Omqp Omnkcal 4A h A :t30F IOV& Omep *30F t.SF
.50 611 5.6 Recommendateon 5.6.1 Subsequnt to this calclation's approval, vise FSARTabe 732 as peAtachm K.
5.6.2 Revise OP 4322 Inaccordance with Table and Tae 9. S.63 Ensure ta a calibration traking sysm exists to evalute consequences of a calation hnteral greater ta 614 days. [Note: There ae no plans to extend dte calbration Interval beyond 64 days] j
-1_
5.6.4 Add VYC4462A to the List of Rofenc h354' J 5.65 Evahat the acceptability ofan analys limit ta is less than the Tedmnical Specification Likit for an increasing trip setpok 5.6.6 Revise Section 7.53 of he EQ manual (vaous places) wicha we 200P as the MSTV isolation trip settn This sh d be the nomina setpoi (exitng and retained) of 1961F as Implemented by the HEL analysis. The 200'F applie to the $teem tunne only. 5.6.7 Review end update MPAC pages for various aers amd omissions Ths rroneous setp hoicraucnek or 190oO F. 5.7 VyDw-1 Crhria VYDEP-I5 mqaires th Impact to plant pog , icensg ad dei docu are considered Wuis calculation hbs been ree f a To fully Satisfy VYDEP-IS reqiurents this calculation sa of depatmnts and provn that could be impacted by the susults and conclusions. Mhc followinghas been considered and is either addressed in h analysis or viathe W d kenreviewPMc=v
- FSAR changs
- Tedmical Specifications (custom and ipoved Teduical Specifications)
. Pwcedar"
- Technical programs I
- Prhfn ,
- Related Design BaAs Calculations (input/output)
- Desip Bsis Documents Based on the above. all impact consideratons o(VYDEP-5 awe addressed.
Page28of31
Memorandum iC-4Cz.A -ccd-coi TO: JamesAllen VolC 3 dP FROM: RE: Markmcrinley Comrntment VYC-0462AR003 a 7 DATE: October 20,1999 Jim, The Setpoint Database has been updated per Commitnent VYC-0462AR0 03. The Comnitment along with closure nm has been forwarded to Roger Vibert. During review for close out of this commitment, several discrepancies wre noted and are discussed below for your consideration of appropriate resolution. The following discrepancies were noted EMPAC:
- The following EMAC assets should have calculation VYC-462A added to the references section of the asset records: TS-2-121(A-D) / TS-2-122(A-D) / TS-2-123(A-D) I TS-2-124(A-D)
This Item has been addressed by submittal of EMPAC equipment change for-ms.
- The EMAC Description for Assets TS-2-122(A-D) indicates switches are for RCIC steam leak detection. This should be corrected to MAIN steam leak detection consistent with sister switches and surveillance procedure.
This Item has been addressed by submittal of EMPAC equipment change forms.
- The EMPAC Asset Notes page for all of the switches (identified above) specifies a switch selpoint of 190
- 10 DEG F and a switch range of 40 to +200 DEG F. Per Calculation and Inst. List referenced on the EMPAC recDrd, the setpoint should be 185
- 5 DEG F and the range identified is -100 to + 600 DEG F.
This Item has been addressed by submittal of a Notes mark up for equipment record change. Calibration / Surveillance Procedure: (OP 4322 Revision 14)
- Surveillance procedure identifies incorrect As-Found tolerances and LSp values assigned to incorrect tag m bers. (Note: Surveillance update was performd per IRF which is incorrect, see comments under Calculation). 5k-.dL .1 cr" k .. I-,
- The reference section of the surveillance procedure lists VYC-462 as the applicable calculation. This reference should be changed to VYC-462A.
Calculation I Interdepartmental Review: (VYC-462A Revision 0) From the desk of: Mark S. McKinley Vermont Yankee Design Eng. (C) Phone: (802) 258-5735 Fax: (802) 258-5854
vyc- 4G-A -cLL4 - o-4
?"e, 3Z of 4VI J5tjs
- The Interdepartmental Review Form (Attachment 0 to the Calc and included with the commitment) identifies in section 3.1a1.lb an As-Found value of + 11 DEG F. Per the Calc, the correct As-Found Tolerance(CI)tobeappliedis*8DEGF. ? o?7- 4 3L Z. 7-3. A;F ; It s.ICotr-kecfiFA
* &!p 41- 1V-i
- The Interdepartnental Review Fo, section 3.1.a.1.a ioeey identifies the tag numbers with the LSp values to be documented. The correct assgnmxnt of LSp values should be:
TS-2-121A/12lB/121C/l21D 191 DEGF
.TS-2-(122-124XA-D) 187 DEG F
- Various Tag Number discrepancies were identified in the Calc Tables (HPC steam leak detection switch numbers vice MAIN steam leak detection switch munbers).
This Item was addressed (ref ER 99-0462 and DEP-022 memo to Caic rie (VYE 991111)). Cale Is scheduled for revision to correct.
- Calc incorrectly identifies the `A7 switches as being in the steam tunnel (different AL, LSp, etc.) and the '"B, C and D" switches as being outside the steam tunnel The correct location for the subject v'_
switches is the "121" switch .(A through D) are located in the steam tunel The "122, 123 and 124"el switches (A through D) are located outside the steam tunnel. This discrepancy is carried throughout the Calc in the tables, discussions, and equation subscripts. (NOTE: The DEP-022 memo against the Calc has the same discrepancy.)
- Section 4.1.5 identifies the DA term to be d: 8.54. This is a typographical error and should be a 8.45.
(Note: the correct value was used in subsequent calculation steps). rj7,611l Section 4.2 substitutes in the value of 8.54 for the DA term This is a typographical error and should/ be 8.45. The calculated value for e; is correct based on an 8.45 DA term . 1f Note: These last three Calc Items have been discussed with the individual assigned to prepare the revision (1) to VYC462A. Based on these discussions, correction of these items will also be included in the scheduled Cale revision. The Setpoint Database has been updated to reflect the Rev 0 values but assigned to the correct tag numbers as previously Identified. These records will be verified (and updated If necessary) based on the resulting commitment following VYC-462A Revision 1 approval. Based on this, this commitment can be closed. ., From the desk of: Mark S. McKinley Vermont Yankee Design Eng. (C) Phone: (802) 258-5735 Fax: (802) 258-5854
; V. ;
REVIEW CHECKLIST' (ER 961090 01) -4GzA - cc.4 - o l-. 33 l0'E N/A any items not applicable to the calculation or CCN. 41 h~jeto Reguirement Preoarer Reviewer
- 1. Ensure the title page is properly filled out (items that are applicable).
- Calculation or CCN number on cover
- Title reflects subject C Correct QA record status box checked
- Page numbering and count Is correct Cycle number Is included ("NA" if not applicable)
- Initiating document is listed
- SSC l.D. numbers listed
- Vendor calculation and revision number listed
- Vendor safety class P.O. number listed
- Superseded calculations listed
- Keywords assigned
- Computer codes (input/output) listed
- Signatures and dates are included and are in correct chronological order. The title page reviewer and approver dates do not predate other dates in the calculation , 1R 24+
- 2. The following forms are properly filled out and attached (if applicable):
- Review forms VYAPF 0017.04 (Ensure dated signatures form the preparer and reviewer are included and all comments have been addressed)
- Open Item Listing VYAPF 0017.05
- Evaluation of Computer Code Use VYAPF 00i 7.06 MIA
^_ 1-1 Calculation Database Input VYAPF 0017.07 oJ A-
- Calculation Change Notice VYAPF 0017.08
- 3. Ensure review of the calculation can be done without recourse to the -7/
originator. ^m_ 40 WAA
- 4. Screening Evaluation/Safety Evaluation Included. t&/A
- 5. Ensure Individuals responsible for each portion of the calculation are identified when multiple preparers and/or reviewers are used. "JIA Appendix H AP 0017 Rev. 5 Page 1 of 3
V. ; APPENDIX H (Continued) are_. 4 GLA- -r o j
.1 Ca 34 of D Reguirement *Z 1q7 - Preparer Reviewer i
,:v JASd_ S,4 a-
- 6. Ensure that the calculation contains a title page, table of contents, w.r calculation objective,method of solution, design inputs and sources, assumptions, calculation, results, conclusions and references.
- 7. Ensure that each page has a page number, calculation number, revision number and CCN number, if applicable.
- 8. Ensure that every page of every attachment (or Appendix) contains its attachment (or Appendix) number.
- 9. Ensure that the methods for revising and correcting the calculation meet the requirements of App. C of AP 0017.
- 10. Ensure that the legibility requirements of App. D of AP 0017 have been met.
- 11. Ensure that the appropriate design inputs (e.g. QA records) were used and the source of these Inputs are clearly referenced.
- 12. Ensure that the calculation design information, both external and Internal requirements have been met.
- 13. Ensure that If design specifications were used as input to the calculation the performance . characteristics are independently verified* and
- documented. IA
- 14. Ensure that all reviewers' comments have been addressed.
- 15. Ensure that input and modeling uncertainties are explicitly addressed In the calculation. (ER 961090 02) .41A/PA /*h
- 16. Ensure that any restrictions and/or limitations on the use of the calculation are clearly stated. -
- 17. Ensure that computer codes are used in accordance with App. E of AP 001 7.
- 18. Ensure that the applicable input considerations from App. Cto AP 6008 have been incorporated and are explicitly addressed within the calculation.
- 19. Ensure review of 10CFR5O.46 reporting requirements has been documented for analyses which assess conformance to 10CFR50.46.
Appendix H AP 0017 Rev. 5 Page 2 of 3
.; , i APPENDIX H (Continued)
'V'y - 4 (?,A - C-CA- o i "Ph-mic.3a5 c,fW41 Bequirement Preparer Reviewer
- 20. Ensure relevant conditions/limitations have been reviewed fortheireffect ,
on this calculation and the review is noted in the calculation.
/
Alk-- 7--- PREPARER _ REVIEWER Name (print) A ; Name (print) Go so. Organization 4YOtCE ESL V C. Organization qf ex Signature ..
- Signature + .-
Date :tzJta/9 Date ' Appendix H AP 0017 Rev. 5 Page 3 of 3
Page I of I VY CALCULATION REVIEW FORM Calculation Number VYC-462A Revision Number: 0 CCNNumber: 01
Title:
Main Steam Line Areas Hiah Teninerature Setnoint Reviewer Assigned: lbis mirk Mtcn 17 Required Date: 1/29/2000 Comments* =ne1*-BUI~W Resolution
-irunrw TM&J AP-00t7.
-i MoC
_IA QwA. AQOA V
-z 15)00
/ - & -o oo O1.A -'&,A /oo
/ Reviewyqignatur ' Date Calcula'don Preparer (Comments Resolved) Date7 Method of Review: 2/Calculation/Analysis Review 6.t O Alternative Calculation O Qualification Testing B.O.AAo(A QL..-... Q Reviewer Signa'ure (Comments Resolved) Date C'j
- Comnuents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. q4 VYAPF 0017.04 (Sample) AP 0017 Rev. 5 Page 1 of I
Page I of' I VY CALCULATION REVIEW FORM Calculation Number: VYC.-' (oCZA Revision Number: O CCN Nrumber: C) I
Title:
t S Ltw. Ir.s 1 oT t-t $ p^qi+ Reviewer Asilgned: V4iC. Required Date: Ij/U/zgo. Comments* Resolution ____WA
- 4 -
Q2/s/co
- - I '
eC X. JI n - An KI
-/ 0iU C, AY2t/ / 3/
Reviewer Sigifature Date . talculation Preparer (Comments Resolved) 3 ate/ Method of Review: lGdiculatlonIAnalysis Review / / O Alternative Calculation pi {./4 / 3/ Oo -- D O Qualification Testing Reviewhr Signature (Comments Resolved) Wae
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of 3 -P-issues. Questions should be asked of the preparer directly.
VYAPP 0017.04.(Sample) AP 0017 Rev. S Page 1 of I
r. I Page .of' I VY CALCULATION REVIEW FORM Calculation Number: \Yrt-' ` ZAR Revision Number: 0 CCN Number:
Title:
- MS L%;A_
*.1
. . 5&1061 S 4pi'4-I
-3nI.
Reviewer Assigned: lRenale .O e-Vr4 Required Date: I17J2. !tQ Comments* Resolution WO e, -
, ftnature - _ pate Calcdlatin Preparer (Comments Resolved) ate ~'
Method of Review: 1j CCalculation/Analysis Review Alternative Calculation 0 r= Qualification Testing Rosi/leerSignature(C mv Resolved) Me W, Ro~leer igatue Comnments Cornnents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct Interpretation of GA oP; issues. Questions should be asked of the preparer directly. VYAPF 0017.04.(Sample) AP 0017 Rev. S Page I of I
WVCALCULATION REVIEW FORM Calculation Number: VYtC-q (oaR Revision Number: O CCN Number: ) IV
Title:
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. Reviewer Signature Date' Calculati-n Preparer (Comments Resolved) I Dic p.'-
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- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of -IW-Issues. Questions should be asked of the preparer directly, tRin 0.
VYAPF 0017.04.(Sainple) AP 0017 Rev. S Page 1 of I
I Page I of' T VY CALCULATION REVIEW FORM Calculation Number: V'YCC L CDZ R Revision Number: p CCN Number: at. _i 4.
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- Corruents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of I.,
issues. Questions should be asked of the preparer directly. L- aZ VYAPP 0017.04.(Sanple) AP 0017 Rev. S Page I of I
Page I of' I WV CALCULATION REVIEW FORM Calculation Number: VYC q6ZA Revision Number: 0 CCN Number: '0I*> TiTle: - M 5 S N TI t-%44k- tSg6 Reviewer Assigned: NED Required Date. 1 ho &gQSX Comments* Resolution QIA).AVJ A,. I F06 C6'R - do /1A e44iM O/A /3/00 I-Reviewe ignature Wm RJ(A- fWIAa ,/ Calculati Preparer (Comments Resolved) 1L'Date/aaL C,
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- 2,3 Method of R w: I`"alculailon/Analysis Review O Alternative Calculation O Qualification Testing
'UAReviewe t__Signature (Comments Resolved) Date 0
- Comnents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct Interpretation of issues. Questions should be asked of the preparer directly.
VYAPP 0017.04.(Sample) AP 0017 Rev. S Page I of I
ATTACHMENT 5 TO BVY 05-068 CALCULATION NUMBER VYC-462D REVISION 0, HIGH PRESSURE COOLANT INJECTION STEAM LINE AREAS HIGH TEMPERATURE SETPOINT, WITH CALCULATION CHANGE NOTICE CCN-01 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
4 331 'dbvd o3 ORIGINAL: PAGE I of PAGES VYC-462D Am A Ai_ B AtbCr=C 3 AnlatczWD 8 AE 9
- 44~ 3 QARECORD' AdMP MAncwrw 0 30 4
RECORD TYPE NO., Q9,06,004 H
~4I 11 .. YES A_ 17 2
3
*v:0? A}K 'Al!: 2~NO Am~bnx0 AiL 4 Safety Class/P.O. NO. . .t,. ^
1 (if applicable) At N A~P ,'4$JT:03 Az I TOWt PAgeS tLAN P YANKEE NUCLEAR SERVICES DIVISION CALCULATION/ANALYSIS FOR UlfT.T' PRIP-.PiS CA W.ANT ThTTF(0AMN ETFAM TL4T. APF.AS iHM T 1 ESETPOINT
&EPR VERMONT YANKRP. CYCLE , 20 AV49S:OIPLN CALCULATION NUMBER VYCA462D TIIsiC CALCULATION A MAJOERI REWIv FA. 4. .,
U- U U PREPARED BY REVIEWD BY APPROVED BY SUPERSEDES DATE /IDATE - ADATE CALCJREV. NO. ORIGINAL I________ 71i, .,? q/ D D g R-7,-1S
/M-P__-_ YE_
I
-,PI
'.,I IE, Ip . I KEYWORDS 1IPC PCTS. Setpoint. Uncertainty. Steam Tunnel Tholation TFT.R COMPUTER CODES: None EQUIP)TAG Nos.: TS-23-lOlA B. C. De TS-23-102A. R. C. n:
TS-'23-l3A.R C-D-TS-23-104A C D., SYSTEMS: High Pressure Coolant-njrtion ( )CTSystem 23
REFERENCES:
OP 4358: Technical Specifiatn Section 3.214.2.R.. Tahles 3.2.2 & 4.2?2 6 R/sa FORM WE-103-1
* /i^Sr#S .
Revision 4
4,.
- B 7 .
HPCI S1 team T in Areaaro 1Hti Ph Tpmnertatrep Rptf _,V.- int V(c AA4T-DRe
- n V
Table of Contents Page LIST OF TABLES .................................................................................................................... .3................................ LIST OF FIGURES .............................. ........................ ;............................ 3 HISTORY OF REVISION ................ 4A 1.0 PURPOSE .................................................................................................................... 5 1.1 Calculation Objectives ................. 5
.1.2 S /Coponents ................. 5 13 Instrunent Loop Function. ................ 6 2.0 METHODS AND ASSUMPTIONS .................................................................. 7 2.1 riteria ......................... . 8 2.2 I'ssmnptions .to 3.0 INPUTDATA .12 3.1 Process and Loop Data .12 3.2 Environmental Conditions .12 3.3 Switch Data .13 4.0 CALCULATION DETAILS .................................................................................. 13 4.1 Normal Condition Uncertainties ..................... 13 4.2 Test Uncertainty (e) ..................... 17 4.3 Normal Module Uncertainty (eJ ..................... 17 4A Accident Condition Uncertainties ..................... 17 4.5 Setpoint Evaluations .............................................................................................. 19 4.6 Margin Evaluation ............................ ...........................................................
21 4.7 Allowable Value (ITS) ............................................................................................. 24 4.8 Calibration Tolerancess ............................................................................................. 24 5.0 RESULTS/CONCLUSIONS ............................................................................................. 25 5.1 Total Loop Uncertainty ............................................................................................... 25 5.2 Setpoint Evaluation ........................................................................... 25 5.3 Graphic Representation of Setpoint Data ............................ 26 5.4 Calitation Criteria .............................. 27 5.5 Measuring & Test Equipment Requirements ............................ 27 5.6 Recommendations .............................. 2 5.7 VYDEP-1S Criteria ............................. 29 5.8 Evaluation of Existing Setpoint .................... .. 29
6.0 REFERENCES
............ 29 7.0 ATTACHMENTS ............. 31 Page 2 of 31
~.~HCta i~isHgh Temnrhtureg Setoit YC46 Rev.0
-LISTOFTABLES
. 4Z
- ni~itdl~
WeI Sn~inn~~t Data ... .... ...................................... . - -TABLEt 6 TdW Lon-Uncirtatnty Results .. ..................................
.-i ep jt ................ ~2 TA L P6ut ...................................
TABLE B' ab W iAttibuts . ................................................... 27 TAB E 9 RW iix~62ed M&TE. ................................................ 2
' *~FU' JISOF FIGURES O.,.
7' FGRE1-craphk~ Representation of Setpoint (CTS)..........26
.. IU E2 Gr#Nhc Representation of Setoin ................
T...............).....:2 Page 3of 31
j-.
- ry" ;- 9, ' -.' T :. -
a.' HPCI Steam Line Ares High1 Trmnh+re A-UL^,AUML. !Qdnnin 6JI4tL^ffl 1VerA.1T% a 'UL AV. J. n- ^2 U HISTORY OF REVISION Rev. No. Approval Date Reason and Description of Change 0 Initial issue; incorporate plant-specific analyzed drift data and ne wsetpoint methodology, support Improved Technical Specification submittal; VYC-462D Revision 0, supersedes VYC-462, Revision 2, (Calculation subset ADO addresses the loop function of High Pressure Coolant Injection Line HELE3 _ _detection). 2 J'.. P.: Page 4 of 31 M
rj. T4PflI Rftem T wineArease Riah Ternerantwe Setonint vv~rSf)n RPV%A 1.0 PURPOSE 1.1 Calculation Obiectives This calculation is performed in support of tO.: Vermont Yankee Setpoint Program and has the following major objectives:
- t. Document the loop function and the basis for the setpoint and operator decision points associated with that function.
- 2. Determine the normal and total loop uncertainty and verify conrstency with the design basis.
- 3. Calculate the limiting setpoint and operator decision points.
- 4. Evaluate the adeqtacy of the existing setpoint, calibration limits and procedural decision points.
- 5. Provide as-left and as-found tolerances for use in calibration procedures; determine Measuring and Test Eqiipment selection and accurac criteria; document 'rocess correctio'ns, instrument scaling, calibration methods.
- 6. VYDEP-IS requires that applicable opeting procedures, alarm responsea, standard, off-normal and emergency operating procedures be included in the evaluation. This requirement Is accomplished by the inter-disciplinary review which supplements the WE-103 review process and is documented in Attachment 0.
1.2 SvstenJComDonents This calculation applies to the High Pressure Coolant Injection (HPCI)Turbine Steam Line Area's High Energy Line Break (HELB) detection switches in the HPCI System. The specific components to be addressed are: TABLE I Component Identification : ReS TAG Number Location Description MFG Model CWD 6.6. TS-23-IOIA Steam Tunnel Temperature Fenwal 01-170230.090 1449, 1451 6.7, TS-23-102A El. 252' 6" Switch 6.14 TS-23-103A TS-23-104A 6.6, TS-23-IOIB Rx Bldg. El. Temperature. Fenwal 01-170230.090 1449,1451, 6.7, TS-23-102B 213'9" Switch 1456 6.14 TS-23-103B TS-23-104B 6.6, TS23-IOIC Rx Bldg. El. Temperature Fenwal 01-170230-090 1456 6.7, TS-23-102C 213' 9" Switch 6.14 TS-23-103C TS-23-104C ' ' 6.6, TS-23-101D Rx Bldg. El. Temperature Fenwal 01-170230-090 1456 6.7, TS-23-102D 213' 9" Switch 6.14 TS-23-103D HPCI Room TS-23-104D _ Page 5 of 31
VYC-462D. Rev. 0
- PCI Steam Line A&eas High Temoerature Setpoint
.1.3 insumlenLb oonFunction
,; . .13 4borlal Operations
-1r or anticipator:' alarms associated with these channels. ns im utputais o output
.3.1 -' aren norindictotrs atethe setpoint;'th efothese channel have 'nonormn. op io l'-
no
': a cntactihanigeof-statet fincion.
1.3.2 i:Off.NoniUaAccident Oerations located outside of the HPCI turbine steam lines aresujply
,.,.High temperae mthe space in which a eh'of an HC i tine steim line. Isofition
' pIary Imndiate contn ntcould i in'imm'ediate atmaic Slat L (stam line high space i'ierit OR high steamnlow) u-ply Li co's.'i ':ureof the Class A valv swich isia te the HPC' Turbe' Ste:S High temperature in the viciit of the I rine ste lines dted four sets '(offour) of b:ime taic tem.perature. siitches ho thatthev shieldecd P q inent' ad nea tenmpeiatue steam lines toitheuair
&angresensitive but notTethe detect rs a kedor
' Lre the'temer e
,': ted .-,-"--a"' , hot ipn The trip setpoint is set far aaougabove heat from PCIS isolation yet low enough to '
er;x. ct dcria g operat1ics'at nitd power to avoid spurious provide early indication of a steam line break. loop (CM-23-lOSA to D) Associated with each set of detectors is an idditional temperzare
'moitoring the same space (Rcference 6.19.5) and which provides:
Remote temperature indication Alarm on HIGH temperature Alarm on loss of power Figure 73-6.) (Reference FSAR Sections 73A.7.10, 73A.8.10 and FSAR ,- '133' Accident Mitigation (Harsh Environment) From Reference 6.7 and Table 2: (LOCA) harsh environment but are Components will experience a Loss-of-Coolant Accident not required to function, nor be LOCA qualified. are EQ qualified, with an
' For HPCI HELB, components are required to function andWhile a Small Break LOCA operability duration of one hour for auto PCIS actuation. operator action is credited for (SBLOCA) may exceed the one-hour qualified duration,
- SBLOCA detection and manual isolation.
components will either not For other HELBs outside the HPCI Steam Line Areas, the are not required to function for experience a harsh environment or, if in a harsh environment, that scenario. Page 6 of 31
C. . I - IMPT~ AL&AL_J& S mn#tUa-fl T* -m Arstma
*naa_ * .hs ,nw.
Rotr,40n
.S'MJ*4* naCV. ArV & onA_'r ID-w 9
&XULL. uJ TARLE 2 PI) Matrhx Dft, Loop Loton Accident CAT TNI,2 F1,2,3 Duration TS23-lOlA, Vol.41 LOCA 36,22 6 WA 102A,103A, MS-HELB C 36,23 0 N/A 104A HPCI-HEL . A 4,36 1 1 hr.
RCIC-HELB C 36,23 0 N/A RWCU-HELB C 36,23 0 NIA _ HHS-HELB C 36,23 0 N/A TS-23-1OB, Vol.48 LOCA E 36 6 N/A 102B,103B, MS-HELB C 36 0 N/A 104B HPCI-HELE; A .4,36 1 I hr. TS-23-101C, ,RCIC-HELB E 36 0 N/A 102C, 103C, RWCU-HELB C. 36 0 N/A 104C _ HHS-HELB C 36 0 NA TS-23-IOID, Vol. 50 LOCA E 36 6 NWA 102D, 103D, MS-HELB E 36 0 NWA 104D HPCI-HELB A 4,36 1 1 hr. RCIC-HELB E 36 0 W/A RWCU-HELB E 36 0 N/A HHS-HELB E 36 0 NWA 1.3.4 Post-Accident or EOP Functions These channels do not provide any indication or any fiurher function once PCIS isolation actuates when the protected areas reach the trip setpoint. These channels are not identified as post-accident instrumentation in Technical Specification Table 32.6. 1.3.5 A erendix R/Station Blackout Considerations During a station Blackout the Main Steam Tunnel will heat up to approximately 174°F (Reference 620). HPCI is relied on to bring the plant to a cold shutdown condition. To do this, the HPCI high temperature switches located in the steam tunnel cannot be set so low as to cause the HPCI Isolation valves to close unnecessarily. To preclude this, the HPCI line high temperature switches should be set as high as reasonably possible. This is not a safety related function (Reference 6.21). 2.0 METHODS AND ASSUMPTIONS This calculation has been prepared in accordance with the "Vermont Yankee Instrument Uncertainty and Setpoint Design Guide"(Reference 6.1), and WE-103, "Engineering Calculations and Analysis" (Reference 62). Standard methods employed in this calculation are explained in the Design Guide; special techniques and criteria are explained below. The requirements of VYDEP-15 (Reference 6.5) are accomplished through the Interdisciplinary Review process. Page 7 of 31
HPCI Steam Line Areas High Temperature Setooint VYC462D. Rev. ) 2.1 Criteria 2.1.1 Setvoint Class As shown in Table 2, these components are associated with Safety Function 1, -HELB Detection and Isolation." Consequently, per the Design Guide, these components' trip setpoints are Class 1, Nuclear Safety-Related. The switch function in support of Appendix R/Station Blackout is not nuclear safety related. Consequently, per the Design Guide, the need to not inadvertentlv trip in support of a Station Blackout is Class 3. 2.1.2 Scaling Consideraiions Per WC-462, Revision 2, and VYC-1599 (Reference 6.15 and 6.10, respectively), the range of v these switches is (-)100°F to (+)600*F. Therefore, Calibrated Span (CS) is: CS -600-(-)100 1 g 700"F Individual error detrnninants will be calculated to two (2) decinal points, the degree of resolution used for Analyzed Drift (DA) output in VYC-1599. Output values (calibration tolerances, Allowable Value, calculated setpoint) will be resolved to the most conservative whole degree F. Note: The range discussed above is dissimilar to that given in MPAC (Page 6, Screen 1). See Assumption 2.2.5. 2.13 Sinle Side of Interest In order to avoid impacting both the analysis value (module uncertainty e) and plant operating margin (el and since the loop approaches setpomt only in one direction (Le, there is no low tenperature setpoint), a single side of interest factor will be utilized as per Reference 6.1, Appendix F. For a 95% proportion the following "i/K" factor ) will be used: 1.6511.96 .
- 0.85 (Rounded Value)
Note that Q)is applicable only to random terms. Page 8 of 31
HPCI Steam Line Areas High Temiperature Setpoint VYC-462D. Rev. 0 2.1.4 Calibration Effect Considerations Per the Design Guide, CE is typically taken as the sum of the vendor's Rated Accuracy (RA) and the As-Left Calibration Tolerance (CT). Based on the number of samples used to determine DA (count 199 as per WC-1599, Tr'-le 4), a test will be applied to determine if credit can be taken for RA being encompassed by DA. Test methodology is described In detail in Reference 6.13. In essence:
- If DA < [RA2 + CT 2 + vendor's rated drift + MTE V'2 2 then CE- CT
- IfDA 2 [RA 2 + CT + vendor's rated drift' + MTEI " 2, then CE CT + A where:
CT Present Calibration Tolerance DA Analyzed Drift from WC- 599 RA - Vendor's Rated Accuracy MTE the Measuring & Test Equipment used in calibration and where the vendor's rated drift is valued at 0 because the vendor has no published drift specifications. 2.1.5 Sian Convention The sign convention used in the Design Guide is based on the effect of uncertainties on an instrunent (or loop's) output signal. For this type of device, where there is no analog process input/signal output relationship the effect of uncertainties are manifested as a shift in the setpoint away from the ideal value. This results in a sign convention which is the reverse of that which is generically defined In the Design Guide. 2.1.6 Class 3 Assessment This analysis will determine the 95%/95% (single-sided/Section 2.1.3) uncertainty applicable to a Class I setpoint. Appendix R/Station Blackout considerations do not require the same level of rigor and can be evaluated as a Class 3 setpoint (95%175%, single sided). In accordance with the Design Guide, the Class I uncertainty value can be converted to a Clazs 3 uncertainty (e,,). From the design guide (reference 6.1, Appendix F, Table 1), a multiplier is determined as follows: 0.6811.96 - 035 Appendix R/Station Blackout support Is an NNS function. Therefore, accident parameters do not apply. Page 9 of 31
HPCT Steam Line Areas High TemRerature Setgoint VYC-462D. Rev. 0 [ 2.1.7 Justification of Existing Setpoint The existing setpoint is 1850 F. A review of the DA indicates this variable is time dependent. The 1850 F is an acceptable setpoint for some duration after the last calibration. An evaluation justifying the use of 1850 F is provkied as Attachment R.Inputs, assumptions, and conclusions are discussed in Attachment R. 2.2 Assumptions 2.2.1 The error term "Temperature Effect' (CE)is not applicable because temperature is the measured parameter of the device. 2.2.2 The effect on setpoint of harsh environmental conditions caused by LOCAIHELR are negligible (Attachment G&P). These include:
- Setpoint Shift
- Radiation Effect (RE)
- Contact Resistance
- Insulation Resistance (IRE)
- Humidity Effect (HE)
(Reference 6.7.1, Section X-23) 2.2.3 For Custom Technical Specification (CTS) applications, the CTS value is typically assumed based on normal operating conditions. However, in this case during the event for which these switches are credited (HELB) a pressurization may occur (see Section 2.2.6). Consequently, for CIS as well as ITS, this pressurization effect will be accounted for. 22A Per Reference for Improved Technical Specification (ITS) applications, the ITS value is assumed based on the most limiting of HELB with TE and HE or Seismic Effect (SE). 2.2.5 Per the original plant design instrument data sheets (Drawing 225A5600, Sheet 100, these switches were Fenwal 17023-6 (-)100°F to (+)600°F. Per the EQ program, these switches are Patel-Fenwal 01-170230-090, range not specified (QDR 9A, Appendix 11, worksheet). Per the vendor manual (VYEM.0029), these switches are EGS (Product Line Sold) 01-170230-090, no range specified. Per VYC-1599, Table 1,these switches are Fenwal 01-170230.090 (-)100 to (+)600'F. Per MPAC (page 1 and page 6, screen 1)these switches are Fenwal 01-170230-090 (-)400 F to (+)200°F. For the purpose of this calculation, the following is used as input based on approved engineering sources: MFG - Fenwal (QDR 9.4) Model 170230-090 (QDR 9.4) Range - (-)100 to (+)600'F (VYC-I599) Page lOof31
HFCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0 2.2.6 Per Reference 6.7.1, there is a pressure effect of+3eF per 100 psi. Per Reference 6.7.2, the maximum protected area pressure rise is +5.1 psi. Where HELB pressure effect (OPEL) is: PE = (31F/l00 psi) x S.1 psi
+020'F (Conserv lively Rounded) and is manifested as a (+) bias in the nonconservative (relative to safety function) direction.
2.2.7 Per Reference 6.1, the following normal condition uncertainty terms are encompassed in the DA value:
- Measuring & Test Equipment Accuracy (MTE)
- Drift (as a functior of time) (DR) .
- TemperaureEffect (AT20PW)(TE)
- Pressure Effect (PB)
- Humidity Effect (HE)
- Radiation Effect (RE)
- Vibration Effect (non-seismic)
Based on recalibration, the above terms are taken as noncumulative. 22.8 For this type of device, the following normal condition uncertainty terms are not applicable:
- Static pressure effects on span and zero
- Power supply effect 2.2.9 Per Reference 6.1, no uncertainty is credited against the relays controlled by these devices.
2.2.10 Based on the design location of these devices (see FSAR Sections 73A.7.10 and 73.5) the nonconservative affects of Process Meiaurement (PM) are negligible. 2.2.11 Per CTS, the specified calibration interval Is"each refueling outage." Per Reference 6.9, this interval Istypically bounded by 18 months and is taken as limiting (by the refueling event, not calendar days). To allow for a refueling cycle extended to beyond a nominal 18 months, this calculation will base DA on a maximum interval of 775 days, which is considered to be bounding for any refueling outage interval. 2.2.12 Per VCY-1599, Section 5A, the analyzed drift daa for these devices (poold Procedures OP 4358 and OP 4370) indicated little time dependency. The analyzed drift value for Groups Op 4358 and OP 4370 is for 775 days..7This interval significantly bounds the required Technical Specification surveillance interval. Consequently, no further drift extrapolation isconsidered warranted. Page II of 31
HPCI Steam Line Areas Hidh Temperature Setpoint V" S..jTJJ lA f-.V. ^J 3.0 INPUT DATA Data used to calculate loop uncertainties, setpoints and decision points are tabulated below with the applicable reference or basis. 3.1 Process and Loon Data TABLE 3 ProcessJLoop Inputs Reference Description Data f) 6.18,6.22 Analytical Limit I% (outside steam tunnel) 6.7,6.22 200 (inside steam tunnel) 6.4, Table 3.22 Custom Technical Specification Limit - 212 6.6 Existing Calibration Procedure Setpoint 185 *5 6.4, Table 42.2 Calibration Interval Once/Refueling Cycle 6A., Table 42.2 Functional Test Interval i Once/Month 620 Station Blackout Reliability >174 (inside steam tunnel) 3.2 Environmental Conditions TABLE 4 Environmental Input Data _________ Reference____Description.- Data (IF) 6.7.1,6.72 Normal Temperature 140 (MAX)
. (Steam Tunnel is Limiting)
TS-23-1OIA to 104A - Stearn Tunnel El. 252' 6" TS-23-IOIB to 104B - RB Torus West l. 213' 9" TS-23-lOlC to 104C - RB Torus SW El.213'9"
. TS-23-lOlD to 104D - RB HPCI RM EL 213'9" 6.7.1, 6.72 HELB Temperature 300 (Steam Tunnel is Limiting)
TS-23-IOIA to 104A - Steam Tunnel El. 252' 6" TS-23-lOlB to 104r RB Toms West El.213'9" TS-23-lOlCto 104' IBTorusSWEI.213'9" TS-23-lOlD to 104L - RB HPCI RM EL 213' 9" _ 6.7.1 Radiaticn Exposure 40 yearnornal exposure 3.S x I0R (steam tunnel is limiting) 2 yearnornal exposure 1.75 x 10 R Page 12 of 31
HPCi SteaifLtine Afeai High Temneratire Setogint VYC-462D;Rcv. 0 33 .Switch'Dita j ~ TABLES5 Temperature Switch Input Data i.R:fere.-c- .: ~:-* 2 Desclition-. '^: . ;.s- ;Data Sectio22.5 r Range..- -lOOFto600. F Section 212 ' Calibration Span, 700 4 F 68 ,u;tput Sigal ;Contacts close on tem t rise 6.8,Section4 1y31 AccurcyF 671 -- - PressureEffect +3F/1ooPSI 610- - Analyzed Drift - 9.74Fms days: 4 t - ; ,_
., . ;s
* ' ;r-f..S.r" . A.it s 4.0 CALC'JLATION DETAILS 4.1-- No lfCondition Uncertainties 4.1:.1 . -Process Measurement Effects (PM)
From Assumption 2.2.10, PM (thermal stratification) is taken as negligible. PM=0 4.1.2 '.Primarv Element Accuracy (PEA) There is no primary element associated with these channels.
- : .PEA NJA 4.13 Calibration Effect (CE) I Per Reference 6.1, CE typically takes the form:
CE-A+CT where: CE Net calibration effect A = Device rated accuracy
- ' CT = Calibration procedure tolerance Page 13 of31
- =w ; -
- z
'is C WfT:: ;5 5
- l5:
F:-U~ Tnr- r- 4^tn.n UvfNAfpore use n
- kIPCI Steann Line Areas HIIEJI ZJLiIALP1..IA&Ui%' LJ&LJ'J~jxx aI J.0 1XV V. V M &1J.
4.13.1 RatedAccuracv(A) From Reference 6.7.1 (Attachment P) the factory temperature setting tolerance for units that close on temperature rise is the greater of *5F or *3% of setpoint (+6@F for a postulated maximum setpoint of 2001F.) However, the calibration technique described InReference 6.8 (Attachment D) infers an average repeat accuracy of*5tF. For the purpose of this calculation: A -+5.0° 0 F 1.
- i. 4.132 Calibration Tolerance (Cl)
Per Referece 6.1, the basis for CT is the rated accuracy of the device, or *5F. This is also the calibration tolerance presently in use in Reference 6.6 (Attachment E). CTr =.00 0F 4.133 Expected Performance vs. Actual Performance As discussed in Section 2.1.A and where there is no vendor-rated drif:
- If DA < (Al + CT2 + MTElJW (Eq. 1) then CE - CT If DA 2 [A2 +CT 2 +MTE]m (Eq.2) then CE-CT+A Initially:
A - 35.00°F (Section 4.1.3.1) CT-150F MTE = MTEACTUAL (Section 4.IA.2)
=-:4.121F DA =-9.74F (Section 4.1.5)
Thus:
*[A2 + CT2 + MTE 2j12 -e [S.OO2 + 51 + 4.122h1t OF
-8*8.18WF p Equation I is not satisfied, consequently no credit is taken for A being encompassed byDA.
Page 14 of31
HPCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0 4.1.3A CE used in Uncertainty Determination Based on the results of Section 4.1.3.3: CE A + CT e *5.00 + 5.00]jF
-*10.0 0 °F ,
4.1A Measuring & Test Eautlment Accuracy (MTE) From Reference 6.6 (Attachment E), calibration is accomplished with an Omega Digital Thermometer (or equivalent), a Type KThermocouple and a test heater. A review of previous calibrations indicates the typical use of an Omnical 8A digital thermometer (MlE,). From Reference 6.11 (Attachment F), total error for the Omnical 8A is expected to be: MTE, = *1.00S°F From Reference 6.17 (Attachment N), standard limits of error for a Type K T/C (nonspecial) in the application range of 0°F to (+)530°F is. MTE 2 *4F 4.1A.I MTE Reauirernents Per Reference 6.1:
- MTE uncertainty is encompassed by DA
- Total MTE uncertainty shall be S rated accuracy of the device under test.
Given the relationship: MTh *[MTE + MTE1 where: MT -=A(Limiting) MTE2 =*4 (Type K TiC, Limiting) , then it can be seen by inspection that any MTE, with a total accuracy up to and including +3°F satisfies the 1:1 total M1E accuracy criteria. 4.1.A2 Imolemented MTE In support of Section 4.1.3.3 and from Section 4.1.4.1, the following is assumed to be representative of MTE used for calibration: Page 15 of 31
HPCI Steam Line Areas High Temperature Setioint VYC-462D. Rev. 0 MmE I; 1005°F MTTE = l4.00°F Consequently, MTEACU i[1.0052 + 4.0O2 j")F 4 a*4.13'F s 4.1.5 Analyzed Drift (DA) From VYC-1599 (Attachment H), switches calibrated per OP 4358 (the scope ofthis calculation) and OP4370 (RWCU HIELB Detection) met the criteria forpooled datL The output of VYC-1599 (per Section 42)is a 95% probability/95% confidence level value, which meets the criteria of a Class I setpoint as per Reference 6.1. The following data applies to DA:
- Average time interval is 775 days
- DA is
- 9.74°F z
- Data is evenly distributed about zero with a slope on the time dependency line equivalent to
<0.3 % per approximately 2,000 days showing, conseqLently, little time dependency.
- The data is normally distributed with a highly peaked narrow distribution.
- The average drift value for this group is -0.081% CS; since this value is less than 0.1 % CS, bias effects are considered negligible.
Per Assumption 2.2.11 and 22.12 for a DA interval of 775 days, fuirther extrapolation is not considered warranted. 4.1.6 Temrrature Effect IE) Typically, DA accounts for a 20F AT TE during calibration conditions. In this case, TE has the following considerations:
- The measuted process parameter is temperature, for which the device is designed.
- Calibration technique is to preheat the switdi (and associated calibration T/C) and use a prefabricated test heater assembly to minimize any external influences and approximate normal operating conditions prior to temperature ramp-up to setpoint. Consequently, normal TE as an en-or determinant isconsidered to be negligible.
TE 0 4.1.7 Radiation Effect (RE) Per Reference 6.1, normal radiation effect is encompassed by DA. RE-0 Page 16 of 31
HPCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0 4.1.8 Humidity Effect (HE) No humidity effect Isspecified by the vendor. In addition, per Reference 6.1, normal humidity effect is encompassed by DA. HE o 42 Test Uncertainty (e1) From Reference 6.1 for this type of device, and where there are no significant testing condition biases: Initially, 2 + DA 2 Jta e, - (CE O Substituting: e =+[1O.OF 2 + 9.74eF2j 2 4-13.95eF Accounting for a single side of interest approach as per Section 2.13: e, *I[13.9SFx 0.851
'-11.850F _
To facilitate the calibration process, e, is conservatively rounded (with regard to setpoint development) to: e, 1.OOTF P 43 Normal Module Uncertainty (e.) In this case, there are no additional tems to those accounted for in the un-rounded e, il1.850F, conservatively rounded to: e* 1I.901F 4A Accident Condition Uncertainties 4A.1 LOCA Uncertainties (e.,,) Per Reference 6.7.1, these switches do not mitigate a LOCA and, while they may experience a harsh environment, need not function during a LOCA. A LOCA coincident with a HELB is not considered to be a credible scenario. Consequently: eLoCA=N/A Page 17 of 31
HPCI Steam Line Areas High Temnerature Setpoint VYC462D. Rev. 0 4.42 HELB Uncertainties Per Reference 6.7.1 Section X-23 (Attachment P) following both the LOCA/HELB simulation and Humidity/Cycling Test, the specimens (Test Item Nos. 2 and 5) remained within the test acceptance criteria of "6IF. Indeed, the post-accident shifts were of minimum magnitude (+2.29F and -0.2F, respectively). For consc.vatism, this calculation postulates that the pressure effect, discussed in Assumption 2.2.6, is only manifested during the accident condition and would have been unmeasurable during post-accident testing. 4.4.2.1 HELB Temperature Effect (TEn Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCAIHELB simulation. In addition, temperature itself is the measured process parameter for switch actuation. Consequently, for the purpose of trip setpoint uncertainties: 4.422 HELB Humidity Effect (HE..) Per Reference 6.7.1 (Attachment P), the switch ta ip setpoints remained bounded by the test acceptance criteria after LOCA/HELB simulation and numidity/cycling. Consequently: HEa 0o 4.423. Overvrewu Effect (OPsTna Per Reference 6.7.1 (Attachment G), a HELB can result in an area pressure rise. The worst-case pressure increase is (+)5.I psi and results in a (+) bias shift in the setpoint, proportional to the extent of pressurization. From Assumption 22.6: OP, - +0.20TF / 4A.2.4 HELB Module Uncertainties (cm Accounting for uncertainties which are negligible or not applicable: cma= 4 [CE2 + DAI2' + OP=2 Substituting: e,,( 0(lO.00'F2 + 9.7467 2 J" (0.85) + 0.204F
= + 12.07F/-1 1.877 o7 Page 18 of 31
2 >-~*.> - . a:V
- :CI Stean Line Areas High Temperature Setpoint VYC-462D. Rev. 0 4.43 Seismic Module Unceriitv a f ent For HELB mitigation channels, em is determined by HELB conditions of overpressure coincident with, or subsequent to seismic effect. From Reference 6.7.1 (Attachment P),
P-F post-seismic effect ranged from -3.' IF to +42°F. For conservatism, the post-seismic simulation functional acceptance criteria of*5tF is taken as limiting. Initially. SE - 5.00F , Accounting for uncertainties introduced by a seismic event followed by switch actuation caused by a HPCI turbine steam line HELB: 2 [ V2 + DA' + SE J"t + OP Subsituting e- + [1O.00P + 9.74FP+ S.00F]" 2 (0.85) + 0.20°F
, + 12.801F/-12.60°F .
4AA Appendix R/Station Blackout Considerations From Section 2.1.6, a multiplier of 035 is applied to the normal module uncertainty to obtain a Class 3 normal uncertainty (ec). From Section 43, the normal module uncertaity (e,)
- 11.90°F. Applying the 0.35 multiplier
- e,, =
- 1.90F
- 0.3S *:4.165F ,
However, as CT> e-a, the CT value of +50 F will be applied. 4.5 Setnoint Evaluations 4.5.1 Custom Technical Snecification (CTS) LSP = Ts - I nu I However, because AL <'IS, the AL becomes the more limiting condition. Therefore:
, 4.5.1.1 TS-23-lOl.02.103.104 (B.C.D)
LSPKD -AL- ITLUI Where: LSPI 3n,- The Limiting Setpoint TS CTS Table 3.2.2 Trip Setting S 212°F (Not Used) AL 196IF (Table 3) Page 19 of 31
I HPCI Steam Line Areas High Temperature hMgint VYC-462D. Rev. 0
- U - Total Loop Uncertainty which, in this cases reduces to:
.- eCau (+eC, is the worst case vector)
Substituting: LSP,qw 196°F- 12.07'F
- 183.931F, conservatively rounded to:
LSP 1KD - 183°F 4.5.12 TS-23-10l1102.103.104 (A) LSPIA AL- IlTLU Where: LSPIA' The Limiting Setpoint TS CIS Table 3.2.2 Trip Setting
. 212-F (Not Used)
AL 200IF (Table 3) TLU - Total Loop Uncertainty which, in this cases reduces to:
-e LB (+eI is the worst case vector)
Substituting: LSP, = 200° - 12.07'F
- 187.930F, conservatively rounded to:
LSPA- 187°F K 4.5.2 Improved Technical Specification (ITS) LSP 2 AL-ITLUI 4.5.2.1 *TS-23-101.102.103.104 (B.C.D) Where: LSP2,, The Limiting Setpoint AL - The Analytical Limit TLU - Total Loop Uncertainty which, in this case reduces to: em, (+ens is the worst-case vector) Page 20 of 31
HPCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0 Substituting: LSP2KV - 196°F - 12.80F
- 18320r, conservatively rounded to:
LSP2S1 - 183°F ' 4.52.2 TS-23-101.102.103.104 (A'
' here:
LSP2A The Limiting Setpoint AL The Analytical Limit TnU Total Loop Uncertainty which, in this case reduces to: CM (+em is the woist-casc vector) Substituting: LSPm =200°F- 12.80°F 87.20°F, conservatively rounded to: LSP2., 187°F # 4.53 AMoendix RlStation Blackout Considerations The maximum heatup of the Main Steam Tunnel during this scenario is 174eF. The uncerlainty associated with this evaluation (e1 3) is 50F. For this scenario, the LSP3 is: LSP3, 174PF+S°F- 179F LSP3 - 179F - 4.6 Msrein Evaluation 4.6.1 Custom Technical Svecification 4.6.1.1 Nominal Marain (MT to Existing Calibration Setpoint (SP) M,-LSP-SP TS-23-tOI,102.103.104 (B.CD) Substituting: MIBCD 183IF. 185F
--20 F Page21 of 31
HPCI Steam Line Areas High Temnerature Setpoint VYC-462D. Rev. 0 TS-23-101.102,103.104 (A) Substituting: MIA - 187°F- 185°F
- +2°F 4.6.1.2 HELB Safety Marmin M. to Existinp Analytical Limit (AL)
Per Reference 6.18 (Attachment B), the existing AL inside the steam tumnel C(A" switches) is 200°F and outside ("B, C & D" switches) is 196°F and includes a 6°F allowance for instrument error. The existing setpoint from Reference 6.6 is 185°F. The "noirn condition" uncertainty applicable to CTS M2 to existing AL still must consider the HELB OP effect, therefore emu (positive vector) is used. 'hus: M2 - AL - [SP + I eUIJ TS-23-101,102.103.104 (B.C.D) Substituting: M2DwCD 196°F-[185°F+I2.07°F]
-1.07°F .
TS-23-101.102.103.104 (A) Substituting: M2A' 200°F - [185TF +12.07°F]
- +2.93°F 4.6.1.3 HELB/Seismic Safety Margin (M1) to Existing AL From Section 4A.3 ecm (positive vector) is 12.80°F.
TS-2-101.102.103.104 (B.C.D) Consequently: M 3%M" 196°F - 11850 F + 12.80°F]
--1.80°F /
7S-23-101.102.103.104 (A) Consequently: M3A = 200°F - [185-F + 12.80F]
- +2.2°F /.,
Page 22 of 31
HPCI Steam Line Areas Hip-h Temperature Setoint VYC-462D. Rev. 0 4.62 Iimvroved Technical Specifications (ITS) From References 6.18 (Attachment B) and 6.22, the current AL is 196°F for outside the steam tunnel and 200°F inside the steam tunnel. For ITS:
- Since LSP, < SP (existing), the evaluation of nominal margin from ISP to existing SP is not applicable.
- Per Reference 6.16 (Attachment M), the original plant design was for an SP which was 200°F. From a review of plant area temperature trends (Attachment G), maximum base temperature is assumed to be l40°F. Since LSP2 accounts for the combined effects of HELB (as applicable) and seismic effect, no additional safety margin relative to LSP, is required.
4.6.2.1 Improved 7echnical Soecification Oneratinz Margin M.) For an eN of (-)1 .90°F (non-worst case vector), and a maximum base temperature of 140°F (TuAA operating margin is expected to be: TS-23-101.102.103,104 (B.C.D) Substituting: MoCD- [183°F- I - 11.90°Fl]- 140°F
-+31.10F TS-23-101.102.103.104 (Ai Substituting:
M 4 A -[187°F - I -11.90°F l140°F
-+35.10°F i 4.63 Recommended Setmoints 4.63.1 Avoendix R/Station Blackout Margin (Located Inside the Steam Tunnel)
A setpoint of I8SF is proposed for inside the steam tunneL The LSPA is 1790F. The margin is the difference between the two, or 64 F. In addition, the calibration tolerance (CT) of +/-50F will also su.pport the maximum scenario related main steam tunnel beatup temperature of 174°F with I F margin. 4.6.32 Switches Located Outside the Steam Tunnel A setpoint of I 80F is proposed. The LSP2wD is 183CF. Margin is the difference between the two, or +3eF. Page 23 of 31
HPCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0 4.7 Allowable Value (ITS) 4.7.1 LooD Accentance Value (ACV) For a single component loop, the determilation of ACV (the algebraic sum of each component's as-found tolerances) is not applicable. 4.7.2 Allowable Value (AV) From Reference 6.1: 4.72.1 *TS-23-101].02.103.104 (B.C.D) AV LSPm + 4 Substitut~ng: AVw= 11;39F+ 11.000 F
* - '194°F .
4.7.2.2 TS-23-lOl.102,103.104 (A) AV - LSP2A+e, Substituting: AVA- 187°F + 11.00°F
-198°F .
4.8 Calibration Tolerances 4.8.1 As-Left Cibration Tolerance (CT) As developed in Section 4.13:2: CT - +5.00TF 4.82 As-Found Calibration Tolerance (AFT) From Reference 6.1: AFT =e, As developed in section 4.2: e,t' 1.00°F Consequently: AFT L.00F Page 24 of 31
4 - : .-, . '. 1. . - - I... HPCI Steam Line Areas Hieh Ternoeiviture Setpoint VYC-462D-VYC-462D Rev. Rev. 0. A HPCI Steam Line Areas High Temperature Setpoint 5.0 RESULTS/CONCLUSIONS 5.1 Total Loop Uncertaintv Total Loop Uncertainty (TlU) has been evaluated for the HPCI turbine steam line HELB detection switches within the context of both Custom and Improved Technlical Specifications and the results are presented below: TABLE 6 Total Loop Uncertainty Results Cal. Interval I 3-HELB ITS-HELBISEISIMC Refueling Cycle +12.07_F/-1i.rF +12.80F/-12.60 0F 5.2 Setnoint Evaluation For protected areas inside and outside the steam tunnel, results are presented below for the limiting setpoint (LSP), Allowable Value (AV), relevant Margins (Mj and baseline data; TABLE 7Setpoint Results Description Results (0 F)
. crs ITS Analytical Limit (ALA) _ 200 200 Analytical Limit (ALo 196 196 Allowable Value (AVA) N/A 198 Allowable Value (AVecD) N/A 194 Technical Specification Limit (TS) 212 1982 (inside) 1942 (outside)
Existing Setpoint' (SP) 185 N/A Limiting Setpoint (LSPA) . 187 187 Limiting Setpoint (LSPjCD) 183 183 Recommended Setpoint (SPA) . 185 185 Recommended Setpoint (SPBC) 180 180 Appendix R/Station Blackout Maximum Temperatue 174 174 Appendix R/Station Blackout SetpointLSP, .. 179 . 179 (A" switches only) Margin LSP to SP (M,1 ) . +2 N/A Margin BSP to SP (MIUD) -2 N/A Safety Margin to Existing AL(M2A)' +2.93 N/A Safety Margin to Existing AL(M2,)wr -1:07 N/A HELB/SEISMIC Safety Margin to Existing AL(MjA4 . +2.2 N/A 4 HELB/SEISMIC Safety Margin to Existing AL(M,,C) -1.80 . N/A Margin AV to AL N/A. +2 ITS Operating Margin (MW3 N/A +35.1 ITS Operating Margin (MacDY N/A +31.1 Page 2S of 31
HPCI Steam Line Areas High Temperature Setpoint VYC-462D. Rev. 0
- 1. Per OP 4358 Revision 12
- 2. For ITS the AV is the TS Limit
- 3. From (SP + ej) to AL
- 4. From (SP + %,wss,, to AL S. From (SP, - C.) to maximun normal temperature 5.2.1 TS-23-101.102.103.104 (B.C.D) -Outside Steam Tunnel From the above table it can be seen that to support ITS and the current AL of 196°F a setpoint reduction to 183°F is required. A setpoint of 180°F is recommended.
Further, while the existing SP of i 85F supports the CTS limit of S2 12°F (including both ema and qmzw== uncertainties), the existing SP does not support an AL of 196°F for any of the applicable uncertainty scenarios. A credited AL less than the Technical Specification Limit is a design input paradox, the resolution of which is outside the scope offthiscalculation. : 52.2 TS-23-l0l.102.103.104 (A)- Switches Inside the Steam Tunnel lhe existing 1S1Fsetpoint is acceptable for both the EQ Program linit of200°F, the Technical Specification limit of 2t2°F, and the Appendix R/Station Blackout temperature limit of 1741F. 5.3 Grnphic Representation of Setpoint Data FIGURE I
*Graphic Representation of Setpoint (CTS)
Technical Specification - - 212°F Analytical Limit (inside steam tunnel) 200OF Analytical Limit (outside steam tunnel) - 196°F LSPIA - 87F SP2 & SPA C(A- is retained) 185°F LSP - 183°F Recommended Setpoint (SPa) - 180°F LSP 3 179°F SBO Main Steam Tunnel Heatup 174°F Normal (MAX) -steam tunnel 140°F
- 1. Calculated for normal conditions (to include OPE)
- 2. Existing setpoint per OP 4358, Revision 12
- 3. Not to scale, provides relative position only Page 26 of 31
XYvr<t'%Ar D'A.. n HPCI Steam Line Areas High Temrerature Setpoint , IXv. V FIGURE 2 Graphic Representation of Setpolnt (1) Analytcal Lfnit (inside steam tunnel) - 200°F Analytical Limit (outside steam tunnel) - 196°F Allowable Value' (AVA) - 198°F AUowable Value' (AVana) - 194°F LSPA 18PF SP & SPA ("A' is retained) 18S°F LSPa 183°F Recotnmended Setpoint(SP,) . 180°F LSP3 179°F SBO Main Steam Tunnel Heatup 174OF Normal (MAX) - steam tunnel ; 140'F
- 1. For ITS, the Allowable Value is the ITS value.
- 2. The existing SP per OP 4358 does not support the ITS uncertainty with Reduced Analytical Limit.
- 3. Not to scaie; provides relative position only.
5A Calibration Criteria In order to support and implement the results of this calculation, the temperature switches are to be calibrated according to the following table: TABLE 8 Calibration Attributes Description Value Units Setpoint (CTS) Inside steam tunnel 185 'OF Outside steam tunnel ISO 'F Setpoint (ITS) Inside steam tunnel 185 OF Outside stearn tunnel ISO OF As-Left Tolerance 5F As-Found Tolerance *11 OF. 5.5 MeasurinyJ& Test Eauioment Requirements Testing is accomplished with the following equipment:
- Monitoring thermocouple (Type K) (Installed)
- T/C Reader (Digital Thermometer)
- Heat source (rest Hiater)
- Digital Multimeter
- Variac Page 27 of 31
HPCI Steam Line Areas Hih TeMnerature SE 6int VYC-462D. Rev. 0 For calculation purposes, only the T/C and Reader have relevant associated uncertainties, developed Indetail in Section 4.1.A. Since the TIC is an installed sensor calculation recommended MTE reduces to the TIC Reader. TABLE 9 Recommended M&TE Description Required Accuracy Actusl Accuracy Reference Omega Omnical 4A & BA _3F *I.005F 6.11 Omega CLSOSA :3°F iL .005"F 6.11 5.6 Recommendations 5.6.1 Subsequent to this calculation's approval, revise FSAR Table 73 2 as per Attachment K. 5.62 In order to support Analytical Limits of 200°F an - 196°F, revise OP 4358 in accordance with Table 8 and Table 9. 5.63 Ensure that a calibration tracking system exists to evaluate consequences of a calibration interval greater than 775 days. [Note Ther are no plans to extend the calibration interval beyond 775-days] S.6. Add VYC-462D to the List of References in OP-43S8. 5.6.5 Evaluate the acceptability of an analysis limit that is less than the Technical Specification Limit for an increasing trip setpoint. 5.6.6 Revise Section 7.5.5, "Small Leaki in the Reactor Building," of the EQ manual (paragraph S) which indicates 200F as the isolation trip setting. This should be the nominal setpoint of 1961F as implemented by the HEL3 analysis. The 200IF applies to the steam tunnel only. 5.6.7 Revise the minor FSAR Figure 7.3-Sb discncy regardiig HPCIRCIC temperature switch sets. The following discussion relates to HPCI; RCIC is comparible. There are four sets of four sensors, each set providing HELD detection protection to specific plant areas (one set covers the steam tunnel and three sets cover various zones of the Reactor Building.) This is shown in block diagram form in FSAR Figure 73-Sb. The block diagram section regarding the Reactor Building senior sets refers parenthetically to "typical of four located outside steam tunnel." This should be "typical of three..," 5.6.8 Per MPAC (page 1and page 6, screen 1) these swatches are Fenwal 01-170230-090 (-)40'F.to (+)200°F. Per VYC-1599;Table 1, these switches are Fenwal 01-170230-090 (-)100 to (+)6000F. MPAC needs to be corrected to show a range of (-)100 to (+)600°F. : Page 28 of 31
H.P(rT I.tetnm J~ina Areas 1Miah Temperature Setnoint VVPt A#;1)n Io- nJ 5.7 WVDEP-15 Criteria VYDEP-IS requires the impact to plant programs, procedures and licensing and design documents are cosidered. This calculation has een reviewed for impact considerations. To fully satisfy VYDEP-15 requirements, this calculation undergoes a review of all departments and programs that could be Impacted by the results and conclusions.
'Me following has been considered and Iseither addressed in this analysis or via the interdepartmental review process:
- FSARchanges
- Technical Specifications (custom and improved Technical Specifications)
- Procedues'
- Technical programs
- prints
- Related Design Basis Calculations (input/output)
- Design Basis Documents Based on the above, all impact considerations of VYDEP-I S are addressed.
5.8 Evaluation of Existing Setnoint The temperature switches located in the steam tunnel are acceptable for the full surveillance interval with a sepoint of I 85F. However, the temperature switches located outside the steam tunnel require a setpoint change to satisfy the full surveillance interval. Attachment R evaluates operation of the switches located outside the steam tunnel with the existing setpoint of 185'F. The time dependency natwre of the DA variable allows operation with the 185°F setpoint until March 14, 1999 without challenging the AL of 196F or the CTS limit of 2121F.
6.0 REFERENCES
6.1 "Instrument Uncertainty and Setpoint Design Guide," Vermont Yankee, Revision 0. 6.2 WE-103, "Engineering Calculations and Analyses," Revision 17. 63 Vermont Yankee Final Safety Analysis Report. Section 73A. 6A Vermont Yankee Technical Specifications, through Amendment IS0. 6.5 Vermont Yankee Project Procedure VYDEP-15, "Calculations," Revision 2. 6.6 OP 4358, -HPCI Steam and Space High Temperature Functional/Calibration Test," Revision 12. 6.7 Vermont Yankee Environmental Qualification Program Manual, Revision 36. 6.7.1 QDR 9A, Revision 10. 6.7.2 EQDI 95-55, "Draft EQ Manual Revision." 6.8 VYEM 0029, "Instructions for Patel Temperature Switches," Revision 0. Page 29 of 31
HPCI Steam Line Areas High Temperature Setnoint VYC-462D1. Rev. 0 6.9 "Selected Definitions and Clarifications Associated with the Vermont Yankee Technical Specification." 6.10 WC-1599, "Drift Calculation for Fenwal Temp SW Models 01-170020-090 and 01-170230-090," Revision 1. 6.11 WC-1758, "Measuring and Test Equipment Uncertainties Calculation," Revision 0. 6.12 Memo, Hengerle to File, "Improved Setpoint Programg S vs ITS Setpoint Evaluation," WI 37/97, dated April 25, 1997. 6.13 Memo, Hengerle to Distrbution, "Application of CT, CE and A for Single Point Devices," VYI 92J97, Revision 1,dated June 26, 1998. 6.14 MPAC. 6.15 VYC-462, "Fenwall (sic) TemperanJre Switch Loop Accuracy Review," Revision 2. 6.16 -Instrument Data Sheets," GE Drawing 225A5600, Sheet 100, RcIvision 9. 6.17 "Nuclear Power Reactor Instrumentation Systems Handbook," Volume I, Joseph Harer and James Beckerlyj. 6.18 NED Analysis Matrix, dated January 21, 1998. 6.19 Plant Drawings: 6.19.1 Flow Diagram, High Pressure Coolant Injectioa, G-191169, Sh 1,Revision 38. 6.19.2 CWD-1449, "HPCI Logic System," Revision 7. 6.19.3 CWD-1451, -HPCI Logic Sys-tem," Revision 23. 6.19.4 CWD-1456, "HPCI Logic System," Revision 2. 6.19.5 CWD-749, 'Steam Leak Detecion System," Revision 7. 6.20 WC-l 347 Revision 0, "Main Steam Tunnel Heatup Calculaion" 6.21 Safety Class Worksheet [for HPCI temperature switches dated 9-29-98; 622 Memo VYE 98n114, G.1. Hengerle/E. Goodwin to R.T. Vibert, "Assessment of VYC-462A,C & D Temperature Limits", October 5, 1998. Page 30 of 31
. .. . - .1. -..
Lk Retwcint VitYC*462D. Rev. O Temnneraftue
.' H}PCI Steam ILine Areas1higlh
> .. .' ': '7.0 ';.AlTACHMENT . . Loop Block Diagram
,.Attachiernt, AttachtxentB, NED Analysis Matr* Excarpt .,
Attachmentit, MPAC Data Excerpt, .. Attaient D, Vendor Data,'VYEM 0029 Excerpt Atti hteit E, Calbation Data, OP 4358 xbcerpt. Attahiient F, MTE Accuracics
- ViG758 Excerpt S ! _
Atii& nt 0,cEQ Manual and QDR ExcerptS99 Exceipt t H. Anald Drift Dita, VYC-1 i;AtU~ . .-
'Ata CTS Diaa ' . , .
,. ;; . ^AtenitJ, PSAR Data
-.t i,:K, FSARTable 7.32 Proed Markup . . .; ' . ' -'
92/97 W Project Memornid&m VYI 37/97 and WI
' c'Ah '..
.':taci N, GE 1nstrur~ent Oata Sli ; .
K-.T' es, Rcfrene7xp;
- '~ ~ ~~~ia6"
'::u .-- .yp:'Attyc/Ccus Reiews. .
WVE-i03 Review Sheits"and Associated Iedisciplinazy Atihioeit, .
- Atnt-,Ad"itPAlQDR"at .
Attacht Q.Teklon
.-.. Record wiiVYEtC. . .
EAtachrent, Asscsmcnt ofExisting Sepoint dated 9-29-98 Memo VYE 98/214 and Safcty Class Worksheet IMiiiueoiiS.
'A - . .
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by _TS Wewmn.o I*L b*ION wc.¶ma ,gv. 0 5.ne. JohTOm paScebftra PA7. Rat 121 51.10. I PtA S.RA M 21 au4 I I r3g145 CT 53 PIP45 Of 5 rt I.: *
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Lr, YMQA7McaW=OOMV CM~ bm 0VroC4; I I TO.. .1 FR.Mb kheisLewh RL. WC-I 99 Rcv. 0 (Ddft CakW~gom r Forwal Tanpactxuz Swkdacs Iugm Mad017402020M) DA71: Segeba S. 1997 VYC-599 Was reiewd to ddet the kzpat afth aon-onsavaim mehod used to dmd ouln fm to sample pooks) e ch anges am as foflows L a pV 12f2g 2l k e bhed of Ow cdkadW htddial =Wl sm b TAlek 3 -
- 2. a s 15E e A t c a al ~ t e O- 3 3a - t d sta on the ertss TMe Imug do no affect thb~ oe of tealo aheoc dw o the da~te woinod mg wkh data fm OP-?70InAftag4. Th e com~nacOfOP-0S8 and 4370
_Nde ISO pfi that kept the odsa riw teat OfAftadmot4 owvde The dmwd Aa 2ofVYC-1599 Aww.rt saantewmioothe an ahndrog. VYC- uwd as ft ft-m hadoc b fior th I=s of C ow xR lahe ddftcladtio tmmveiflctin of the out~iar lck thcre ofui aed the n eedto r- b CC. George Jlcgeuce mc
@"] W4?N rfa"Oi
WaEAroumcaEmc1Ro ~uw
- ~-I .
MMO1 .W OdMcabkuton RrFoFwi TomPwaba. Swlh Mcdl s 01-170020(230) vyc-1599 Rev. NAAPM V. Reason a DescmpMoaI of Change msa.3 . serd Ad stoa oxa fwn Ii. sams pooIksa The doig 1;~.diTa*e S.CId t skfort-Te pa 12(20 bh wbody 2 Room pqe1. S. 7& ft o reod e OP-43 2to to-
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OLUTNW, Y-4;Z. Aev, Drft Cada5on For Fewat Tpenam SaChes Models 01-170020(230) Vc1-599 2.4.7 Ouller tlts were perfoomed on the data until either S% of the oinal sanpl wasen*W
- no other outliers were detecedi
..Tabl3 Crditc Values Fr t-Test 4 S - - t - -
3 43 4 42
-l_,- --
Ui - U_ J L.. __ _ __ _ _ 28 __ __ _ __ __ _ ,t 4 0 2A Pooling the Ddit Data Note: Refer to the VemAont Yankee Insument Drift Analysis Design Gue for method&M used h Ihis section IRe. U) 2.4.1 The SndaWd detion and variances of thes rious suboups were evhuatd to determin lie dats suftabift for c arri* Mng 24.2 The model rmbeea. spars and seolo3 isded hITable I (Eqipment &mlnary) were evaluated to determne the suitablty for 2.4.3 A v I-Tt aspig unequa variances was peformed on all potential Wrupns using le *o oin equation InMcrosoft Exo*k tM 3 Yftdn; IRot. S.1 &0l r *tmistatsf n -Tal mxberof datdpaps. v- k of M sano h A4 '-Hy~ ed mea diffamce. 2.4.3.1 The tes performs a twonample student'6 test which assunes lst the vriances of both rags of data are unequW nd Isreferd to as a heteroscedasc-test This I-est Is used to'dotermine whether two sajle meas are equal d when the grus under study ae distinct. Peg. IZef 20 Yarimo Nudest Suwloes YakNuer8ms Pp12 of 20
1::.? . I . ..-- 1 V CVIAvAIoN b cMVAN-8CO U uA-u.pI 4
.7.1 aUrl Is OIMUL ?AO! I OF..2L PACES 7.Z 7Y 60 7 Itc 1: PAGS I Ci'r- PA=S 9
FAGM II (W_ raw OF-. PAGS WAO Q 74 a2g? -F*t- 0 evlqs lof rah24 A . . . lrOM nwO~rP .. L ... i._ _ NO W.O.IP.MM NO.z" YAn _UMKStV3MSVrnON , CA M-TIWtQALY=SFCR D~ T~AfIITW ml ,)WA!~mwfWMnpRFlJfO.§b1172& fAT= ml& VP_ V _ iNrYAU. tv=~ 2e'jq H - *' a.- CUtLA" ONUM - v Tt - And miU AftVA I ulmn. OfSWNDOCL Ms i n a g e7O
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I I --, I .. WM~FAT1DcM1TCaC1R&M OWAuwuuwkVuk- 4 UP Difi OMAio For F&nWa Twaperabna $*Wfth MWOU~l 01-170020(230) wYC-lsg ICA4.CULATION COJECWJES This cacuaiaon documech f drie*ft analysis perfrmed an the Fenwal TeqIPWakf,r Switche at Vrmxnt Yankee f or StemCow Leak Detection System cOf i Mobk. Etesm Lines HPCI 66parn Uwes RC1 Steam Unes and M%, Am&Ls WL.cabtiafln has been devetlpdinpport of DieVermnt Yarke Irnpirovd Tedinica S06dfflcdon Projct with Die following major olWjecve
- Determnae Die drift dhafraeisfic forDdFew ulW Model 0141?D04=09 &
014M7030-.0 Ilemerture uwwche Isted inTable 1(Equlpmdn Sunnw.
*Documnent live analyses pierformed on the componefts Inaccordance wfth the 'Vermont Yankee fratrument Drift Analysi Design Guide." J PURILI6.
4 Rovio the standard deviation, vaiance 95VA5% Tolerance Interval Factors CMIP for-Die device groups covered.
- Evaluate, the data for womiefty. Ome dependency and provide the 95%W9%
Aralyzed Drift Term,(ADM) for Die components coveed Inthi calcuation. 1.1 System & Components lids calculaotio applies to Die Main Stearn Uine, HPCI Steam Line. RC1 Shemn Lin =ad MVWJ Spac dstem leak detecton tnefseratre sftchem Th peil -on.wonnaddresed arsDsted beow in Die quomen manmuy Wteef nug P"WwPK IAN so -KWW Dw"ITI
,uI Wia23 742 a ItwWIc W IM*&%Om I DC t8*03S4*OlSn STD Peg. 401 20 Vaise Yaf#" N&adwServIo Nudew services Pop 4 of 20
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D1cdc pe ~r6 Swfde Models 01-170020C0) VYC-1599 1222 The o h o d by OP-4W moitor the HPCI
.bO*n L f ht enmutuec edbydsona ea (snlj~owki F kIen High temperatre hI the HPCI Steam LimeAmaws'poyks i automatlo bolailon signal to the HMC Steam lienIolsfonah.
123 The o swthewer byOP4 monrhe RCIC lewerat t Seam Li. *A ft ohten~amturecaused by-tem bake ( WF H tenithn Hiwssig). mgh linOe RCIC Own he poies an autma Isolatio signal to hom RCIC Slon 12-4 The switches covered by OP-43rmontor the RWOU J Steam L eas for hgh lemperature caused by steam lebaf (S 12(rF I Derag). High kempemrtu Inthe RWOU Steamn Ine reas proides an automatic Isolation Ognal to the RWCU Steam UWe b6laon Valves. 1.3 GovernIng Proeedurej And Programs 1..1 VennontYankee laftmentDfOt Aalsis Design Gulde, Rev. 0. gPw6.l 1.S2 VermontYankee utrument Uncertainty nd Setpoints Design Guide. Rev. 0. 5.3A 1.3.3 yanke Nudea Savlce Enineeft butucton WE-103. Rev. 15. AnM mid ulIuon VW" 13.4 VamoriYarime Er7ineh Ig Poedure,.AP4017, Rev. 4, CWisaflon ond An.lses. Pact 1.3 Yanm Nudor Serkves Engneedrng sc WE- 08, Rev. S, Comp-eCodes ,E 2 MEIM OD OF SOUTION Thi calculation has bowprped Inaccordance wfth the Govenfng Proedus and Programs Isted Instep 1.3. Standard methods enloyed Inthis caction ae emplined Inthe Vermort Yankee Insrument DritAnalysis Design Guideo an overview of to methodology b eOlained below. RW6.13 21 Data Enrdy and Dtunnrnafton of Drift VYlues 2.1.1 Catwatlon data was collected from the appicable Su&veMance Test br the comporet a sed InTable I (Equpment Surrmay). 2.12 The data was thn entered into Microsoft Excl Sp _adsheets ted aft the STuveanoe Test (e.g. OP4322.S) noting any dscrpande found with the data (e.g. As Found out of tolerance. legb d etc.). - I ml) Y8MNUDeSAo Page 6oe 20
J9 OMf Cakubtlon For Fenwial Temperatta Swildies Ucdels 01.170020(230) WYC.1S99 4.1.2 A ch~aing selpohitwas madein OP.4370 betweenl97-1989 an 4.2 StittcsClclfln 2i Mm sbatsfti calculalon for each swvelfluc test ad the group)ed 4.. opnrsIs dociminted InAtadinients 2 and 4. ML2 £41 4.2.2 The TIF wed Iithb anauyssis fa MM% lee of con:dence and IsIsted InTabl 4 (Stastical Simunry) for each suvelance tedtandVie groupe data> 42.5 The Analyzed DrMf Wmlu Issted InTable 4(Staftfsical Summary) for each aunmlltane test and the grouped data. 4.2. The sttitcssnanar for each surveillance es and tMhe to grouping can be found InTable 4 (Staftescal Srmimary) and at tae beginhlng f Aftacments 2 and 4. M~.2£ 43 4.3 Plots 4.3.1 The XY scatter plots. Regression Ens itgasand Probabffty
*plots swefor doekten i fthcharatm sisoft.data we coctaired InAttacment 5 for Group OP-4= &68 and Attacmet 6 forGaou0OPMM5&70 A 56 4.3.2 The plot tatistic am locatd at goe end of the plot grop in Afadhmb 5 a.63 .
3o 5 RMMUTS 4 ANDT~ CONCLUSIONS w8b~. 54 Groupings 5.1.1 Refer to Table 4 (Statistical umimany) for the suninary of fth statiestia analysis for each svell~ane and Vie reutaifg U.roupings 5.12 The daeta rom OP-432 and OP-4M6 was able to be Pooled into one group due to the conwonents passtIng te -Tedt pemrfredji ftep 2.4.3. haftn fte same ranges. sbrdlar mode numbems sane NWanOSsen*alequal standad deviatons and variances. efrto Table I(EQu~rnent Surmmar)for conwnen nfomiaton and Table 4 (Sftatscal Summary for staftistca Infrmaion . M31 5.12.1 The pooe data provides a gic.p pf 20 swle point wfth a stada 4d1eVItion Of 0.0i 6i sa Wth an average tm Inteval of 544 days Ms dbscXse InSection 3 of fth calculation a95%105%- TIP YM be applied to the standard devaio th r groupWch equate toanAD1termof 17 of spar(7.640). Reerto Tble4(Sttistcal Page 170(20 Ys ?&rdmwSauloss yawmmrderebu P~o 1T CC 20
"=RTO V~--f Dsif Calesualon For Fowewl Tempurautra Sv~tdm eaUl~s 01.170020(20 WYC-.1599 5.1.3 The dafta *m OP-43A8 and OP-4370 was able to be pooled kint one group due Ile the corrponefts passing the 11-Tet perfxnied Instep 2A.%4 hvigthe ft swne mriges same model eumberasriuffar i toferTebbleI (qtM*ment S rwnafor conionent anoraton and T*W 2 (SWaIlstical Summawy for statistical fnwfrmtLon M 3) 5.1.3. The pooled data provides a amop of 199 sarnple points With a standard deviation of 0.648% of span with an average Omni Irdirval of7M5days. As dbscu~d InSection 3ofvgs c~cualon a MAS%l't Fwil vLie pplied to the Standlard deviamo fortDo group which equates to cii ADR torm of 1.9% of span (9.74*F). Refer toTable 4 (Statistical 5.2 Time Dependency 5.2.1 Group OP.4=2 and OP.4368 As seew ftrOmteXY Scatter plots, Regression lines and Regression staisris Aftachrnent 6 I can be concluded that the date Ibeverily distrbzed about zer vifi a sdope on the Gmn dependency gmi equealttto c 02 %I -SW days. 5
.22 Group OP.43 ad OP.4:
As see ftin the XY Scatte plots, Regression Ome and Regression slaft Icsn Adftacuien 6Itcm be concxde that the daba Isevenl disrbuted aboit zmm wbt aeloe on the gmn dependency he eq~ivalestto cO0.3 %1-2DDOdays.Me 5.3 Norma*~t 5.3.1 Group OP-4S2 and OP-438 As seen from the Probabhit plots, Probability statistics and Histogramn InAfttchmnent SIt can be concluded tha the data Isnoffna!1y
..2distributed wfth ahighly peaked narrow distribuftiorn.IL5 5.2Group OP.4=5 and OP.4370 As seen from the Probabilitty plots, Probablity statistcs and lfistogrmm in Afttachnent ClItean be corcluded that the data Isnorrmally distributed wfth a hIgh'Jy peaked naro distribution. lAB. 6J Page toOl 20 Yak NudsmSaridosa Ywima Wee 6vo po la of 2
- -.' - . 1. .i .. ` 1, - -
VMKEV"Gca Drit Cmlaion ForFonW TewpwtL Swtches Modes 01-170020(3 VYC.1S99 SA Summazy Mhe date wftakied iswt adbdmV NWe Gomtdepeneny
- and Isaoccepbbab for use In SeOtokdtlkncrtaity cakculat~onr Mm 95'tS% ADA' V , . ...
5A. GGotqp OP422 nd OP.48M 1.0 of Span (7.64f. 5A2 Gcmup OP-4358 ed OP4 = 1391% of Span (974E). I AME A gfts umX v-T- A L 4. tzl- s ~c- m ma-um - d - 7"-"& ID 8810 ts 44 4X 2X m-W3 ~ 4334%. .04 3%W %* I7 .0*23 A W1% *3U% 4.AIgOA aW-U U CMI%.S0 0*AI
- 1 %UZ u 0* w04 MH% 3.* UM3% UW %
eJ1 LAMS W73 sLM Sf Li" 4a.S ala ass. 'un out '*n38 .0' U M31 . Sim M@% U7116 tLS & L.a 4AN :4 4A.W 4A4O iN * *634i.l 2.31
- .6341 2.341 2 _*
2.643 244 U-*Z % sic3 7 2.1 4 131%S u113i SD-s - - - - # -- W Yw e u wS et OU n P I0# 10; am t n20 Yo wNUrtordo t40 III d 20
XT"c XY Scatter - Fenwal TeMperatUre Switch Group 0P4358 & 70 I I-%OS A1 I _ Of 400 hDon-qa YEkINTUsmAi lo I of IS
I I I A16Anai XX Scatter (Absolut Vda! Lc)- Feawa TeMpeRUre SwUc Group OP4358 & 70 2.5005 9 ag4 s4 2S.000 4 0 4 4 *L D 1 I C S*. . Ht . . I 4 0 500 1500 200 "Wavw YENTIAv~ AP 2 E Is
= 0)&7 caFtFcLata)
Modaa 01-1700r0D3 -159 DRe Ammm=4 Rtgreulau LUm (Raw Data) - Fenwal Temperature SwItch Group O1'4358 & 70 1oos0 9 *' SD"
.*I
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Dt A"ac Fst=mlwTs0 Modd *159 AbkOm V -=akO 0Goup O4351 &O70 A6g=6 Regressio Lne (AbsoUte Value) - Feawal Temperature Switch Group 0P4358 & 70 2M% 0% 2.0% .+ I _%wkDsv"v I It *
;.1.5m00%
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.t 0.500* + p0 I II 4 I. 41 0.0AD% I 0 Lim0 2000 2500 Yen New 5aIks PENESn Ap 4 of 15
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-0
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Ic hoabUMQoqOP Da'. - 3& 70
.Normalized Probabilty Plot - Feziwal TemponuW= Switch Group 0P4358 & 70 I
- 0J&S 1.-M IMA 2.a%
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ZDA .aPft PUANITS Mcddc01.17CWOC23090 .1s9 IWaV.7QWOMUA70 AM6 Est-onram - FeAMnl Temperature Switch Group OP4358 &70 so 70-60 soI I40, I _ 30
.3.5OO A=% 4B% By% 0100% 1=% 1=0 2 mm Y EW=NkAWSavi= p7015
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AITACHMENT 0 VYC-462D REV 0 PAGE 1 OF 5 CALCULATION/ANALYSIS REVIEW CALCULATION NO. VYC462D REVISION NO. 0 COMMENTS RESOLUTION WE403. meuakw
- C A./E7_77c,b,,e4t_4,,nrv7i' ________________________
I oAkwfati cakuQBmd mdhod oQoafifimnteiog, C wcaub C~cdtzd an Page: A/d Dam FORM W4F103-3 Revigto S I
VERMONT YANKEE SETPOINT CONTROL PROGRAM INIERDEPARTMENTAL REVIEW OF CALCULAMON: VYC-462D Revision 0 VYC- 462D ReviswoqO has been prepared and independently reviewed. The Departments inpacted by this calcuwation are requested to review the results of this calcahtioa, concur with the results and/or recommendations, and document the departenatws acceptance prior to the calculation being approved. I. Summar. Thiscalculationevaluatestheuncertainty &setpointfor HPC) Steam Line High Temperatwe
- 2. Calctfiion Onen Items, AP-0028 to he Assixned
- 21. N~one-
-3. - contact tSetpoint irogram Manager (G. Heneerle) if not in agt wh the 3 coo ctuoi stacw nts. . 3.1. VermontYankieE&C 3.1.a. FocedureOP-4358Revision 12 will requirethe following (based onsCwtor TechnialSpec Zcatiom
/ssand siirveillance cycle):
- 1. Add the following Inthe procedure discussion:
- a. LimitingSetpoint: ;' .
7&23-1OLe-DIJ02A-D/IO340-D/1O01D 183 OF 3 0 , 714aL& /OV-9
- b. As Found values:
-S-23-10A-D1/102A-D/103A-D/104A-D +I °F
- c. Revise Head to reflect: ,
- d. Insert the following M&TE requirements:
Omega Omnical 4A, 8A, or CL-505A, or T/C reader
- 2. In the body of the procedure and the data sheet revise as follows:
- a. CAlibration Tolerance From To 7S-23-1O1A-D/102A-D/)03A-D/104A-D +/-1eF +/- F
- b. Trip Setpoint 3 From To 7SM23-011-D/1O2-D/13/-D/J043-D 185F 180 F r7 '-23 -,t'* mWe4 /09V
- c. Revise calbation data to reflect head correction of: ' -
VM w~m _M 0+. MO PAG 2.- cv 3 Page ., of _
- I .. _' r: . I I-cYAN eU'a BWRWMN MMS Vermont Yankee Setpoint Control Program Interdcpartnctal Review of Calculation VYC- 462D Revision 0
£3>
- d. Insert a 9-point calibration for all analog instruments: NA ATFa tw Jg Thmsmiftcr Rcs dicmo Square Rot Convrtr Otr f ~quoment ID) fL4u0d ID] [Equip-at D] 0 tID]
Eq ID] ou O"1 -ne IDpUt Output t Output - Output 25% mA 75% mA IOMA mA 3.1.b. The following commnentsrecomnnendations apply:
- 1. Incorporateabove changes. 0 Sign& Date . . e . //
Vernft YinlceePC RepresenstatM76-3.2. Vermont Yankee Reactor Engineering Concur 3:2.a None-. Sigp& DatO5__ k .Z-AI /W-Al,4 Vermont Yankee RE Representative 3.3. Vermont Yankee Operations 3.3.a Operations "id adminctrat ! m (r Adict 2) Se/lS the maximum acceptable setpoint to 196° F in lieu ofthe 2120 F presently allowed by the Vermont Yankee Technical Specifications. An ER has bee generyOd, addre this issue. Sign & Date J__ __0_ _ _ _ /_ J/_ Vermont Yankee Ogerations Reoreststive 3A. Vermont Yankee Systems Manager Concur Comments 3.4. This analysis supports the design bases for the HPCI Systenm 4 Sign & Date 1 Vei t YankecSyem Engirrming Representative 3.5. YNSD)NtIucleart ngmerg Con Comments 3.5a. Custom Technical Specifications
- 1. Analytical Limit used in setpoint determination: MO96 FO
- 2. Potential accident trip (LOCA): NA
- 3. Potential accident trip (HELB): 196" F 3.S.b. Improved Technical Specifications
- 1. Analytical Limit used in setpoint determination: 1960 F'
- 2. Potential accident trip (LOCA): NA
- 3. Potential accident trip (HELB): 196- F See Section 3.1 and comment I Sign & Date Izo0* YNSD NED Repre sentative
+,' i'Page _.A of j,
,rmE IG m3CI0 Vermont Yankee Setpoint Control PrMogm MA=Z Intepartmental Reviewv of Calculation VYC- 462D Revision 0 3.6. Vermont Yankee DBD Manager Yes No 3.6.a. Ibe HPCI DBD should reference this analy .
The DBD Is complete (an AP.0028 to follow) O t3-The DBD is not complete. Incorporatt reference to this analysis as O a-apprmpria . Sign & Date -4::-, 14 - , ze I ,-.M 7'- ISP Progm Manager 3.7. Vermont Yankee Licensing Impact Yes No 3.7a. FSAR Changes (AP-002S to follow) Table 7.3,2 00= Table 7.3-Sb 3.7.b. Otherimpactonlicensingbasis: 0 0 The ClS has a limit of 212 VF. 7heA anyf lca Limit is 196 F It Is not acceptableto have anAL < CISasthis wouW allow the Lnstns etpoInt to beabove 1960 F(out.;& the analsislimits). Either
.:e NED aw65nis needs to be revisedto use a vawhe of 212 F or the CW Lbmlt needs to be lowed Jo 196"F.An ER has beeng awedsto saddresthis coOm ?PR : S X we . xCwAzr
-<e/Czssr4Ar ;e- AVc AA@-,'8&r ?M' r-1soss 1 c ezk .
Sign & Date .. e -oY4V ISP PonaM Manager 3.8. Varmont Yin~kee llS5 Manager Yes No 3.8.a This analysis provides an input to the ITS. An Allowable Value applies. 0 03 Allowable Value -9EF * ?.-35i10'3 2c .7C ar 9, 7 198F S;CaM" 7 ULK . 3.8.b. This analysis provides an input to Technical Requirents Manual. Incorporate as appropriate. o c0-Jl~,J Sign & Date - - ISP PrografManager 3.9. Other Depsrtment(SYFrgram(s) ( None) Concur 3.9.a Impact assessmenthwoeomendations: _ 0 jJA I Sign & Date ISP Progranm Manager
- 4. Setpoint Program Manager Completed 4.1. Concurs with above. a
- 42. Interdepartmental Review form (copy/steps I through 3) incorporated E into calculation.
4.3. Calculation has been approved. Approvedon________ 4A. AP-0028 commitments have been assigned and forwarded for 0 incorporation Into the Commitment Tracking System. Sign & Date Si4_, Page ? of c
P. t
'I V j.
. .. I
- 5. Post-Approval Requirenents Vermont Yankee Sctpoint Control Program Interdepartmental Review of Calculation VYC- 462D Revision 0 r61W oM MFNM REIIQW~ 52
- a. E&C Wform as apprpiate):
- Initiate AP0022 Setpoint Cliange Request AP0028 - - VYCD462DRO-01
- Update MPAC -44A., -&c Cpmm
- Revise calibro/functional/ogic test ocedu
- Inforim the following after changes are implemented: #'
7'4i~ 9
,c.a vSj' "o '; C~ep
- Setpoint Coordinator
- Stpoint Progam Maager
- Training (notified via AP-0022 if initiated)
- Operations (notified via AP-0022 if initiaed
- Design Engineering
- b. Setpoint Program Manager. Update Program Manual IB VYC0462DR0.02
- (aftirstep 5S).
- c. Setpornt Coordinator: Update Setpoint Data Base AP0021B_ VYCO462DRO-03 (aftersttsp 5-.)
- d. Design Engineering: Initiate FSARJDBD changes, AP002O VYCO462DRO-04 as appropriate (if DBD has been completed Comments:
I) An ER has been generated to address the condition where AL<CIS 7- ,;s: /az~5PC Nt APOOZ 8 vYozbo -ek; A&Z70 ZaSSx- Z<X;f ZWe-11"- ^A/ca- -A'gR
-Zcv$ IAJX S. 7 69eL-=) * (PS 7-46,- exeT Ae)
Page yL of4,-
7 WCALCULATIONCHANGENOTnCE(CCN) VYc-46ZP -c-c-A- cd Poled.-i e- a CCN Number: 01 Calculation Number: VYC-462D Rev. No. 0 Calculation
Title:
High Pressure Coolant Iniection Steam Line Areas Hi h Temperature Setpoint Initiating Document: PO 99-5911 0-00: Commitment VYC-0462DR0-03 VYt DC/MMfM/Spec. No./ other Safety Evaluation Nwnber: N/A Superseded Document: N/A Reason for Change: Provide a basis for increase in Technical Specification Surveillance Interval from Monthly to Quarterly. Description of Change:
- 1. Evaluate CTS Quarterlytesting interval on calculation outputs.
- 2. Address commitment memo issues.
SEE PAGE 4 FOR DETAILS Technical Justification for Change: Technical Specification proposed change No. 217 requests surveillance test interval change from monthly to quarterly.
Conclusions:
For CTS Quarterly:
- 1. Existing setpoint and uncertainties supports Quarterly functional testing of logic.
- 2. Setpoint, calibration attributes remain unchanged.
Prepared By/Date Interdiscipline Review By/Date Indepcndent Review By/Date Approved By/Date 1t9/2-711 FOPtMS VGS. 18-ZM- 1 43//4600 Z/ 0O I~~~M I II a W F.so OP~rp3 iTem5. Installation Verification_+ .N A o - _l -zl1 LO Signature Date Note: VYAPF 0017.07 should be included imnediately following this formL VYAPF 0017.08 (Sample) AP 0017 Rev. S Page 1of I Di #99-381
VY CALCULATION DATABASE INPUT FORM t4 -442VPLCr - - o I1 2. of ; VYC-462D-CCN-01 0 N/A MIA VY CalculationlCCN Number Revision Number Vendor Calculation Number Revision Number Vendor Name: NIA PO Number N/A Calculation Type (Originating Department): VV Ieian, Vnvineprino llrlkrl Implementation Required? [3es WMNo Asset/Equipmnent ID Number(s): Various Asset/System ID Number(s): 23 Kevwnrds: No New KCevwnrds General References Reference # Reference Title (includina Rev. No. and Date. ifanplicabic) (See Api,. A. Section 3.1.7 for Guidancel Critical Reference ( I I I Technical Specification Proposed Change #217 1 1*
- 4. 4.
- 4. 4.
4 4 4 1. Design Input Documents - The following documents provide design input to this calculation. Docurnent I Docuaent Title (including Rev. No. and Date, if applicable) Critical Reference _) No New Design Input Documents Design Output Documents -This calculation provides output to the following documents. Document I DocunentTitle Critical Reference C) _ No New Design Output Documents I I 1 1 4 4 4 4 4 4 4 4 4 4 VYAPF 0017.07 (Sample) AP 0017 Rev. 5 Page I of I
Page I of I VY CALCULATION OPEN ITEM LIST Calculation Number VYC-462D Revision Number.. 0 CCN Number: 01 lOpen Item Resolution Method of OI Tracking or Date Closed p I 0 p la I P. VYAPF 0017.05 (Sample) AP 0017 Rev. 5 Page I of I
VCON vy ALCtJLAfONU,~ SMT C,-4Z Z. - cIA _o
-46 Rvial Number:
Callon NPagew of CCHi NWW MID Itkc,;S 4 Q A Att ;>A 4i'- a Cr ;;y+ I&,V v.i4&L cr v,; o(r;9. Vw$5r; UtC* ;e44 4$# A. . SvOAD'k-e Qc.&*Aev~VoLL(tt1 ago4L~ -cJr-ovc.L -6 ce~a' 4. se...eS 4, <2e46cL XCAec .;te-rt;f
- 4. o.W-ec-.0-:kr^: oW;0e:g j-:1 )sW t~o v;5o~w.c-cvcS v, Jo cVl;rswc. 4s CCAl; Wcoe .X~es A5F 001C.0 A. 4C 001 Rev. 5
;-s'c. k %t&;Lj o
,S, ii.0%0-q" Lc 5 J _
or It_ a.. ct50-C4 A.-v.CCA t o . VYAPF 0017.03 AP 017 WtV. s
'YYC-4(VC4. - ce -0
?&e.5 af 1r9I V# T;- Ar Uiv T .~ .*
J W L . 9a KW. . S^t VYC-02D, EotO I. Wm doa finclion.
- 2. D dmmine te mnal and toW loep mclatty an verify co cy with She design
- 3. Cakulate dte Iimizg ASpoi and operdecision points
- 4. Evakat the akdwy of the exis actp calblstoa lub and p~odix decision paints S. P vide -left and a-4W tleWices for se: hi calitnition wcodwes daumieo Meurig and Tust E vmt vsad acoancy crit doa;doc pmoctu ofrfectins, it
- 6. VYDEP-IS eqaiesthpplicaopemnling p aM Ip~e-P stmAoduPd off-ncSa ad a gccy operatg procelre be boxbkd hI do evahniko. This requIr is c boshed by t WWeqlscily review which s te lhpWE-103 rview s and CCA4-1 1.2 WS Calculation apm to tf Hgh Pss Co bIjection (HPC)lw e Stem Lin Am's H gh t71/ZJ/f Ewgy Use Break (HELD) debton swch h Ie HPe a Syst. TMa spcic comnponazt to be tihoo addressed arr.
-_-___ TABLEIals.
OWL TAG Number 4Lato C iMF od2el CWD 6.6 13-23-IOlA Stem Tunnl TaMPema Pazual 7023 09 1449,1431 6.7. iS-23-102A EL 25Z 6" Swib, 6.14 TS-23-103A TS-23-104A __ 6., TS123IOIB Rx Bd EL TesUa Fenwal 01-1702304090 1449,1451, 6.7. TS-23-102B 2139' Switch 1456 6.14 TS-23-103B TS-23-104_ 6@, TS-23-IOIC Rx Bldg. El. Teperture Flwal 01-170230M090 1456 6.7, TS-23-102C 213' 9" Switch 6.14 TS-23-103C TS-23-104C _ 6.6. TS-23-IOID Rx Bbld EL Tanpraste Fa J 01-17?230-090 1456 6.7, TS-23-102D 21379' Switch 6.14 TS-23-103D HPCI Room I TS-23-104D I
~~A; 54 L o b.. So f 31Al r LSlve-vJr _ CS S&
V V-4 S
*%5e--6 &x- e-j .
P74 . I vc.-4A(zD-cca -bi HPCI Steam Line Areas HaH Temnerature Setnoint VYr-A,)n Rq- f 2.1.7 uffimo of xt The e xiting scp leIs II? F. A review of dh DA indicates this variable is am dependent. The I SO F isan acceptable selpoint for s duraton after lhas calftloo. An evalugioa Jusiffying the use of l135 F isprovided as Altachment R. Inpa;s mssmmxpocas. and cowbhaiouu am dss sevk 2 1, CCA-3. 2.2 CSeCe. nQ'se.4 l ieZ 1 221 TheI awmTepr" a Effee) snoapplicableb m t_c e o e st ed -LL p mmeter of the d vice.* 2.22 Te effect on sdpolat of harh enouebta conditions caused by LOCA/iELB are eglgb ( - t G& These inel
- Sepoint Shift
- Radiodn Effect UR)
- ContactRes
* '=,,Wm Resi"snce (IR
- HiEfct(HE)
(Reference 6.7.1., Section X2.3) 2.23 For Custmn Tchnical Spcification (CTS) alicaons On CS vae Is h afly asumed based OD VAral opeating conditons. However. in fthicase duft the ewnt for whih e switches we crodked (HEWD) a m ocw (see Section 2.4 May Consequently, for CIS as well as S,this pmUiIn eIt Will be accoud for. 22.4 Per Rference far Irt dTechnic Spcification (ITS) appl tio, the ITS vaiue is assued bused on the astamtg of HEL with TE and HEff Seic Effect (SQE) 22.5 Per teorig plant design in o dat dzeft (DMrawing 22A5600, Shat 100, tse switcewereawal l7 6()100F to (+)600F.PertheEQpogm.h swicheswme Pul-Fenw&a 01.170230090, racngem specied (QDR 9A, A x 11, woae) Per the vendor nual (YM4 9) te witches wdp§ (Podoct Line Sold) 01-170230-90,M o an specifled. Per VYC-1599,Table 1, ths swices are Fenwal 01-170230.090 (-)100 to (+)600F. Per MPAC (page I and page 6; i 1)these witches am Fewal 01-170230-090 (-)4VF to (+)200F. For Om pps ofthis calulaion, tm following isused as inpuW based on apprved engeering-soutces: MFG . Fenwal (QDR9A) Model -01.170230-O90(QDR9.4) Range - (-)I JO to (+)600'F (VYC-1599) I Page lof 3l i I
VY CALCULATION SHE5/ "~c - - - Calculation Number: VIYC-462W Revision Number: 0 CCN Number: c I Page L of 22 L.d.F !5vuv&-VeL*d-AcL Cir%;-.e-Vlo.. 4.8A
. Vs..L oJr;cA L Tei 4-(?e,- -L c se a4;eWA; S5 UiV-Ve;L44C)L
> .J4vs;.k-c-- -6s6s &r-c qe,-6w--m Mar~ki -vsd T e c, 1c -°- Zr 41 Ts T-L
/. Z. Z .1 -1)
-e. 1.ei o 4o,(
t . o? 4358, hv .3, A...t 4vc;o
- O WYv~tL i0 l - .4.
O TsS+i 4 54. 55 . S -ett - iA ,i4 4 t
\40WI V 1,4.t&-6 ;-r ;5 essa-;^-L~ a Lal;c.
/TC5+
VYAPF 0017.03 AP 0017 Rev. 5
HPM Steam Linm A&Was High T-cmaature Setnoint VYC462D. Rev. O 22.6 PerRefrnce 6.1. the Isa pes dfectof+3Fper lOO.PrcrR nce 6.72,dhe maximun protetcd ers pressur rise is +5.1 ps. Whee HELY sr effect (OPjm) Is P - (3F100 pso x 5.1 psi
- +02VF(Conservatively Rounded) and manifested es (+) bis Inthe ooncsrvative (ratve to safety function) direction.
2.2.7 Per Rtference 6.1.tde following onoal conditio uncatainty terms ae encowpassed i the DA Value:
- Measuring &Test Equipment Accuracy (MTE)
- Drilt (as a fMctlo of tim) (DR)
- Temperature E t (AT 20'?) C(E)
. peesun Effect (PB)
- Huiftn Effect (HE)
- Radion Effect (RE)
- Vradm Effect (non-eismic)
Based on recalbrtion, the above we tken as noncwnubtlve. 2.2.3 For this tpe of device, t folhe owg norm condition uncetlaV Saote nc applicable:
- S~tati pressume effects o.a span ad zoo
. Power s pplyifr 2.2.9 Per Reference 6.1, no uncetainty Iscredited uplast th relays controlled by thes devices.
22.10 Based on the design location of hese devices (see UR Section 7.3A.7.10 and 73.5) the nonconservatve affcts of Pr Measurement (PM) we negligie. 2.+/-11 Per CTS. the specified caliatlon interval Is'tub mrueft outa. Per Reference 6.9,1ds intval Is tyicallybounded by I tmons and is taen asl ii (by the reffSIMrot calenahrday). Toadlow fbrarhdigcyceded: L 8mont ehis cealculaton wfi base DA on mxm bt of775 d which is to be bounding for any ra g otnitra. lC-CA 22.12 Per VCY-1 599. Section SA. the elyzed drift data for dte devi (pooed PRc s 0P 4358 /§ end OP 4370) Idaed i etleth dependcy. ' ayzed rIftvalue for Groups Op4358 and OP 4370 is for 775 days. This inthalspgflou bounds th rqired Technical surveillance ine . Cosequently, no fmr e drift extrapolation is considered Wall v-U,c.fwre ;ot
!7 Oj4 M. LA ov CQ"V-vcL,, Akt-v- c t- 4 o i ~ ~ ~ (~ +e-$8Vv rV 1.5u>
4-^51 [ > isocy~a UVAa
%Gi #'eftt J to65 5 tie
I1 V'ic.-4(*7-D -CCA - o iR Pcn 9 VDC 2' . HPCI Stewn Line A sagoint WXCMDRcv.O
.4.3 Sgiric Mgek UrtvULrao)
For HELD i til chunnels, is detrmned by HEL condios of ever-pirssum coidcdt wkh, o sbsequat to admic eecLt Frm Rdimc 67.1 (Anachmert PI pontemic effect nged frum -3.1F to 442-?. For cocsrvathm, ft poo-wismic s;uato m neo c h dIOf 3F Isc UM a
- CC== 7=A49eev 4- C>t4.-
_mlb _ - c51ce. &4 n% 1t ) ' SE-*3.00*F .- i//UI Accounting for unowtshte nh~odl-c by £ sismie vent foflwed by swi actuation csd INS-~ bya HPCI ubine site Us HELB: o -
- IC 3 + DV + SW]'*+ OP cm' -
- f10.0V +9.74F + S.O00"34 (0Z5) + 020F
-+ 12TF/-12AWF ,
- 4.4.4 dtx RISWMBon V Bbc" out R Fom Seci2.16.amipliof 035 is alied totenorml modu untai to t a am 3 normal unceaanty (eg). Frcn Sectin 43. ft normal module unceiahly (c) -
*11.90F. Applying the 035 multiplitr.
.rej *1l.90ZF 0035 - &4.1651F ,-
Hawever,a CT > ea, the CT value oft*7 win be applied. 4.5 Sewnt Eva l 4 L5.1 S-TS U i ( LSP -11;-lTrWI
- ..-..V.
I 4.3.1.1 TS-23-1011.02 103,104 MC.D) LSP.. - AL. In-IT I IS - CTS Tabl 322 Trip Sein S21F(HotUsed) AL- 196F (Table 3) Pae 19 of31 I
vyc -44 zp- cc 4 - o . VY CALCULATION SHEET Calculation Number: C- - 4'62D) Revision Number: a CCN Number: 0 ? Page 10 of 2.L C'tV (ON L t4ti 4
.cI e~l#;s 4-L~^.,r -es-'S 4
ACeeA-tV4LLrrve. Ivo S;~e VYAPF 0017.03 AP 0017 Rev. 5
I,,..
.- -7
. k a' 2t!rf~
EU1I .o Q I L.. A. m~AIL.IMWxm I~.Z U.4. An TU.-n L I s cmnnu; U O.0 t VItr]y I L J~vn - 9%
. n cv. U FIGURE 2 Gphi RCphmlteR etSetpalat (ITS)
Limi (Isd iM A rxmnel) 2000F Analytica Limit (outside mtem humne:1) 19 Alowabl VaUe' (AVA) 198F Alowable Valie' (AVac) - 194F ISPA ISTF SPa SP, CA isrtbaed) - ISSOF 15Ps - I83FF Recommended Setpoint (SP - is"F LSP - 1797 SBO main S-m Tunnel a 1744P NormW (MAX-stm4 am - 140*F
- 1. For[S, the oAllwable ValmY lathe I vawue
- 2. The exbg SP per OP 4358 doesO aupport the IS ueataiy with Reduced Analyda Limi
- 3. Not to acak; P dt reai Position !l. _
5qA "54>CiA -S OL___.SC oot lt 5'e-f V% mnto cvYF qp" 4 thle resealss oflh caicuolntim th temperature rwitches = to I,. IexAA be calibrated acmdi to dw Mowing be: Scvoird (CTS)
!=29=o bikd - aiime jVain TAB= a cai o Attributes It5 v A Uab OUel 130 IS;4 7F Serpoint(S) tsdes Unw 185 :' ' - OF T Ou-deoaeranc *5 F A,-round Toieraue
_ _ _ ___! . I 5s.
,1/1-041 A.AJ/ -
- Monkitaon termocowPle crNPE K) (Installed ' 0s,7,
- TIC Reader (Dgta Tbamorter)
- Hea source (Test Heaer)
- Digital Multimeter
- Varlac Page 27 of31
VY CALCULATION SHEET 'i'4.
-MoZto - CCd A -o C.OaNwicr: vjcU-44zI Revision Number: o CCN Number: b Page 52 of ;2 a.
t.ci4-t tzle < wiedkve.L~ CeSs~_\ e..4 5
- 2. 4ctiorvL CIA.4. CT
( K4ow ~~>&~ qt~~~~~~~s -F t *atlrtv;^ A7%-^ o VYAPF 0017.03 AP 0017 Rev. 5
Memorandum IL- 4 Wx - rcAS - ,,i TO: George Hengerle 'Pale &Z3 J, va FROM: Mark McKinley RE: Convnitrnent VYC-0462DR0O03 DATE: March 24, 1999 George, The Setpoint Database has been updated per Comtnitment VYC-0462DR0 03. Attached are the printed form from the Database for the components listed by the cornmitmnent. No discrepancies associated with the Calibration Procedure, PP 7007 IRF or Calculation were noted during this rview. Thanks Mark S. McKinley I I I I I Freo the desk . b Mark S. McKboky Vermoat Yaakne Design Eng. (C) Thonr. (802) 25154735 Fax: (202) 2515S34
REVIEW CHECKLIST (ER 961090_01) 'yc. 4.zz- cAd -U; N/A any Items not applicable to the calculation or CCN. Recuirement PreDarer Revewer
- 1. Ensure the title page is properly filled out (items that are applicable).
- Calculation or CCN number on cover
- Title reflects subject
- Correct OA record status box checked
- Page numbering and count Is correct
- Cycle number is Included ('NA" if not applicable)
- Initiating document Is listed
- SSC I.D. numbers listed
- Vendor calculation and revision number listed
- Vendor safety class P.O. number listed
- Superseded calculations listed
- Keywords assigned
- Computer codes (input/output) listed
- Signatures and dates are Included and are in correct chronological order. The title page reviewer and approver dates do not predate other dates in the calculation ^#. - H
- 2. The following forms are properly filled out and attached (if applicable):
- Review formsVYAPF 0017.04 (Ensure dated signaturesformthe preparer and reviewer are included and all comments have been addressed)
- Open Item Listing VYAPF 0017.05 #A61
- Evaluation of Computer Code Use VYAPF 00i 7.06 o-44-IA
- Calculation Database Input VYAPF 0017.07
- Calculation Change Notice VYAPF 0017.08 I /1
- 3. Ensure review of the calculation can be done without recourse to the originator.
- 4. Screening Evaluation/Safety Evaluation Included. N/A
- 5. Ensure individuals responsible for each portion of the calculation are Identified when multiple preparers and/or reviewers are used.
Appendix H AP 0017 Rev. 5 Page 1 of 3
APPENDIX H (Continued) VAD-4"2Lv-c-C..t -ca
.L- Ata v OA ?" I7~
*_ReaurLement -v . , I Prenarer Reviewer
- SpV-CCA S ,.,S$ 4 5j
- 6. Ensure that the calculation contains a title page, tatle of contents, calculation objective,method of solution, design inputs and sources, assumptions, calculation, results, conclusions and references.
- 7. . Ensure that each page has a page number, calculation number, revision number and CCN number, if applicable.
- 8. Ensure that every page of every attachment (or Appendix) contains Its attachment (or Appendix) number. A/ Of
- 9. Ensure that the methods for revising and correcting the calculation meet the requirements of App. C of AP 0017.
- 10. Ensure that the legibility requirements of App. D of AP 0017 have been met.
- 11. Ensure that the appropriate design Inputs (e.g. QA records) were used and the source of these Inputs are clearly referenced.
e--
- 12. Ensure that the calculation design information, both external and internal requirements have been met.
- 13. Ensure that if design specifications were used as Input to the calculation
- the performance characteristics are independently verified and documented. P IA ry. $--
- 14. Ensure that all reviewers' comments have been addressed.
dl _ &.1
- 15. Ensure that Input and modeling uncertainties are explicitly addressed in s/-7 the calculation. (ER 961090_02)
- 16. Ensure that any restrictions and/or limitations on the use of the calculation are clearly stated.
ts/
- 17. Ensure that computer codes are used In accordance with App. E of AP 0017. _V
- 18. Ensure that the applicable Input considerations from App. C to AP 6008 have been Incorporated and are explicitly addressed within the calculation.
- 19. Ensure review of 10CFR50.46 reporting requirements has been documented for analyses which assess conformance to 10CFR50.46. .3/A #/A Appendix H AP 0017 Rev. 5 Page 2 of 3
APPENDIX H (Continued) Vic.. - 4Cz.,>- cc o Reauirement 01=are Reviewer
- 20. Ensure relevant conditionsllimitations have been reviewed fortheir effect _
on this calculation and the review Is noted Inthe calculation. -4 PREPARER l REVIEWER Name (print) lkC0so4 ' Name (print) r S te Organization V'I)I Y E C. Organization 6 S - Ere Signature (LI=) S Signature f 4 ; Date l4 Zs IC)cc Date Appendix H AP 0017 Rev. 5 Page 3 of 3
Page L of4 VY CALCULATION REVIEW FORM Calculation Number, VYC-462D Revision Number: 0 CCN Number: 0Q
Title:
High Pressure Coolant Iniection Steam Line Areas High Temperature Setpoint Reviewer Assigned: Jeln M"K Required Date: 1/29/2000 Comments* Resolution -Ruvtfcb =AW AP-oil7. Mo Co mrmnts . (tA- J&. &3/0 1 I- I_ (% I A&n1 7/ A'Z Review4Signatufe
> 7 /T/cooa Date 4A 2-c AAQQ -,
Calculation Preparer (Comments Resolved) __/ PB<. Date - Method of Review: IS/Calculation/Analysis Review CMAlteeRative Calculation OJ(A4 .(. Ae.l. ../..S 03 Qualification Testing Reviewer Signature (Comments Resolved) Date o
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. C Questions should be asked of the preparer directly.
VYAPF 0017.04 (Sample) AP 0017 Rev. 5 Page I of I
PageoL.I of' I VY CALCULATION REVIEW FORM Calculation Number: Wc.-'L(,b) Revision Number:, 0 CCN Number: C) :
Title:
UD-Te- nS1- 4L~u A. W;^lA .^ Reviewer Assigned: 2 4 C . Required Date-. lLZ.7/Loo Comments* Resolution 4As 20 &Oa 2-/1l.10 9)c R Of&, P,(0, . /(z-A oo --
-Reviewer Signiture Date Calculatich Preparer (Comments Resolved) Date Method of Review: 13iiculation/Analysis Review o Alternative Calculation eie- igae (Cmmnt Reslve)D O Qualification Testing Reviewe Signature (Commnents Resolved) 'Date .V -=
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly. o VYAPF 0017.04.(Sarnple)
AP 0017 Rev. S Page I of I
Page I of, I VY CALCULATION REVIEW FORM Calculation Nunber: VYC- LI biD Revision Number: 0 CCN Number: 0 1:
Title:
IAPXQ Z6!1, L v Imem;m -4 Sae.A-Reviewer Assigned: Required Date: IJ2.0I Dae: D Comments / Resolution
,k2 CiAA-UEArS- (A- P(1/2. ACa. /la_-
L:t44:~ CAM 0y ,44AE, dAa,°S~/5~1
-Ve 44°?
A7o /7 CW 4-vd-jA"t A A .ce Ijo 43400 &(A g ,Q0rnsvt. 0,
.~~ L00 iA
<s2r 2Calculation Preparer (Comr nents Resolved) Dite it
- e 7
Method of Review: o -a
'Calculation/Analysis Review C' O Alternative Calculation L tA Z>//2-00oo o 0 t o Qualification Testing leviewer Signatur (Comni ments Resolved) E ate
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wor ding to ensure the correct Interpretation of .p Issues. Questions should be asked of the preparer directly. V 7 VYAPF 0017.04.(Sample)
AP 0017 Rev. S Page I of I
Page I of' I VY CALCULATION REVIEW FORM Calculation Number: _C.-L44btZT Revision Number: C CCN Number: Ol Tide: pXc. Lsa p, ;.:, , ; i mi, Reviewer Assigned: ___________________________ Required Date: AI2.L=0oo Comments* Resolution k0 Yxvti* Mal L Q zf3/O v< c e - _ ___._, swsl duA U7 W
,a~~ TclN . -
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,fiU I U/tD Wao q - W Aa" / ?d la I Reviewer Signature Daf' Calculatibn Preparer (Comments Resolved) Dati O C Method of Review: IeCalculation/Analysis Review 47 n M Alternative Calculation 4 k P. (J. \ QQ / 713/ o O Qualification Testing Reviewer Signature (Comments Resolved) sate O
- Comments shall be specific, not gener. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
VYAPF 0017.04.(Sample) AP 0017 Rev. S Page I of I
Page L of' I VY CALCULATION REVIEW FORM Calculation Number: VYC.- 2L71) Revision Number: 0 CCN Number: Ol :
Title:
HPXCS1w LSujI. fJ;cisi qr40.iA" Reviewer Asslgned: 1:cr "I ) Required Date-. I/Z'2.0
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Comments* Resolution
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/ Anoo IDate Calculatiohi Preparer (Comments Resolved) ob I N1 Method of Review: ,(Calculation/Analysis Review 0 Alternative Calculation 0 O Qualification Testing Reviewel Signature (Comments Resolved) Date
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
VYAPF 0017.0 4 .(Sample) AP 0017 Rev. S Page 1 of 1
Page IJ. of I.. VY CALCULATION REVIEW FORM Calculation Number: \tc.-4LZ.D Revision Number: 0 CCN Number: If
Title:
Apxc.. 56 Lt 1. At.&-% P.L4ifm M in4 Reviewer Assigned: Ne) Required Date: t/I iLwog Comments* Resolution O(4, P.(A. Ao Q- ,-r /.o 7 A L e
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Reviewejn Iture l0a(e 4Calculti(n Preparer (Comments Resolved) laik Method of Revf/w: B &culatton/Analysis Review IN O Alternative Calculation reY e AMme, ( Resove 5/Dte (,I O Qualification Testing ievewer Signaturc (Comments Resolved) Date'
- Conmments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of 0I issues. Questions should be asked of the preparer directly.
VYAPF 0017.04.(Sample) AP 0017 Rev. S Page 1 of I
ATTACHMENT 6 TO BVY 05-068 CALCULATION NUMBER VYC-462C REVISION 0, REACTOR CORE ISOLATION COOLING STEAM LINE AREAS HIGH TEMPERATURE SETPOINT, WITH CALCULATION CHANGE NOTICE CCN-01 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
oa 4'S 0,: Dg ORIGINAL: PAGE 1 of _=U-_PAGES 0 J1D tO9' VYC462C t 1: oh AmmB I
-n -16C 3 os 30 AIbaoD 8 QARECORD? A 4 aLtH: IT A G 3 RECORDTYPENO. 09C160-4 r=H ffil 17 I-01 s Anacb~m A=Amnt3 2
3 __NO 4 Safety Class/P.O. NO. iSCE fM Amtf" I (if applicabe)
- ,j °fl
- 3 oC P. o3 YANKEE NUCLEAR SERVICES DIVISION CALCULATIONIANALYSIS FOR R- PONT-PLANT VERMONT YAN1F.P CYCLE 20 CALCULATION NUMBER VYC-462C PREPARED BY REVIEWED BY APPROVED BY SUPERSEDES IDATE _ IDATE . /DATE CALCJREV. NO.
ORIGINAL j tJw.4..;_2
- Re / - ;
L Afidesn D.W- ,8{iF KEYWORDS RCTC. PCIS. Setpoint. Une rtainty Steam Tunnel. II.1 COMPUTIR CODES: EQUIP/tAG Nos.: TS 7I9A B C Dn TS-1348fA RCD:TS-13-81A R.C - TS-13-82A-Cr CD SYSTEMS: Reacor )re Isolation Cooling (RC= ,YSystem 13
REFERENCES:
OP 4366- Technicl Smecifiation Section V4-2 R1 Tsbhles 22 & 4.22 FORM WE-103-1
- APP'R I/ZO &A.r ir5 Revision 4 V/nANOMW30l&=
i RCIC Steam Line Areas Higeh Temperature Setpoint VYC-462C. Rev. 0 Table of Contents Page LISTOFTABLES .. 3 LISTOFFIGURES 3 iHISTORY OF REVISION .. 1.0 PURPOSE S 1.1 Clation bjeives .................. 1.2 Syst.m..poents ................. 5 1.3 Instu tbpFunction ................ .6 2.0 METHODS AND ASSUMPTIONS ................. 8 2.1 Crieia ............. ;.....8 2.2 Assumptions .10 3.0 INPUT DATA .. 12 23.1 Process and.lo1 Data ....................... ; 12 3.2 Environmental Conditions .12 3.3 Switch Data .13 4.0 CALCULATON DETAILS 13 4 4.1 Normal Condition Uncertainties ..................... 13 4.2 TestUnctity (e) ..................... 17 4.3 Nomal Modul¢UnerCtant (e ..................... 17 4.4 AccdentCcinditionUncertainties.................... 18 4S & cpEvi o ons.19 ............................................................................................. 4.6 MarginEvaluation ............................................................................................. 22 4.7 Allowable Value (ITS) .............................................................................................. 4 4.8 Calibration Tolerances ............................................................................................. 25 5.0 RESULTSICONCLUSIONS .............................................................................................. 26 5.1 Total Loop Uncertainty ............................. 26 5.2 SetpoitEvaluation ............................. 26 53 Graphic Representation of Setpoint Data ............................ 27 SA Callbation Criteria ............................... 28 5.5 Measuring & Test Equipment Requirements ............................ 28 5.6 Recommendations ................................ 29 5.7 VYDEP-S Criteria ............................. 29 5.8 Evaluation of Existing Setpoint .............................. 30
6.0 REFERENCES
............ 30 7.0 ATFACHMENTS ............ 31 Page 2 of 31
VRtr Q*Ptm T.inoe Arac fligh Tempmrahire.Retnnint VC..AA')' Pev A LIST-OF TABLES fra TABLE I Coponent Identification .................... . .. .. .5 TABLE 2 EQ Matrix Data TABLE 3 Proces/Lop Inputs .12 TABLE 4 Environmental Input Data .12 TABLE S Temperture Switch Input Data .13 TABLE 6 Total Loop Unceitainty Results ... 26 TABLE7 Setpoint Results . ............................................................................................ 26 TABLE 8 :aibration Attributes ............................................................................................. 28 TABLE 9 Recommended M&TE ............................................................................................. 29 LIST OF FIGURES FIGURE I Graphic Representation of Setpoint (CTS) ......................... 27 FIGURE 2 Graphic Representation of Setpoint (ITS) .......................... 28 Page 3 of 31
n RCStm LeAa H .T }tCIC Steam Line Areas High Temnperature SWtpint t VYC462C. Rev. 0 HISTORY OF REVISION Rev. Nom Approval Date Reason and Descrpon of Change 0 10-30-98 In'tial issue; noporate plant-specific analyzed drift den and new setpoint methodology, uppeot Improved Tchnical Specifaton submittal; Wc-462t! Revision 0, supersedes WC462, Revision 2, (Calculatlob subset IC" addresses the loop function of Reactor Core Isolation Cooling Line HELB 2detection).
.. 2 Page 4 of 31
RCIC Steam Une Areas Hih Temrerature Setpoint VVY'-A;) w
- 5__V£, R^\Gt.tVs nUJ 1.0 PURPOSE 1.1 Calculation Obiectves This calculation is performed in support of t' Vermont Yankee Setpoint Program and has the following major objectives:
- 1. Document the loop function and the basis for the setpoint and operator decision points associated with that frnction.
- 2. Determine the normal and total loop uncertainty and verify consefncy with the design basis.
- 3. Calculate the limiting setpoint and operator decision points.
- 4. Evaluate the adequacy of the existing setpoint, calibration limits and procedural decision points.
S. Provide as-left and as-found tolerances for use in calibration procedures; determine Measuring and Test Equipment selection and accuracy criteria; docunent process corrections, instrument scalbig, calibration methods.
- 6. VYDEP-1S requires that applicable operating procedures, alarm responses, standard, off-normal and emergency operating procedures be included in the evalrttion. This requirement is accomplished by the inter-disciplinary review which supplements the WE- '03 review process and is documented in Attachment 0.
1.2 Syster/Comnonents This calculation applies to the Reactor Core Isolation Cooling (RCICj Steam Line Area's High Energy Line Break (HELB) detection switches in the RCIC System.L e specific components to be addressed are TABLE I Component Identification _ Red TAG Number Locstion Description MFG Model CdM 6.6, TS-13-79A Steam Tunnel Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-SOA El. 252' 6" Switch 6.14 TS-13-81A TS-13-82A . 6.6, TS-13-79B Rx Bldg. El. Temperature Fenwal 01-17.0230-090 1179, 1180 6.7, TS-13-SOB 213'9" Switch 6.14 TS-13481B TS-13-82B . . 6.6, TS-13-79C Rx Bldg. EL Temperahtre Fenwal 01-170230-090 1179,1180 6.7, S-13-80C 213' 9" Switch 6.14 TS-13-S1C TS-13-82C 6.6, TS-13-79D Rx Bldg. El. Temperature Fenwal 01-170230-090 1179,1180 6.7, TS-13-80D 213'9" Switch 6.14 TS-13-81D RCIC Room TS-13-82D _ Page 5 of 31
DfTOl D ,'rG C#S 3tv1 bus ar Ta;-.; AxAPC . iohl T.Pmn%,rnhir,-
- Ta .
RptrMnnt vsnxAf.'r ID.. A I W. WV. 1.3 Instrument Loop Function 1.3.1 Normal Overations There are no indicators or anticipatoij alarms associated with these channels. Instrnment output is a contact change-of-state at the setpoint; therefore, these channels have no normal operational function. 132 Off-NormallAccident Operations High temperature in the space in which the RCIC steam lines am located outside of primary containment could indicate a breach of an RCIC steam line. Isolation Signal K (stean line high space temperature OR high steam flow OR low steam line pressure) results in automatic closure of the Class A valves which isolate the RCIC Turbine Stearn Supply Line. High temperature in the vicinity of the RCIC steam lines or equipment is detected by four sets (of four) of bimettalic tcmperamure switches. The detectors are located or shielded such that they are sensitive to the airtemiperature but not the radiated heat from h -tequipment The trip setpoint is set far enough above the temperature expected during operations at rated pouer to avoid spurious PCIS isolation yet low enough to provide early indication of a steam line break. Associated with each set of detectors is an additional temperamlre loop (TE-13-77A to D) monitoring the same space (Reference 6.19.4) and which provides:
- Remote temperature indication
- Alarm on HIGH temperature
- Alarm on loss of power (Reference FSAR Sections 7.3.4.7.7, 7.3A.8.7 and FSAR Figure 7.3-6.)
Note that a RCIC isolation signal from sensors located in the steam tunnel are permissive through a nominal 30 minute time delay relay (Ref. 6.19 and FSAR Figure 7.3.5b). 1.3.3 Accident Mitigation (Harsh Environment) From Reference 6.7 and Table 2:
- Components will experience a Loss-of-Coolant Accident (LOCA) harsh environment but are not required to function, nor be LOCA qualified.
- For RCIC HELB, components are required to function and are EQ qualified, with an operability duration of one hour for auto PCIS actuation. While a Small Break LOCA (SBLOCA) may exceed the one-hour qualified duration, operator action is credited for SBLOCA detection and manual isolation.
- For other HELBs outside the RCIC Steam Line Areas, the components will either not experience a harsh environment or, if in a harsh environment, are not required to function for that scenario.
Page 6 of 31
R CM Rtenm I.;ne- Aremn High Temperature Setnoint vvc,-df;,)r RCTC trn line Arean IThh Teninerature ettmint VVC'.4f9C' IR~ 1u fl n TAUBLE 2 EO Mitri Data Loop TlAation Acddent -IAT TBNI,2 FI,2,3 Dumtlon TS-13-79A, BOA, VoL 41 LOCA E 36,22 6 NUA SIA, 82A MS-HELB C 36,23 0 NA HPCI-HELB C 23,36 0 N/A RCIC-HELB A 36.4 1 I hr. RWCU-HELB C 23,36' 0 N/A _HHS-HELB C 23,36' 0 N/A TS-13-79B, SOB, Vol.42 LOCA E 22,36 6 N/A s% 8m2B MS-HELB C 23,36 0 ./A TS-13-79C, SOC. HPCI-HELB C. 23,36 0 N/A 81C,82C RCIC-HELB A 4,36 1 1 hr. RWCU-HELB C 23 0 N/A HHS-HELB C 23 0 N/A IS-13-79D, 8D Vol. 52 LOCA E 22,36 6 N/A SlD,82D MS-HELB E 23,36 0 N/A HPCk-HELB C 23,36 0 N/A RCIC-HELB A 4,36 1 1 hr. RWCU-HELB E 23,362 0 N/A
. HHS-HELB . 23,362 0 NOA
'Thi sc Not 36, does not apply to TS-13-0A 2 This set, Note 36, does not apply to TS-13-80D, -81D,4-82D 13A Post-Accident or EOP Functions These channels do not provide any indication or any funther function once PCIS isolation sctuat when the protected areas reach the trip setpoint These channels are not identified as post-accident instnmnentation in Technical Specification Table 3.2.6.
1.3.5 ADendix R/Station Blackout Considerations During a station Blackout the Main Steam Tunnel will heat up to apprwimately 174 1F (Reference 620). RCIC is relied on to bring the plant to a cold shutdown condition. To do this, the RCIC high tmperature switches located mithe steam tunnel cannot be set so low as to cause the RCIC Isolation valves to close unnecessarily. To preclude this, the RCIC line high temperature switches should be set as high as reasonably possible. This Is not a safety related function (Reference 6.21). Page 7 of 31*
RCIC Steam Line Areas HigPh Temperature Setgoint t VYC462C. Rev. 0 2.0 METHODS AND ASSUMPTIONS This calulation has been prepared in accordance with the "Vermont Yankee Instnrment Uncertainty and Setpoint Design Guiden ( ce 6.1), and WE-103, "Enginmtning Calculations and Analysis" (Reference 6.2). Standard methods employed in th calculation are explained in the Design Guide; special techniques and criteria are exained below. The r jufrements of VYDEP-1S (Reference 6.5) are accomplished through the Interdisciplinary Review process. 2.1 Criteria 2.1.1 Setpoint Class As shown in Table 2, these components are associated with Safety Function 1, "HELB Detection and Isolation." Consequently, per the Design Guide. these components' trip setpoints are Class 1, Nuclear Safety-Related. The switch function in support of Appendix R/Station Blackot.; ir not nuclear safety related. Consequently, per the Design Guide, the need to not inadvertently trip in suppbrt of a Station Blackout Is Class 3. 2.1.2 Scaling Considerations Per VYC-462, Revision 2, and VYC-1S99 (Reference 6.15 and 6.10, respectivety). the range of these switches is (-)1000 F to (+)600'F. Therefore, Calibrated Span (CS) is: CS 8600-(-)100 700DF Individual error determinants will be calculated to two (2) decimal points, the degree of resolution used for Analyzed Drift (DA) output in VYC-1S99. Output values (calibration tolerances, Allowable Value, calculated setpoint) will be resolved to the most conservative whole degree F. 2.1.3 Sinyle Side of Interest In order to avoid impacting both the analysis value (module uncertainty e') and plant operating margin (e), and since the loop approaches setpoint only in one directic. (Le., there is no low teperatre setpoint), a single side of interest factor will be utilized as per Reference 6.1, Appendix F. For a 95% proportion the following "J/K7 factor (fl will be used-() =3 /K
- 1.65/1.96
- 0.85 (Rounded Value)
Note that Q) is applicable only to random terms. Page 8 of 31
RCIC Steam Line Areas HiM h Tempeae Setpoint VYC462C. Rev. 0 2.1A Calibration Effect Considerations Per the Design Guide, CE is typically taken as the sum of the vendor's Rated Accuracy (RA) and As-Lft Calbation Tolerance ( . Based on the number of samples used to determine DA mthe (count- 199 as per WC-I599, Tab= 41 a test will be applied to determine if credit can be taken forRA being encompassed by DA. Test methodology is described in detail in Reference 6.13. In
. essence:
2 2 2
- If DA<[A +Cr2 +vendor'srateddrife +MTEL" ,
then CE- CT
- iDA [RAI + CT2 + vendor's rated drift 2+ MT]V ,
then CE CT+ A
- where:
CT - Present Calibration Tolerance DA Analyzed Drift from VYC-1599 RA -Vendors Rated Accuracy MTE - the Measuring & Test Equipment used in calibratick and where the vendor's rated drift is valued at 0 because the vendor has no published drift specifications. 2.1.5 Simn Convention The sign convention used in the Design Guide Is based on the effect of uncertainties on an instrument (or loop's) output signaL For this type of device, where there is no analog process input/signal output relationship the effect of uncertainties are manifested as a shif in the setpoint away from the ideal value. This results in a sign convention which is the reverse of that which is generically defined in the Design Guide. 2.1.6 Class 3 Assessment This analysis will determine the 95/e95% (single-sided/Section 2.13) uncertainty applicable to a Class I setpoint Appendix R)Station Blbkxout considerations do not require the sarne level of rigor and am be evaluated as a Class 3 setpoint (95%175Yo, single sided). In accordance with the Design Guide, the Class I uncztainty value can be converted to a Class 3 uncertainty (eO,). From the design guide (reference 6.1, Appendix F, Table I), a multiplier is determined as foUows: 0.68/1.96-035 Appendix RJStation Blackout support is an NNS function. Therefore, accident parameters do not apply.. Page 9 of31
RCIC Steam Line Areas High Temperature Setpoint VYC-462C. Rev. 0 22 Assumdtons 2.21 The error term "Temperature Effect' (CE)is not applicable because temperature is the measured parameter of the device. 2.22 The effect on setpoint of harsh environmental conditions caused by LOD NELB are negligible (Attachment G&P). These include: Setpoint Shift
- Radiation Effect (RE)
- Contact Resistance
- Insulation Resistanre (DRE)
- Humidity Effect (RE)
(Reference 6.7.1, Scction X-23) 2.2.3 For Custom Technical Specification (CTS) applications, the CTS value is typically assumed based on n&mal operating conditions. However, in this case during tfe event for which these switches are credited (HELB) a pressurization may occur (see Section 2.2.6). Consequently, for CTS as well as ITS, tis pressurization effect will be accounted for. 2.2A Per Reference 6.1, for Improved Technical Specification (ITS) applications, the ITS value is assumed based on the most limiting of HELM with TE and Hl; or Seismic Effect (SE). 22.5 Deleted 2.2.6 Per Reference 6.7.1, there is a pressure effect of+30 F per 100 psi. Per Reference 6.72, the maximum protected area pressure rise is +5.1 psi (RX Bldg. Bounding pressure is +2 psig). Where HELB pressure effect (OPm=,) is: PHEM (3°F/100 psi) x S. psi
= +020'F (Conservatively Rounded).
and is manifested as a (+) bias in the nonconservative (relative to safety function) direction. 22.7 Per Reference 6.1, the following normal condition uncertainty terms are tncompassed in the DA value:
- Masuring & Test Equipment Accuracy (MTE)
- Drift(as a function of time) (DR)
- Temperature Effect (AT 20°F) (CE)
- Pressure Effect (PB)
- Humidity Effect (HE)
- Radiation Effect (RE)
- Vibration Effect (non-seismic)
Based on recalibration, the above terms are taker. es noncumulative. 2.2.8 For this type of device, the following normal condition uncertainty terms are not applicable:
- Static pressure effects on span and zero Power supply effect Page 10 of 31
RCIC Steam Line Areas High Temperature Setpoint VYC462C. Rev. 0 2.2.9 Per Reference 6. 1, no uncertainty is credited against the relays controlled by these devices. 2.2.10 Based on the design location ofth-e-e devices (see FSAR Sections 73A.8.7 and 73.5) the nonconservative affects of Process Measurement (PM) are negligible. 2.2.11 Per CTS, the specified calibration interval is "each refueling outage." Per Reference 6.9, this interval is typically bounded by 18 months and is taken as limiting (by the refueling event not calendar days). To allow for a refueling cycle extended to beyond a nominal 18 monfts, this calculation will base extrapolated DA on a maximum interval of 684 days (using the critia of once per operating cycle +25% as a convenience). If the calibration interval extends, for whatewver reason, beyond 684 calndr days, an evaluation to detennine'thi interval increase effect on setpoint is REQUIRED. 2.2.12 Per VYC-1599, Section 5A, the analyzed drift data for these devices (pooled Procedures OP 4322 and OP 4366) indicated little time dependency. Consequently, it if assumed the RSS extrapolation of calibration interval is approprate. Page II of 3t
RfCIC Stem Tine- Areaq Hioh Temnernture Setnoint _ UVO-A41r 1D-. v . wusu nev n
*,J 3.0 NPUTHDATA Data used to calculate loop uncertainties, setpoints and decision points are tabulated below with the applicable reference or basis.
3.1 Process and LoO, Data TABLE 3 Process/Loop Inputs Reference Description Data (OF) 6.18 Analytical Limit 196 (outside steam tunnel) 6.22 - 200 (inside steam tunnel) 6A,Table 32.2 Custom TedmicalSpecification Limit S212 6.6 Existing Calibration Procedure Setpoint 185MS 6.4, Table 42.2 Calibration Interval Once/Refueling Cycle 6.4, Table 42.2 Functional Test Interval OncFiMonth 6.20 Station Blackout Reliability >174 (inside stcam tunnel) 3.2 Environmental Conditions ____ .TABLE 4 Environmental Input Data Reference Deaiption Data (-F) 6.7.1,6.72 Normal Temperature 140 (MAX) (Steam Tunnel is Limiting) TS-13-79A to 82A - Steam Tunnel TS-13-79B to 8213 - RB TS-13-79Cto 82C-RB TS-13-79Dto82D-RB ._. 6.7.1. 6.7.2 HELB Temperature 300 (Steam Twnnel is Limiting) TS-13.79A to 82A - Steam Tunnel TS-13-79B to 82D-RB TS-13-79C to 82X:-RB TS-13-79D to 82D - RB _ 6.7.1 Radiation Exposure 40 yearnormal exposure 3.5 x 10'R (steam tuLel is limiting) 2yearnornal exposure 1.75x 1IWR
. Page l2cf31 1--._
RCIC Steam Line Areas Hiah Temnerature Setnoint [ AYe--A')I ID- n v J \__U£t__ Itt:V. J 3.3 Switch Data TABLE S Temperature FwItch Input Data Reference Description Data 6.10,6.14 Range --100°Fto+600F Section 2.1.2 Calibration Span 700eF
'6.8 Output Signal Contacts close on temperature rise 6.S, Section 4.13.1 Accuracy t5°F I
I 6.7.1 Pressure Effect +30F/100 PSI 6.10 Analyzed Drift 7.S4F/544 days 4.0 CALCUl. MON DETAILS 4.1 Normal Condition Uncertainties 4.1.1 Process Measurement Effects (PM) From Assumption 2.2.10, PM (thermal stratification) is taken as negligible. PM 0 4.12 Prima vElement Accuracy (PEA) There is no primary element associated with these channels. PEA N/A 4.13 Calibration Effect (CE) Per Reference 6.1, CE typically takes the form: CE-A+CI where: CE =Net calibration effect A - Device rated accuracy CT Calibration procedure tolerance Page 13 of 31
RCIC Steam Line Areas-Hilh Tenuerature SetDoint
- V~rtAA1)r1
*
- _v - . ID-acv. n u
4.13.1 RatedAccuracv(A) From Reference 6.7.1 (Attachment P) the factosy temperature setting tolerance for units that close on tempta3ture rise isthe grcater of E5'F or 3% of setpoint (*6°F for a postulated maximum setpoint of 200°F.) However, the calibration technique described in Reference 6.8 (Attachment D) infers an average repeat accuracy of:*50F. For the purpose of this calculation: A *5.00°F 4.132 Calibration Tolerance (CT) Per Reference 6.1, the basis for CT iSthe rated accatrc of the device, or +50F. This Isalso the calibration tolerance presently in use in Reference 6.6 (Attachment E). Cl -:tS.00°F 4.133 Expected Performance vs. Actual Performance As discussed in Section 2.1.A and where there is no vendor-rated drift.
- If DA < [A 2' + CT2 MTE 2 "M (Eq. 1) then CE - CT
- IfDA >:2W + Cr+/- MTE]" (Eq. 2) thenCE-CT+A Intialy:
A - i5.00°F (Section 4.13.1) CT - $5F (Table 3) MlME = MTEA=AL (Section 4.1.4.2)
- *4.12'F t
DA - *7.54F (Section 4.1.5) lbus: 4-A2 + CT* + MTE2 1' 2 = *[5.002 + 52 + 4.121'2 OF
^^*8.18°F Equation 1 is satisfied, consequently credit is taken for A beig encompassed by DA.
Page 14 of 31
w 4 RCIC Steam Line Ar~t H vLenortr Ser nt I VYC-462C. Rev. 0 f 4.1.3A CE used InUncertinty Dtermination Based on the results of Section 4.133: r CE - CT
- d5.00F 4.1.4 Measurini & Test Euipment Accuracv (MTE)
From Reference 6.6 (Attachment E), calibration is accomplished with an Omega Digital I,.. Thernometer (or equivent), a Type K Thermocouple and a test heatf. A review of previous calibrations indicates the typical use of an Omnical SA digital thermonmeter (MTIE). From Reference 6.11 (Attachment F), total eror for the Omnical SA is expected to be: i MTE, =*1.005F From Reference 6.17 (Attachment N), standard limits of enror or -aType K T/C (nonspecial) in the application range of O0F to (+)530IF is: MTE2 =i4 0F 4.1A.I MTE Reauirements Per Reference 6.1:
- TE uncertainty is encom by DA
- Total MTE uncaty shall be rated accuracy of the device under test.
Given the relationship: M M*[MTE 2 + M17T] 2 where: 4 MME =A (Liniting) MTAE - :+4eFCype K T/C, Limiting) then it can be seen by inspection dat any MTE, with a totalaccuracy up to and including +30Fsatisfies the 1:1 total MME accury criteria. 4.A42 Implemented MATE In supportof Section 4.1.3.3 and from Section 4.1.A.1, the following is assumned to be representative of PATE used for calitration: tMTE,= *1.005F Page IS of 31
-1 1- .
RCIC Steaun Line Areas High Temperature &epint VYC-462C. Rei. O MTE2 - ".4O0F ?j Consequently, MTEACrUA - +[ 1.002 - 4.OO 2] .. F
-i4.13°F 4.1.5 dDrift(DA)
From VyC.1599 (Attachment H), switches calibrNed per OP 4366 (the scope of tiis calculation) and OP 4322 (Main Stean HELB Detection) met the criteria for pooled data. Te output of VYC1599 (per Sectio 4.2)is a 95% probabilityl95% confidence lvel value, which meets the criteria ofa Class I setpoint as per Reference 6.1. The following data applies to DA:
- Average time interval is 544 days
- DA isl 7.54¢F
- Data is evmnly distirued about zero with 8 slope on the time dependency line equivalent to
<02 % per approximately 550 days showing, consequently, little time dependency.
- The data is normally distributed with a highly peaked naurow distribution.
- The average drift value for this group is -0.008°/ CS; since this value is less than 0.1% CS, bias effects are considered negligible.
Per assumption 2.2.11, extrapolation of DA from a baseline of S44 days to a maximum of 684 days take the form: DA - +/-DA,44 (684/S44)
-E 7.54@F(684/544)U2
-+/-854°F .
4.1.6 Temnerature Effect (ME) Typically, DA accounts for a 20F AT TE during calibration conditions. In this case, TE has the following considerations:
- The measured process parameter Istemperature, for which the device is designed.
- Calibration technique is to preheat the switch (and associated calibration T/C) and use a prefabricated test heater assembly to minimize any external influences and approximate normal operating conditions prior to temperature rmnp-up to setpoint. Consequently, normal TE as an error determinant is considered to be negligible.
TE-0 Page 16 of 31
. i . N. ..
RCIC Stean Line Area HiMgh T -miernaature Setpoint. _
- WYC462C. Rev. 0 4.1.7 Radiation iffect (RE)
Per Referen ce 6.1, normal radiationeffectis ncompassed by DA. RE-0 4.1.8 HuiniditvEffect (HE) t- No bumidit' Veffect isspecified by the vendor. In addition, per Reference 6.1, normal humidity effeit is cueompassed by DA. HEmO 4.2 Test Unctainty ( i -, From Refeee 6.1 for this type of device, and where there are no significant testing condition biases:
- ~'. Initially, ri:[CE + DA 2 J' Substituting:
c, t[5.00°F + SAS4 F2lZ
- *9.82'F Accounting for a single side of interest approach as per Section 2.1.3:
*[9.8rF x 0.85]
&8.347'F To facilitat the calibration process, e, is conservatively rounded (with regad to setpoint development) to:
4 .00°1F 43 Nomal Module Uncertainty (e? In this case, there are no additional terms to those accounted for inthe un-rounded e,
- *834rF, conservatively rounded to:
e - *8AO4F Page 17of31
._ ,+ *o-y;.; s- ,.-
U.,.>t ft-,. z z-, : *!
.e 2 RCIC Steam Line Areas Hi Temoerature Setnoint YC-462C- Rev. O 4.4 Accident Condiiion Uncertainties 4A.1 LOCA Uncertainties (e..
Per Reference 6.7.1, these switches do not mitigate a LOCA and, while they may experience a harsh enviromnent, need not function during a LOCA. A LOCA coincident with a HELB is not considered to be a credible scenario. Consequently 4A.2 1B Uncertainties I- ... Per Reference 6.7.1 Section X-23 (Attachment P) following both the LOCAIHELB simulation
.-: and Humidity/Cycling Test, the specimens (Test Item Nos. 2 and 5) remained withbin the test acceqwncc criteria of +6'F.
Indeed, the post-accident shift were ofmininium magnitude (+2.2°F and -0.2F, respectively). For conervtism, is calculition postulates that the pressur effect, discussed in Assumption 2.2.6, isonly manifested during the accident condition and would have been immeasurable during post-accident testing. 4A2.1 HELB Temperature Effect (T11,m..' Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCA/HELB simulation. In addition, temperature itself is the measured process parameter for switch actuation. Consequently, for the purpose of trip setpoint uncertainties: Tni,- N/A 4A.2.2 HELB Humidity Effect (HE ) Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCAIHLB simulation and hurnidity/cycling. Consequend)b HEmaa - O 4A.23 Overpressure Effect (OP 1a Per Reference 6.7.1 (Attachment G), a HELB can result in an area pressure rise. The worst-case pressure increase is (+)5.1 Psi and results in a (+) bias shift in the setpoint, proportional to the extent of pressurization. From Assumption 22.6: OPHEL - +020°F 4A2A HELB Module Uncertainties (em I Accounting for uncertainties which are negligible or not applicable: Page 18 of31
RCIC Steam Line Areas MAr Ternneatuit Setwoint t VYC462C-Rev-VYC-462C. Rev 0fl RCIC Steam Line Areas High Temneratur Setrioint Substiftting ems - * [5.00F 2 + 2 8ASAF J8 (0.85) + 0o20F G+ 8.55F/4351F 4.43 Seismic Module Uncertainty ( For HELB mitigation channels, em is determined by HELB conditions of overpressure coincident with, or subsequent to seismic effect. From Reference 6.7.1 (Attachment P)I post-seismic effect ranged from -3.11F to +42F. For conservatismn: the post-seismic simulation t .i fiucdonal acceptance criteria of +5F is taken as limiting. f: Initially (- SE =+S.0O"F Accounting for uncertainties introduced by a seismic event follo- red by switch actuation caused by a RCIC turbine steam line HELB: cm *
+[CE 2 + DA2 + SE]U2 + OP I
Substituting: cm k* [5.00°F 2 + S.4AFP + S.0O°F 2 ]m"(0.85) + 0.20°F
' + 9.57F1-937F 4AA Amendix RlStation Blackout Considerations From Section 2.1.6, a multiplier of 035 is applied to the normal module uncertainty to obtain a Class 3 normal uncertainty (e.).From Section 43, the normal module uncertainty (e,) *8.40'F.
Applying the 035 multiplier
- e. -8.40°F
- 035 - *2.94*F However, as CT> e,,, the Cl value of*5?F will be applied.
9 4.5 Setpoint Evaluations 45.1 Custom Technical Snecificadon (CMS) LSP TS - ITLU I However, because AL < TS, the AL becomes the more limiting condition. Therefore: 4.5.1.1 TS.13-79.80.RI.82 (B.C.)) LSP,b' - AL - I TLV I Where: Page 19 of 31
RCIC Steam Line Areas High Temperatue Setpoint VYC-462C. Rev. 0 LSP, ,m 1 lbe Limiting Setpoint TS CTS Table 3.22 Trip Setting s212°F(Not Used) AL = 196F (Table 3) nLU - Total Loop Uncertainty which, in this cases reduces to:
- et= (+e,, is the wost case vector)
Substituting: LSPtsm 196F-8.55F 187AS°F, conservatively rounded to: LSPSM - 187°F 45.12 TS-13-79.S0J1.2 (A) LSPIA= AL - I TLU Where: LSPA- The Limiting Setpoint TS - CTS Table 32.2 Trip Setting S 212°F (Not Used) AL - 200°F (Table 3) TLU Total Loop Uncerainty which, in this cases reduces to:
- eC (+em, is the worst case vector)
Substituting: LSP,,, 200 - 8.55F
= 191A5°F, conserva ly rounded to:
ISPk - 191°F 4.52 Improved Technical Specification /lTS) LSP 2-AL-ITLUI 4.5.2.1 TS13-79,80.81.82 (BsC.D) Where: LSP2, - TheLimiting Setpoint Page 20 of 31
RCLCStearm Line Arei3 MgJh Tempeiature Setooint 'VYC462C-VYC-462C fip-Tv 0 C) h Temserature Sctroint AL - The Analytic Limit TLU - Total Loop Uncetainty which, in this cast reduces to:
- OMi(4t= is the Wonst-Cas vector)
Substituting: LSPMCM - 196F-9.57F'
- 16APF, conservatvely rounded to:
LSP, = 1t60 F 4.52.2 TS4 3-79.S0.81.82 (A) Where: LSPz, - The Limiting Sdtpoint AL The Analytical Limit TLU - Total Loop Uncertainty which, in this case reduces to: i eCM (4eC is the worst-case vector) Substi:ting LSP2,A -20rF-9.57-F
- 190.43VF, conservatively rounded to:
LSP2, - 190°F 4-5.3 Aj~ lix R/Station Blackout Considerations The maximum heatup of the Main Steam Tunnel during this scenario is 174'F. The uncrtainty associa ted with this evaluation (ed) is S°F. For this scenario, the LSP, is: ISP) 174eF + SOF = 179°F LSP 3 = 179 0F I., Page21 of 31
VV'A) . ~ A RCICr Steam T sinp Ariea aith Tanmrwtreik ScRtooint 4.6 Marin Evaluation 4.6.1 Custom Technical Specification i. 4.6.1.1 Nominal Margin (Ma)to Existing Calibration Setoimt (SP) M,°LSP-SP i.. TS-13-79.8O.01,82 (B.C.D)
.~I Substituting:
MM>a= 187°F- 185SF
- 12°F TS- 3-79.8Q081.82 (A)
Substituting: M,, = 191°F- 185F
=+61F 4.6.12 HELB Safety Margin M. to Existing Analytical Limit (AL)
Per Reference 6.18 (Attachment B), the existing AL inside the stam tunnel CIA" switches) is 200°F and outside (B, C & D" switches) is 196F and includes a 6°F allowance for instrument error. Mm existing sepoint from Reference 6.6 is 18°5F. he "normal condition" uncertainty applicable to CTS M2 to existing AL still must consider tie HELB OP effect, therefore em (positive vector) is used. Thus: M AL - [SP + IemB I] TS1 3-79.80.81.82 (B.!) Substituting: M29m - 196°F - [185SF +8.55FJ
=+2A5°F TS-13-79.80.81.82 (A)
Substituting: M2A - 200F - 1185'F +8.550F]
- +6AS4F j sPage 22 of 31 I . . . - . . . . ... ... - . .
RC1C Stcam Line Areas Higzh Temperature Setpoint VY*-462C. Rev. 0 4.6.13 HELB/Seismic Safety Margin nM.) to Existing AL From Section 4A.3 c, (positive vetor) is 12.80 0F. IS-13-79.80.81.82 (B.D) Consequentdr M,w3 = 196-F-[8I5F+ 9.57F1
- +1A43VF TS-13-79.80.31.82 (A)
C~oosequentily MMA 2000F -j185'F + 9.5.F]
+54A3F 4.6.2 Im roved Technical Specifications (ITS)
From References 6.18 (Attachment B) and 622, the current AL is 196°F for rutside the steam thnnel and 200"F inside the steam tunnel. For ITS:
- By inspection, it can be seen that the limiting nominal margin from LSPsw (18611F) to existing SP (IlBSF) is +I-F.
- By inspection, it can be seen that the limiting nominal magin fiom LSPA (190lF) to exsting SP (I85?F) Is +SF.
- Per Reference 6.16 (Attcment M), the original plant design was for an SP which was 200F. From a review of plant areatemperature trends (Attachment G), mximum base temperature is assuned to be 140°F. Since LSPm accounts for the combined ef&Mcts of HELB (as applicable) and seismic effect, no additional safety margin relative to LSPm is require&
4.62.1 Improved Technical Svecification ODeatin Mare;D (M) For an ec of (-)&A"F (non-worst case vector), and a maximun base temperatu of 140-F (TuF ; operating margin is expected to be: MK [LSP - I eKI- TM TS-13-79 80 81.82 (B.C.D) Substituting: M,., = [I86iF - I - 8AFI -140°F
- +37.6°F Page 23 of 31
RCIC Steam Line Areas High Temer2tue Setnoint VYC-462C. Rev. 0 TS-13-79.10.8112 (A) Subsaiting: M, -[1190F- A-84F11 -140°F 8+41 .6F 4.7 Allowable Value (ITS) 4.7.1 Loon Acceytance Value (ACV) For a smgle component loop, the detemnination of ACV (the algebraic sum of each component's as-found tolerancet) is not applicable. 4.72 Allowable Value (AV) From Refernce 6.1: 4.72.1 TS-13-79.80.81.82 (B.C.D) AY - LSP,, + C, Substibtuing: AV], =1 86°F + 8.00°F
- 194°F 4.72.2 TS-13-79.80.81.82 (A)
AV LSP2A + C, Substituting: AVA= 190°F +8.00°F 198°F Page 24 of 31
I i
. . t RCIC Steam Line Areas HghbemFerature Setioint ~Set oitt VYC462C.
VYC-462C. Rev. Rev. 0 0 RCIC Steam Line Areas Hi21 Tcmrerature 4.8 Calibration Tolerances 4.8.1 As-Left Calibration Tolerance (Cfl As developed in Section 4.1.32: Cr ' k 5.00F 4.82 As-Found Calibration Tolerance (AFT) From Reference 6.1: AFT'= As developed in section 42: c, - iS.00F Consequendly AFT = u.00°F Page 25 of 31 I
RC-'TC 'Steam Une Areas High Tempmture SetWint VYC-462C- Rev- R---010 - RCTCSfrani!An Aras Hnh eni~raureSctvintVYC462 5.0 RESULWCONCLUSIONS 5.1 Toal LOOD Uncertaintv Total Loop Uncertainty (111) has been evaluated for the RCIC tuifine steam line HELB detection switches within the context of both Custom and Improved Technical Specifications and the rtsults are presented below: TABLE 6 Total Loop Uncertainty Results, CIL. Interval CISHL TS-HELB r`4WASE1SK1C Refueling Cycle +355FI-8.35OF 49.5rF.9.37'F 52 Setpoint Evaluation For protected areas inside and outside the steam tunnel, results are presented below for the limiting setpoint (LSP), Allowable Value (AV), relevant Margins (M.) and baseline data TABLE 7 Setpolnt Results Description Results (OF) crs _ITS Analytical Limit (ALA) 200 200 Analytical Limit (ALsMD) 196 196 Allowable Value (AVA) N/A 198 Allowable Value (AVma) N/A 194 Technical Specification Limit (TS) 212 1982 (inside)
.1 1942 (outside)
Existing Setpoint' (SP) 185 N/A Lhniting Selpont(LSP1 &) 191 190 Limiting Setpoint ISP,_) 187 186 Recommended Setpoint (SP,) 185 185 Recoanmended Setpoint (SP.,) 185 18S Appendix R/Stabio Blackout Maximum Temperature 174 174 Appendix R/Station Blackout Setpoint LSP, 179 179 rA switches only) Mai LSP to SP (MIA) +6 NWA Margin LSP to SP (M1 1 ) +2 NWA Safety Margin to Existing AL(Ma) . +6A5 N/A Safety Margn to Existing AL(M a)3 +2A5 N/A HELBISEISMIC Safety Margin to Existing AL(M3 )4 . +5.43 NA HELB/SEISMIC Safety Margin to Existing AL(MsmV . . +1.43 N/A Margin AV to AL NIA +2 ITS Operating Marin (MA) .N/A +41.6 ITS Operating Margin (MY)' N/A +37.6 Page 26 of 31
RCIC Steam Line Areas High Temperatre Setpdint *VYC-462C. Rev. 0
- 1. Per OP 4366 Revision 12
- 2. For IT the AV is the IS limit
- 3. From (SP + ca) to AL
- 4. From (SP + %.uc~) to AL S. From (SP, - ej to maximuni normal tenperalure 52.1 TS-13-79.80.81.82 (B.C.D)-Outside Steam Tunnel From the above table it can be seen that to support ITS and the current AL of 196°F the existing setpoint of 185F is acceptable for both CTS and ImS considerations.
52.2 TS-13-79.8.081.82 (A) - Switches Inside the Steam Tunnel The existing 185°F setpoint is acceptable for both the EQ Pogram limit of 200°F, the Technical Specification limit of 212F, and the Appendix R/Station Blackout temperature limit of 174°F.
)3 Granhic Rereentation of Setpoint Data FIGURE I Graphic Representation of Setpoint (CFS)
Technical Specification - 212OF Analytical Limit (inside stm tunnel) _ 200°F Analytical Limit (outside steam tunnel) - 196°F LSPIA _ 191OF LSPU,, 187°F SP2& SPA (Setpoint is retained) - 18?F LSP, - 1790F SBO Main Steam Tunnel Heatup 174°F Normal (MAX) - steam tunnel 140'F I. Calculated for normal conditions (to include OPHEL)
- 2. Existing setpoint per OP 4366, Revision 12
- 3. Not to scale, provides relative position only Page 27 of 31
M RCIC Steam i.ne Areas }wigh Temperature Setpoint VYC-462C, Rev. 0 FIGURE 2 Grapblc Represeatation of Setpolnt (ITS) Analytical Limit (inside stm tunnel) 200°F Analytical Limit (outside steam tunnel) 196F Allowable Value' (AVA) - 19F Allowable Value' (AVD) - 194°F LSP2A - 190°F LSPn 186°F SP2 & SPA (Setpoint is retaed) - 185°F LSP, - 179°F SBO Main Steam Tunnel Heatup 174°F 140°F I.... Nomal *A) - ,temtunnel I. For ITS, the Allowable Value is the m value.
- 2. Not to scale; provides relative position only.
5A Calibraton Cnteria In order to support and implement the results of this calculation, the temperature switches are to be calibrated accordig to the following table: TABLE38 Caibration Attributes Desaiption Value Units Setpolnt (CTS) Inside steam tunnel 185 OF Outside steam tWWel 185 OF Setpoint (ITS) Inside steam tunnel 185 Outside steam tunnel 185 OF As-Left Tolerance *5 As-Found Tolerance _ OF 5.5 MeasWriin & Test EMLinment Reauirements Testing is accomplished with the following equipmnen
- Monitoring thermocouple (Type K) (Installed)
- TIC Reader (Digital Thermometer)
I -
- Heat source (rest Heater)
- Digital Multimeter
- Variac Page 28 of 31
RCIC7 Steei Line Areas 7Hifh lTem~hrature Setpoint VVrl-A,<')r V h uJ Nigh Temnerature Setnoint fl rsse. RC'W team TJnt Areaq VVr'Akr w s wvcw. T1.U For calculation purposes, only the T/C and Reader have relevant associated uncertainties, developed in detail in Section 4.1 A. Since the T/C is an installed sensor calculation recommended MTE reduces to the T/C Reader. TABLE 9 Recommended M&TE Description Required Accuracy Actual Accuracy Reference OmegaOmnical 4A & M *3°F +1.005°F 6.11 Omega CL-SO5A *3`F *1 .O11 5.6 Recommendations 5.6.1 Subsequent to this calculation's approval, revise FSAR Table 732 as per Attachment K. 5.62 In order to support Analytical Limits of 200°F and 196¢F, revise OP 4366 in accordance with Table 8 and Table 9. 5.6.3 Ensure that a calibration tracking system exists to -valuate consequences of a calibration interial greater than 684 days. [Note Tbere are no plas to extend the calibration interval beyond 684-days]. 5.6A Revise the minor FSAR Figure 73-Sb discrepancy regarding PCIRCIC temperature switch sets. The following discussion relates to RCIC; HPCI is comparable. There are four sets of four sensors, each set providing HELB detection protection to specific plant are (one set covers the stam tunnel and three sels cover various zones of the Reactor Building.) This Is shown in block digam form in FSAR Figure 73-Sb. The block diagram section regarding'the Reactor Building sensor sets refers parenthetically to "typical of four located outside steam tunnel." This should be "typical of three..." 5.6.5 Add VYC-462C to the List of References In OP-4366. 5.6.6 Evaluate the acceptability of an analysis limit that is less than the Technical Specification Limit for an increasing trip setpoint 5.6.7 Revise Section 7.5.3 of the EQ manual, various places, which indicates 200F as the isolation trip setting. TIhs should be the nominal setpoint of 196F as implemented by the HELB analysis. The 200°F applies to the steam tunnel only. 5.6.8 Close PORC follow itern PF19604 101 (Attachment R). 5.7 VYDEP-15 Criteria VYDEP-IS requires the impact to plant programs, procedures and licensing and design documents are considered. This calculation has been reviewed for impact considerations. To fully satisfy VYDEP-IS requirements, this calculation undergoes a review of all departments and programs that could be impacted by the results and conclusions. Page 29 of 31
RCIC Steam Line Areas Hih Temnerature Setpcint VYC-462C. Rev. 0 The following has been considered and is either addressed in this analysis or via the intrdpartmental review process:
- FSAR changes
- Technical Specifications (custc. and improved Technical Specifications) 0 P rocedue
- Tehnical programs
- Prints
- Related Design Basis Calculations (ilp/output)
- Design Basis Documents Based on the above, all impact considerations of VYDEP-IS ae addressed.
5.8 Evaluation of Existing Sctoint The temperature switches locatd inside and outside the steam tnnel are acceptable for the full sundeillance interval with a setpoint of 18S5F. 6.0 RBJCES 6.1 "Instrunent Uncertanty and Setpoint Design Guide," Vermont Yankee, Revision 0. 62 WE-103, 'Engineering Calculations and Analyses," Revision 17. 63 Vermont Yankee Final Safety Analysis Report. Section 73A. 6A Vermont Yankee Technical Specifications, througb Amendment 150. 6.5 Vermont Yankee Project Proedure VYDEP-15, "Clculaions," Revision 2. 6.6 OP 4366, URCIC Steam and Space High Temperature Functional/Calibration Test," Revision 12. 6.7 Vermont Yankee Environmental Qualification Program Manual, Revision 36. 6.7.1 QDR 9A, Revision I. 6.7.2 EQDI 95-55, -Draft EQ Manual Revision." 6.8 VYEM 002% "Instructions for Patel Tempaature Switches," Revision 0. 6.9 "Selected Definitions and Clarifications Associated with the Vermont Yankee Technical Specification." 6.10 VYC.1599,"Drif Calculation for Fenwal Temp SWModels 01-170020-090 and 01-170230-090," Revision 1. 6.11 VYC-1758, "Measuring and Test Equipment Uncertainties Calculation," Revision 0. 6.12 Memo, Hengerle to File, "Improved Setpoint Program/CTS vs ITS Setpoint Evaluation," VYI 37/97, dated Aprnl 25, 1997. Page 30 of 31
RCIC Steam Line Areas High Temnerature SetPoint VYC-462C. Rev. 0 6.13 Memo, Hlengerle to Distridtion, "Application of Cl, CE and A for Single Point Devices," VY 92/97, Revision 1,dated June26, 1998. 6.14 MPAC. 6.15 VYC-462, "Feawall (sic) Temperature Switch Loop Accuracy Review," Revision 2. 6.16 'Instrument Data Sbeets" GE Drawing 225A5600, Sheet 98, Revision 0. 6.17 "Nuclear Power Reactor Instrumentation Systems Handbook, Volume 1, Joseph Harrer and James Beckierly. 6.18 NED Analrsis Matrix, daed January 21, 1998. 6.19 Plant Drawings: 6.19.1 Flow Diagram, RCIC System, G-191 174, Sb 1, Revision 33. 6.192 CWD-1 179, "RCIC Logic System," Revision 15. 6.193 CWD-i 180, "RCIC Logic System," Revision 16. 6.19.4 CWD-748, "Steam Leak Detection System," Revision S. 6.20 VYC-1347 Revision 0, 'Main Steam Tunnel Heatup Calculatio" 6.21 Safety Class Woridbeet [for RCIC temperature switches dated 10-20.98] 622 Memo VYE 98214, GJ. Hengerle/E. Goodwin to RT. Vibert, "Assessment of VYC-462AC & D TempaUreLimiOctber5, 1998. 7.0 ATTACHMENTS Attachment A, Loop Block Diagram Attachment B, NED Analysis Matrix Excerpt Attcment C, MPAC Data Excerpt Attachment D, Vendor Data, VYEM 0029 Excerpt Attachment E, Calibtion Data, OP 4358 Excerpt Attachment F, MTE Accuracies, WC-1758 Excerpt Attachment G, EQ Manual and QDR Excerpt Attachment H, Analyzed Drift Data, VYC-1599Excerpt Attachment 1,CTS Data Attachment 1, FSAR Data Attachment K, FSAR Table 732 Proposed Markup Attachment L VY Project Memorandum WI 37/97 andVYI 92/97 Attachment M, GE Instrument Data Sheets Attachment N, Type K.T/C Accuracies, Reference 7 Excerpt Attachment 0, WE-103 Review Sheets and Associated Interdisciplinary Reviews. Attachment P, Additional QDR Data Attachment Q. Telecon Record with VYE&C Attachment R, Procedure Review PORC Memorandum, May 20,1996 Attachment S. Memo VYE 98/214 and Safety Class Worksheet dated 9-29-98 Page 31 of 31
ATTACHMENT 0 VYC-462C REV 0 PAGE 1 OF 6 CALCUIATONIANALYSIS REVIEW CALCUlATION NO. VYC462C REVISION NO. 0 bmmme , , . i. _o
,,.,,,_-,-Acezw" *,_,i~vokb gIdsi VO -ezfc Ad o Ah waibig -d RcbcmCD_ Ae 03Quarmsimkof sqa.
CO=MbComt a XW FOMcWE.3-3 ItaVhi 5 I
All VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION: VYC462C Revision 0 7- 7T 0 WC, 462C Revlsisoa has been prpared and independently reviwed. The Departants impacted by this ftlbtion are raqested to review the results of ths calculation, comoo with the rdsls and/or ocien s, and document the depaament's aceptanc prior lto the auation b igapproved
- 1. is calailation evalutes the uwcertaty & setpoint fr RCIC L Hh Temer pJL Deecgon).
- 2. Calulation Onen Items: AP40029 to be Assigned
- 21. Nonwe1S
- 3. Pe ment w - co the Setpoit P anamge (G. Heneet if not in agreeent with the enhkit ttt~mnts.
3.1. Vermont Ynkee E&C 3.1 Procedure OP366Re on 12 will recire the following (based on Custom TeclmlcoSpecadbw
- 'stmdardsurveilancecycle):
- 1. Add the following inthe c discussion:
a Limiting Setpoint 7'S-13-7.9A-DIOA-D/81,-D/82A-D 187 T
- b. As Found vaues 7413-79A-D/80A-D/81A-D/82Wo-D +/-1! PF
- c. Revise Head to refecm b
- d. InsrAtthe folowing&TErequirements:*
Omeg Omnic 4A, SA, or CILSOSA, or T/C reader
- 2. In the bodY of the procedure and the daa sheet revise as follows:
a CalibrationTolerance From To M13-79A-Wi80A-D181A-D/82A-D 4 eF t eF
- b. Thp SepoInt From To 2S-13-79A-D18OA-D/8lA-48U-D 15-F 185 'F
- c. Reavisecaltioa datatorefketbeadcotioa of:-f Page CZ of 4
'Vermnot Yankee Setpont Control Progrm A77. 0. .
tdeartmentar Review ofCalculaionC Revsion 0
- d. an9ert.. calibrationforall analog instruments: NA
,40I,ta - Rontm Od _
14'WD j4*SIDl : V ID) :ez mDl Epto LDI O 04d Oduthw PAw Oug ° _ Ouqx 25% MA 50% mA. V 75% MA iOO% mA L 3.1b. The following commutkeunendations apply.
- 1. fJ cwdIibvehg M 3.2. Vrmi at Yankee Reactor Engsmeering Concu 3.2... None Sign&&_ Z z 7~ St/
Vermont YikeRERpesnatv 3.3. Vermont Yaikee Operations
°c4 jJit6dr.'bs erwS fhe mmum acceptab setpoint to 196 F in lieu ofthe 212 F presently allowed by the Vermont Yankee Technical Specifications. An ER has been geneWSd thissuE. /7 Sign &Date / _ / _ _ _ _
Veimont Yatkee Ooerations Revremti 3A. Vermont Yankee Systems Manager Con CenX cor 3A.L Thi analysis supports th design basesforthe RCC Sys. G d Sign& Date A" / A irYiame tysfm Eqngf Revenaim 3.S. YNSDNuclearingtIag
. ' Comments 3.5a. Custom Technical Specifications
- 1. Analytical Limit used in setpoint determination: 196eF Fs_
- 2. Potential acidet trip (MMCA): NA _____
- 3. Poential accidet tip (HELB): 196°F FST 3.5.b. mproved Tbdiical Specifications
- 1. Analytical 16lt used in setpoint deterination : 196- F E
- 2. Potential accident trip (LOCA): FNA g
- 3. Potential accdent trip QIELB): ' 196* F a See Section 3.1 and oinment I (2 00c -J "d & Date r _ A - ' __ f v W f - -
l A'k9Af
- ^
I 0 YNSD NED Representative Page 3 of 6
- Vermont Yankee Scipoint C~trol Prgrwb..
*In* rdehartmna ReviewofCakulation VYC-462C RevisionQ0 A77 C0 3.6. Vermont Yankee DBD Manager Yes No 3.6.a. Tlh RCIC DBD -hould reference this analysis.
The DBD Ls complete (an Ap28 to follow) Ibe DBD is not cempletc. incoipate refauacc to this analysis as approriate.`14 . Sign & Date - -
, /00-- r r 4SP ProgramvMAger 3.7. Vennont Yankee Licensing Impact Yes No 3.7.L FSAR Cmaes (APMo to follow) Table 7.3.2 . C0 3.7.b. Other impact ce Jiesing bai= 01 2 The CThasa LiWitO f]2'F. The fAbycd Limit Is 196'F. It is sotaccltae to have an AL <
C7ar td i~jiow the Lbnmsenaseoint to be above 196 F (oautrde the onai 1bnlts). Ether the NED ansbe to be rveiedtoswe a value f2212 'For the ClS nlt needs to be lowered to 196F.Ai ER Am been gaeto os ths cond A . aPoozg s f "'V S.'YVM SJC Man nrs 70 ,J#7 zr~
* ~~~Sign &Dae g d¢
- ISP F~gamMiae 3.8. Veamont Yankee 1; I~aae Yes No 3.8.a. hanalysis provides an input to the ITS. An Allowable Valuc applies. a n Allowable Value -1E (o0rstb S;Z7 )
3.8.b. ianalysis provides an ipUt toTcdmical Requirments ManuaL 0 - Inemporateas qpqxi . __ / Sign & Date Conu 3.9.a Impact asessmcntfrocommend in: NA E Sip& Date 4Y I jb .7fP ISP P16gram angers A zbJ P &fn YW. 4.1. Concurs with above. 4.2. IReview form (capysteps I rugh 3) inoporated Er ino Calcatiaz . 4.3. Calculaiohasbeena roved. .. A Twovedon ' 4.4. AP-0028 commitments have been assigned and forwarded for incotpo into the Commitment Tracking System. ion Sign & Date .
-L I //-9-9Y' ISIfProgran Manager Page 4 of 6c IV- , .... I' 1 . -, - . , . - - . ,.
* .. VVermont Yankee Setoint Control Pnoam ,4A7C
*
- InW4;xrtinental ReviewofCaciation VYC42C itceision O
- 5. Post-Approval Requirernents
- a. E&C (perform as appvpriaft):
- .
- Initiate AP0022 Selpoint Change Request APDO28 VYCO462CRO-01 . .
- Update MPAC
- Revise calibration/functionaltlogic test procedure
- Inform the follwing after changes are implei.mted:
- Setpoint Coordinator
- Setpoint Program Manager
- Training (notified via AP402 if initiated)
- Operations (notified via AP-0022 if initiated)
- t. - Design Engineering lri, b. Setpoint Program Manager: Update Program Manual APD028 VYC0462CRO-02 (after itep S.a).
s
- c. Sctpoint Coordinator. Update Setpoint Data Base AP0028 VYCO462CRO-03 (after step 5 a)
- d. Design Eng&ecring:.Initiate FSAR/DBD changes, AP028. VYCO462CRO-04 r,
.. as asrvpriate (if DBD has been completed Conmments: .I I 1) An ER has been generated to address the condition where AL<CTS II I
- e. Design Engineering: Investigate need to revise EQ AP0028 WC0462CRO-05 roam Manual tperture lInits (2000 F applies inside steam tunnel, 196&F applies outside steam tunnel) for HPCI, RCIC & MS small break HELs.
Page _5 of _
. . :- . 7, - : , - :I-'. - -, : ., .-. -
SY-STEM ENGR13G RENEWV FORM Ho,=-- - _.I 1/a/z -> 2C-Xof&, a_. 2O r -k- P.. ocuoment C - 7u AI C
-cr DRSoiont2 46$.1Resolution 5-*
!Comment i ;4>-..
Ado G,tS I q - - I l-I V I,. fK I-Ii: - w r>= , Z 4 - , fKw,2 2 b , .1/IloA/o Og AeviewerSideiii Date Document O~riginator Date
/
Reviewer Signature Date
VY CALCULAON CHANGE NOTICE (CCN) VI'C-4& C - ccj -p CCN Number. 01 Calculation Number VYC-462C Rrv. No. O % 243lO Calculation
Title:
Reactor Core Isolation Cooling Steam Line Areas Hiah Teeratue Sctpoint VYDC&MVm'pec. NoJ ofter Safety EvaluationNumber: N/A Superseded Doans N/A Reason for Cang: Provide a basis for increase in Technical Specification Surveillance Interval from Monthly to Quarterly. Description of Chngc:
- 1. Evaluate CIS Quarterly testing interval on calculation outputs.
- 2. Address comitnent - issues.
SEE PAGE 4 FOR DETAILS Technical Justification for Change: Technical Specification proposed change No. 217 requests surveillance test intemi change from monthly to quarterly. Conclsioa For Crs Quarterly.
- 1. Existing setpont and umcertainties supports Quarterly fimctional testing of logic.
- 2. SetpoiAt, calibration attributes remain unchanged.
SEE PAGE 5 FOR ADDITONAL CONCLUSIONS P .aedBylat Ihediscipline Review By/Dat Inldepdent Review By/Date Approved By/Date I A Ipv 242-7 4WW o1kO7;0 A
. 3;16 LW1isn& -Sul Alkews Instalionverification A _va A flz/o !)
S igne I Note; VYAPF 0017.07 should be included immediatly following tis form VYAPF 0017.08 (Sanple) AP 0017 Rev. S Page I of I DI #99-381 r
VY CALCULATION DATABASE INPUT FORM JYC. - 46 7 C - CC.A4- o1D.
'PI Zi f Y72 p VYC-462C-CCN-01 0 N/A N/A 'q 2*3It VY Calculation/CCN Number Revision Number Vendor Calculation Number PRevision Number Vendor Name: N/A PONuniber: N/A Calculation Type (Originating Depaziment): VY Design Engineering (EI&C)
Implementation Required? csiNo % 2-Fla- [V., Asset/Equipment ID Number(s): Various Asset/System ID Number(s): 13 Keywords: No New Keywords General References Reference R Relerence Title (including Rev. No. and Date, if applicable) (See App. A. Section 3.1.7 for Guidance) Critical Reference( ) 1 Technical Specification Proposed Change #217 Design Input Documents - The following documents provide design input to this calculation. Document # Document Title (including Rev. No. and Date, if applicable) Critical Reference () No New Design Input Documents Design Output Documents - This calculation provides output to the following documents. Document Documet Title CQitical Refcrcnce(L
'No New Design Output Documents I I.
- 1. 4 4- 1 L 4 VYAPF 0017.07 (Sample)
AP 0017 Rev. 5 Page I of I
Page ..L. of Page I of I VY CALCULATION OPEN ITEM LIST Calculation Number VYC462C Revision Number 0 CCN Number: 01 Open Item Resolution Method of 01 Tracking or Date Closed L 2h 11S100 - __ T -,_-,
.oyf -SP bit C. Ck r IIwF f8°s XP.5 Lt; Th-I3-79 1 A, wk,1R 4 82r 4bf[4o.I9 0 F~. m41e-,
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'VYCMCULATIONSUIET
- Calation Number VyC 464-Z C Revision Number. O CCN Number: o4- Page 4 of w
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- 46zAg- cc.- A-o (D C.W2Z 1
RCIC Strm Line Areas HMh Temnerature Sewoim WC~4C .O 1.0 fM1OBE l.1 7bisaeklOi hi perhid insppt of the Vasw Yautm S lrt mad ho do "owing
- l. 1Do ai 0ioop f tmioand thebci htc sisn adj Imardccin pobitsussod with U~s fAmcdosL
- 2. Defterize tdo Donal sad total loopmccrubly and verif cosatcy with do design beaL I
- 3. Cacu the liiing sdpoit and Werdo dwdon poinm
- 4. Bvitaha die adequacy cfdhe exidsfti aepincaliraion linits nd procccdora decisin poloI.
- 5. Pvie aseft and at-found okmasc for am Is calibratio h proafeds demi lgeastcrn iwTess dmcayoksIC Bi* p , ; _qiMt~X s
- 6. VYDEP-15 ftquke that applicable operating piocedzure, aim raomes, 92ard, off-normal and ezmgaacy operaigg 1voce I ps be inchided Intbe e~iausiona..This requicameat is 6Ct, accsaled by doe kftordlciplmayVJCreview
&-which &up~wste W1-103 revimw peoec and 10JCXc -14.
s calooaion appie to die Reactor Com lsobgoo C~ofg (RCIQ Slum line Ames Hig EseW Una bak (HEL) ddetion ixwkchs in db. RMC System. Ib. apd aapoenutsobe s , ReL TAG Pou-ber ________ Ieaa TA____ _tCWD F _-_____ Mi _ fi TS139A -17Z30090 1179,1310 6.7, TS-1340A E1252'6 Swih.i 6.14 7Sl3lS ,A TS-13-g 6I TS-13-799 RxBM&EL TeMPMe Fcwa 01-170230-90 1179, 11ltO 6.7, TS-1340B 213'9" Swit 6.14 TS-1341B TS-1342B 6A 71-13-79C RxBU4B. Tmpe*tu c Fenwal 01-170230.090 1179,1120 6.7, TS-13-C 213'90 Switch 6.14 TS-13SIC 7S-1342C .__ 6A, TS-13-79D Rx Bldg. El. T
*r- MM Fimal 01-170230490 1179,110 6.7. TS-13-SOD 213'r9 Switcb 6.14 TS-1341D RCtC Room TS-1342D SscA A-
=
ie p W -4F C5 5se L e
Npc -4Oz CCA L R RCIC RStm lne Awt HiMh Tefmntiwe SRm'it _VY-42C. Rcv. O $- 4510 At 2.IA Calibion EfefCos Per the Design Gide, CE is tyialy taken as ;e su ofdbcvaldr's Ried Aceacy (RA) aid 6e A*LAf Caliaton Tolerane (C Based an ti nb saiples. used to deinn DA (count - 199a per VYC-1599, be 4), a+/-twil be avoied to ddrnine lifredtc be tan for RA being Passed by DA. Test meDology is described i. detal hinReference 613. In a If DA [ + ClT +vendaos mated drif + W +I, tCE -Cr t
- IfDAk[R+C +v+do'eedif+MTE ,
thI CE-CS+A who:e cr - Preset Caibration Tolcn DA -Analzed Drift fianS VYC-199 RA - Vendors Rated Accuracy KmT - the Measwuig& Test Eqtdpm used in calibration and when the vendors raed drift isvalued attO because th vendor has no plffisbed drift 2.1.5 g g g Thesigp cowenloa used in te Design Goide is based an the effect ofinceutani c so tm u (or locP's)opaa siaL Forftistp ofd-vie,w e diereIs w :1 lnputfsigon t telaionship, te efect ofmicrtm am malfwed as a shift in b teokzt away fnxu ite Ieal value. Mids r schhna sipn convention vdhli s t.t rverse ofdatubid Is geneically deftie In te Design Guie 2.1.6 C 3Assntent This alsis Wi dctesaim t .95W95%(A 2.13)nccltY aa to,&e ams I sepoint Appendi R/St Blackout consderafios do not reqefre th nme Ine of rigor mid cm be evaluated as a Clas 3 aetoobl (95W75, single sided). In accordac wih tho Design Guide. the Class I uncertinty W an be coervertedtoaaass 3 uncestainty (c,%). 1lrow the design guie (mrcmrnc 6.1. Appendbx Z Table 1), a maliplior is deserwuzmd as follws 0.6811 g6 - 0.35 Appendix R/Statlo Blackout support is a MM fimcdon.Tlerefot, accidczt pwneters do not aPPly COO Icci4-3. O z/lIff X45e,,Jr 2Z (.Se g%A$+ "Co) Pape9 of 31 4
W CALCULATION SHEET VvC._ 4c4or - oCC14_& Calcuation Number: -iIfC -4G Revision Number o CCN Number: c> L Page 8 of 7i2 S 2f00oo z1 C-ceoc, iC-;v.j; . T L{i2f .1. v c 4e+-i;oLesA-( n@Fsel cl. - d1o. z-l TS Tsl M f 7 4Z C (Atc 3) SV 01gc 4S 0>-0. 46,14cvits~
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- 0 VYAPF 0017.03 AP7017 Rev. 5
,VIC - 46&=r - c-ct - 0 A RCIC Stm Li T VYC-462C. Rev. 0 4 3rm 2.29 Per Refacre 6.1, notuncatty isadagabhst erlays,o oed bysdeices 22.10 Barn &e desigp bo of diae devic (sce eFSAR 7das7U 7 and 733) th v a frcts atof proc M _aect (PM) are KeglIc.
2+/-11 PeCrS CM scecified calibration hftrval is "ch refueling onhp?'Per Referce 6.9, dbs bntrva! Is typially bounded by ISIot -hs and s take as Io-iz (by dohde ft MMS~11 not calend days).~ To allow for a rdfueling cycl extnded tobyond a mominal 18 mais, tis cknlacaz will base eapobted DA, amaxi ftmal af 684 days (using dme e " mlof eperopetaf cyce +25% as a convence). If de calitatim kftrna caeds, fwtzmm reason, bryond 684 cdcad y*- im evakmbmo to detemmme ffie Interval mincrs eftect an saphit RBQUIRED I CCA.
*2.212 PerVYC-1599,Sect 5.4, A nalyzediftdatfaortesdevice(peProcess OP4322 0)t%
and OP 4366) dcatd lido time dqendcacy. Cnseqly, his assemed t RSS exia /t44 of caxrt= Interl is qppreitcf
.4
. ( 1bS Jee &i 05os]T, J ~
Page II of 31 i
x jC--4GzC. - cce4 - RCIC Steam Line Are4 HiiieatD Sctoint VYC42C H. 614to b.IE,.-[I4LOS2 +4J^OjIJ
-14.13T 4.1.S Ady dM (iM Fmom VYC-1599 (Afadment H switches aolibed pa OP 4366 (&escape olis cakuodin) and 0? 4322 (Kan Stea= HEXW Deeccdin met dh cituria fiorpooWe dats. The osqmz of VYC-1599 (per Sec 42)ls a9 probdiy/% codmenelvevalwhd -e, the citesOfaaaCas 1setpoixasperRrdrence6.1.be f lowing dappliesto DA:
a Avenge time IWmil 155S44 days
- imdsfi734Ft
- D is eveny dbsied about zro wit a, slope an the *mdepeneocyi liaeeqivaleatto 4.2 % per y 550 days swwiz coseqey, riale lime dependny.
- Mm dm s tay disubuied with a highly pealed imvw ditmfiam
- The xvage drift vahl this gWopsb 4.00% CS; sne bi value is ks ga 01% CS.
bias effes we conkdlerd negi40W Pcr amptioe 22.11. capoblaion of DA fium a baseline of 544 days to a aof 64.
'.'+/-DA 4 4(6UJS44)bt r ca-3 44 in+/--7.UT(6S4541S)w
-*DA4.
?,c 1UFA 4.1.6 Tcn.).Eff.dll.l A5 lplly, PA accomiab for a2OF ATTE dxb*g c _ cniton In lbw E ffi 4aise, followincosidation:
- Mbm oredp c m p for edeice idese
- Ca<hon t Isto prehest to xwich (and amciaed calbwa TC) nd kdmqu use a pretcated tbesterssrably to minimz anye l i es d a~ppdmsf norma operatig Condos pnorto _c pertore.rpt sipo 1t conspeenly, traw TE as aD a 'xetermiim is consired tobe nebible.
lE -0 Pnge 16of31
. ---. . , . - -.-. Nunn---... --- .-
. VIc. - 4 c - c-cA -o A, I
?X62I it2 of -W MC §iem Line Artur ffleT;SM ratur Setvont WCree 4zt qim -
4.1.7 dibti= EffMO (RU Pier Refterace, 6.1, morma nidiation effect I emomziassed by DA. RE-O 4.1.8 HumdMfetl No hb idity effec i specified by ft vendor. In addlzioa, per Rdarcoce &1,noona' hanidky effect is ed by DA. HE o 42 TestUtc"iVw Finom Referenc 6.1 for tis;type of device and where thn am no uA tcsin conditba c.
*9t+0- 6A5&
Accoingforamsig kside of xmapproa asperSection2.13: l v /t ej-A9.S2'F x 0.35] 8 *S.347F To fncifi1eI he a i pocc s ed (wh r dta sctp dc p Ic e,-8.00"F 43 (l- .'M1.t In dtiscase there am no rMtnal tam so thoe fco In tm-remunded ec cu"i
- &S.347F. convseva wonded ter e.- *.40"F Page 17of31
,qfC.- 4(,t - c.c.0 _ C)
.. ?&I.S - Z o+ 1,S ..
f RC3C qtmm T ie Arens Moh Temnerstm, Setnint
- V-YcC46C Rm!. O' 214a Substkut
*: [500F + 34S1 TV (0.85) + 0.20F
- + "SSF/483S*F 4.43 Seisack Mo& Unceraint (y For HELD mitim damesan is detumksd by HEZ coaditions ofo-xssm twX, ormbsequen to scsio c leecL Fkom Rdercnc 6.7.1 (Auachmem F pw-eism effect zneed fivm -3.1F to function c w of*
*J4P. For cmeralisa, the post-sdismic uiwis I
EFIs bkuas imrnin&$ ( hxkhfly.- ($4 nsTs- ii-'. II SE -*S.OOOJF A gf by aRCIC ttubinomam he HELD: introduced by a ismnk event fa~wod by swic actu~mcocsed II ems
- CE +DA'+ sE+ OP e.- [S.wC 2+ sAP+s Vj (0.5) + 020-F
- + 97F1-937F 4AA dkRamM IMI Frm Secti2.16,amuM of035 isapIiDotbenogmal mdukeu tytoo oa Cbs 3 mc uacutah* (c, From Section 4.3, the Dwmu mDel. =city (e.3 *&A0-F.
Apying The 0.35 muhltm-w e, 3 +*L40 *O3M:t*2.94' A Howev, Cr > ea,Ihe Cr vate of *5F win be applied 4.5 SCUVowtEv 4.5.1 Cstom Tech"l Spedfi (Cm LSP - TS-ITLUI Howcver, because AL < 1S, tde AL becomes the nore lmiting Condo. efre: 4.5.1.1 LS79D-0. A1.82 (B.CD) LSPzm-AL- ITslU Page 19 of 31
. . .. . . . i .. . . . . . . . : , . ;' .- . ' ; ;.. -A .:---@ -- -- ;- ~ - . r; . . - l vtic.4Gz.- cc,4 -o VY CALCULATION SHEET Calculation Number: -J'fc - 4162.C- Revision Number. o CCN Nuniber . Page A ) of 49frZ
;5 FtvFuSD;; ptt ¶oG;$C_ sctise., c,. Ct Va&-
(75trs\1 (, \1;~~te ]r4 ;vet~ 4; 4ke-;tego-eS^t 4m fe t r, resuL O4-eas C a-§6 S VYAPF 0017.03 AP 0017 Rev. 5
4_- S _ J
,5'_.'.S-*-. ; ' - s . . . . . . . . . . . . . . . . . . . . . . . . .. .. .. ... ..... ;C_...... . . J
_ __+
;',,.='_.:Ss
- J~~~~r6~-
-CJ-o -Y-GZ x~~~~~
RaC Stiam Lute Am High Tez n&de Setpomt .XC- . 1kv. 0 s 4DM 46.I1.3 e&tic Safety MMrvi 5L.ji So ELx s Sccdou,4A.3 ain (poskiv vecto) P1-79ELSJ2~43 Proa se ICA-&. cA - Mm - 196-F -[1IMF +9.5rF
-+1A3F MS-13-79AXSI . (
MM., 20D -[1sS*F + 9*57eF
-+S.43*F 4.62 JMr8veA Tcdmical SpeciSicado 1 FMRoai ~fwraac6.1 (MAsdamxutB) and 6.2,6 thev pit ~AL is19wfor utside We seM tumd and200F sid 1be ft t u For ITS:
ngSP(ISM ) Ii+1'.
*By Insetion, fmbe ce that thec linngominial~s marti Sro 15P,,(I9O03 o vistiog SP 113S').+n
- PIRcavoce 6.16 (AttAch thM),e oga plamt design vW 1hr MSpW Wu 2007. Frow arview pln ae= tmpcras umn (Auadma GI Mahn= bm tcipc~m Isatand to be 140l. Slx LcPm a=oraf fwort cemd cm iHELD (as applab) an meaic .ffct,no mikoa saey mgn reae to LS~ brEpse 4.62.1 hwv td For aen of()&4F nOm-wot c ef e b e o 140'F (F" opemaiog mu expeisd to be:
M4 ujLSP- ItwiJ-TM M.,-[IS6"F- l -+43F7I-l46F
- +37.6eF Page23 of 31
jr V'Yc. - 4GZC. - cc - ot-J ,
.?o VsYC 46 .0- C .-.
RCIC Rtmzm Line Area Hikh T aetiire Setrdint *_ - YCs462C~cvL9 - 5.2 T1379iOJU2 (BC.DI-OutsideSt Td Fr thoveube itc bes tthastto pmpTflSiU r AL o(f96'F eidstin wetoint of I ZTF is accepWtab for both CT'S aid nS cowidaurmti. 5.22 TS-137920212 (A) -Swch Imide te Stm TuMmle TIe csist WP utpoid is acceptable for both tbc EQ Pzpm lifnk o90F, lh Tcd l Specificatclimtof212"FandtheAppendi 'StiaBlakout znqmatorc limk of 1740F. 53 I I FIGURE I GraphlcRiwreseataio.oSetpat (CMS Spedfication Technic.! Slk3md Teciial 212'F 212*F i 20DOP
!rUA4J&~ Lmt L= £-.U
- A -~L.--wI v~ ~.
34=~ ftm4J ItWF 19611 I' 191OF LSPhAo 13?F ICA-Wi' LSP, 179F r1f:511i ISBO uixSamdH 174"T I"Izr/0 14W
- 1. Cacubatd for moiml coodW= (to incld OPE)
- 2. Exig-etpo perc0'436 ision12
- 3. to scae, FOTdesrreu positi= dy Pap 27 of 31
I - - .. . .... .-- - ... , . ...... . V-r 79 I 1RCrCrqnt Uine Area. Hih Tmnimef etinit- VYC-46M PmRv.O +2/iJ0 FIGURE 2 Graphic !eprm~emtie ofSetpain (Im Asmi deae - 21WF E Owfmfml (my - 196T Abbow (AVA) dVaec 19W-Aflow~e VahJ(AVca~) -X45eVCA - 194"OF LSP2A - 190DP SSh - IWMF SI C4'-,- 1,- 179F 12fil4ft SDOWmSmT~mdep - F 9z /q~lb X t- 140.F
- 1. For US, Oae Af"e Vahm bc th vuim
- 2. )4ctto scair,E.Ovle Utlah" posadm only.
be wsopm lmkWt runh ofthis la e tuopswlure swildchs Ing to he calkatd aCcodift~ofthe wfolloingrI ICC#4-L I CCA-L t5Cees ht-*- Testing is acmphedwh dw folowin eqhlpm I4'..f-tf2t/fff
' M Codog 6=hew Cryp$e K) Qastafl a = wx 1e;&rmg nCkr)
- be So= Crest leat) 2/3k
- DWW Muldetr
- Vrc i
Page28 of 31 I
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;t;(rhb VYAPF 0017.03 AP 0017 Rev. 5
Memorandum fiJYC -4CZc - cc.. - o TO: James Allen FROM: Mark Mcainley C 4Q jjr RE: Commitment VYC.0462CR0O03 DATE: December 23, 1999
- Jim, The Setpoint Database has been updated per Cormmitinnt VYC-0462CRO003. Attached are the printed forms from the Database for the components listed by the commitment. The following discrepancies were noted during review:
EMPAC:
- The following EMPAC equipment should have applicable calculation added to EMPAC
References:
TS-13-79A-D/8OA-DI8lA-D/82A-D: (VYC-462C) This Item has been addressed with submittal of an EMPAC Equipment Change Form.
- The EMPAC model number for the identified instruments needs to be corrected from 01-170230-09 to 01-170230490.
This Item has been addressed with submtittal of an EMPAC Equipment Change Form. Surveillance / Calibration Procedure: OP 4366 (Revision 15)
- Surveillance Procedure identifies an As-Found Tolerance of + 11 Deg. F. The correct As-Found Tolerance should be d 8 Deg. F.
- The VYC Limiting Seipoint is identified as 187 Deg. F for all identified switches. This is correct for the BCs and D switches. However, the LSp for the A switches is 191 Deg. F.
PP 7007, Interdepartmental Review Forrm
- Section 3.1.a (l.a) specifies to add the LSp value of 187 Deg. F for all switches to the surveillance procedure. The LSp associated with the WAt switches should be 191 Deg. F.
- Section 3.1.a (L.b) specifies to add the As-Found value of
- 11 Deg. F to the surveillance procedure.
The correct As-Found value should be
- 8 Deg. F.
Calculation: VYC-462C (Rev 0)
- Section 4.1.5 identifies the DA term to be
- 8.54. This is a typographical error and should be
- 8.45 (Note: the correct value was used in subsequent calculation steps).
- Section 4.2 identifies the DA term as 5.45. This is a typographical error and should be 8.45. The '
calculated value for e, is correct based on an 8.45 DA tem Allr I1
- Section 4.6.13 indicates that the es (positive vector) is 12.80. This is a typographic21 error ando should be 9.57. The 9.57 value was correctly used in subsequent calculation steps . I,4l-11 9
- Drift Calculation VYC-1599 was revised on 6t7/98. VYC462C Rev. 0 was completed, reviewed and approved after this date but did not use the updated drift values.
Mark S. McKinley
Com~pilation of ISP M-Iyses Efrors E9-ER99- O 33 a 0-7
& A _ _ __[ 11bE_
. l HOW Idatiicd Type of Error Uptranuty ltFeM~ CacuIM.W a I ucnspIrm 01 trr Aesolullon A - Admntrative Concern
- 1. Database Entry
- 2. DBD Validadon T -Technica Yes/No
- 3. Engineering Riview A n*k Wrgfr
.. A N TWC 462C Rev O OP-4366& IRF-Shows AF- I1 F. This informstion Is provided in xieprocedurediscuso n RCIC Temp Switches Should be So F. section and Is used by the E&C engineer as aid In Approved: 11-5-9t edaluatdons. T.heeAFaes arenotusedforcalibraion Preparer: MA acceptance criteria. The correct AF values were used In the calculation.
Action Required. None Imiediately. E&C to Di OP4366 _prior to next scheduled calibration. NA 2 VYC462C Rev OP-4366 & IRI-Shows LSP-- 1I7- UscofaslngliPl smorelimrinndisconsesvativcIA RCICTtmp Switches F.This I co ect fortheB. C a D This WAS done intentlonally. Howeve, for accuracy, the LSP Approved: 11-5-9t switches.TheAswitch BSP - 191' F. associated with the A switth sud also be shown. Preparer: MA Action Required. None Immediately. E&C can Include the LSP it their discretion Via Dl to OP.4366. These typographical CIeors occurred as pat of the A 3 VYC462C ReY 0 aculation Tet - Typographical RCIC Tecmp Switches errors wert noted as follows: conmrsion ofWord Ptrfect to MNcrosoft Word. Similar Issue Section 4.1.5 shows DA - 8.54. was addressed In ER994462. In this case, the correct values 1us Approved: 11-5-93 - Preparr: MA Should be 8.45 were used In the analysis. Action required: None Imrmedlately. VYC-462C wal correct *I
- Section 4.2 shows DA - 5.45.
Should be r.45 the typographical errors when next revised.
- Section 4.6.1.3 shows error -
12.10 Should be 9.57 A This Isa typographical error that cannot be confused wth I 4 VYC-I596 Rcv O Section 4.6 Identifies switches s PS-Head Calculaton 115-134A through D. Should be PS any other switch evaluation. Approved: 2-15-97 134A through D. Action Required: None Immediately. VYC-l 596 will correct iPre.RP ORtpogrhical error when next evised. the The discussion Is confusing. In particular, th head A 5 VYC66 Rev 3 Calculation Text h OP-4324 - MSL Presure Discussion on setpoht In regards head correction Identified In Table 13 implies it s negative. < j .4 Approved: 2-27-98 correction Isconfusing Kid appears to Howeer, the note associated with the head correction Is Preparer DiK be Inorrect, specific In It being a positive head correction - the negative ;(a PI value provided to Indicate where the process trip would occu. The K35psig field aetting will result In a proces rip of 833-psig. The field setting Is referenced Instead of the
.0 P%
lr process trip throushout the calculation. This is specified to 9 tj
^4ez be t ccase by the statenent In VYC-466 Attahment B A-S (1%
f, ~Secsion 4.0 (haed correction Isnot Included in the analysIs). ctbcasIhs-noeh n I quired OP-4324Isfc cRe. ured. r% Action Required: VYC-466 should be revised to clarIfy the difference between the field setting and the procs setting.
.j D
R I Although the values shwn throughout the calculation are corrert fr field ettling the head correction needs to be 0 considered to clarify the proces trip point .. VI-
._c a.
.1.. _____ _ __ __ _ _ _ _ _ __ _ _ _ _____ ____. u_
Po Page 3 of 3
REVIEW CHECKLIST ycZ-4GOc - ccA O. (ER 961090 01) ?&I no Zo a~12%I, 44 NIA any items not applicable to the calculation or CCN. Requirement Prenfrer Beviewer
- 1. Ensure the title page is properly filled out (items that are applicable).
- Calculation or CCN number on cover
- Title reflects subject
- Correct QA record status box checked
- Page numbering and count Is correct
- Cycle number is included ('NA" if not applicable)
- Initiating document is listed
- SSC I.D. numbers listed
- Vendor calculation and revision number listed
- Vendor safety class P.O. number listed
- Superseded calculations listed
- Keywords assigned
- Computer codes (inputloutput) listed
- Signatures and dates are included and are in correct chronological order. The title page reviewer and approver dates do not predate other dates in the calculation
- 2. The following forms are properly filled out and attached (if applicable):
- Review forms VYAPF 0017.04 (Ensure dated signaturesform the preparer and reviewer are included and all comments have been addressed)
- Open Item Listing VYAPF 0017.05
- Evaluation of Computer Code Use VYAPF 0017.06 Pi _ _A
- Calculation Database Input VYAPF 0017.07
- Calculation Change Notice VYAPF 0017.08
- 3. Ensure review of the calculation can be done without recourse to the originator.
- 4. Screening Evaluation/Safety Evaluation Included. / /A &V
- 6. Ensure individuals responsible for each portion of the calculation are Identified when multiple preparers andlor reviewers are used. o[A Appendix H AP 0O17 Rev. 5 Page 1 of 3
APPENDIX H (Continues d)VVC- 4(62C-C.CA _CDi
- 1- e- Z; -s , UCqz q43loo Requirement r - 1tld71rll Prenarer Reviewer sow X e4AL)550k.
- 6. Ensure that the calculation contains a title page, table of contents, calculation objective,method of solution, design inputs and sources, assumptions, calculation, results, conclusions and references.
- 7. . Ensure that each page has a page number, calculation number, revision number and CCN number, if applicable.
- 8. Ensure that every page of every attachment (or Appendix) contains its attachment (or Appendix) number.
- 9. Ensure that the methods for revising and correcting the calculation meet the requirements of App. C of AP 0017.
- 10. Ensure that the legibility requirements of App. D of AP 0017 have been met.
- 11. Ensure that the appropriate design Inputs (e.g. QA records) were used and the source of these inputs are clearly referenced.
- 12. Ensure that the calculation design information, both external and Intermal ~4-@
requirements have been met.
- 13. Ensure that If design specifications were used as input to the calculation the performance characteristics are independently verified and p5t documented.
4-%
- 14. Ensure that all reviewers' comments have been addressed. ,_ & u
- 15. Ensure that input and modeling uncertainties are explicitly addressed in the calculation. (ER 961090_02)
- 16. Ensure that any restrictions andlor limitations on the use of the calculation are clearly stated.
- 17. Ensure that computer codes are used in accordance with App. E of AP 0017. O /A pi W-
- 18. Ensure that the applicable input considerations from App. Cto AP 6008 have been incorporated and are explicitly addressed within the calculation. tv- &-
- 19. Ensure review of 10CFR50.46 reporting requirements has been documented for analyses which assess conformance to 10CFR50.46. ts 1A Appendix H AP 0017 Rev. 5 Page 2 of 3
APPENDIX H (Continued) V rc-a4- eAw- oer Requirement Preparer Reviewer
- 20. Ensure relevant conditions/limitations have been reviewed for their effect on this calculation and the review is noted in the calculation.
PREPARER REVIEWER Name (print) Aoaletvj A SName Q UA (print)L to Organization V4 D Organizationri El-d (E2CI S) Signature Signature ( m y __ ___ __ ___ __ ___ __ __ Date z (Z's Date __ _ _ _ _ _ _ _ Appendix H AP0017 Rev. 5 Page 3 of 3
Page ft of / VY CALCULATION REVIEW FORM Calculation Numbers VYC-462C Revision Number 0 CCN Number: 01
Title:
Reactor Core Isolation Coolin2 Steam Line Areas HiRh Temnerature Settoint Reviewer Assigned: John Lewis Required Date: 1/29/2000 Comments* Resolution
,A/ 6K,+ t1A TO U M
tIjAQCL) /Z.3e'o f I
/ kvicr Signature Date Calculatfn Preparer (Comments Resolved) Dat WS M
Method of Review: ZCalculation/Analysis Review be 6 o Alternative Calculation 1oQualification Testing Reviewer Signa e (Comments Resolved) Date Y4 o ox 9F
- Cornments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. 1 VYAPF 0017.04 (Sample) AP 0017 Rev. 5 Page 1 of 1
Page I a of VY CALCULATION REVIEW FORM Calculation Number: VitzL4e.C.. Revision Number: :. fYIM 1Lnlmhirn W9,A I &I -v.- . hi'
Title:
RC.Ic ____ S_ IQ I Reviewer Assigned: 34 C - Required Date: f/c2?/ao2o Comments* Resolution I 1
... D..D
-Reviewer Sigatr- Date Calcul ion Preparer (Comments Resolved) 4-. ~10 D te C9, Method of Review: UrCifculation/Analysis Review let O Alternative Calculation o Qualification Testing Revier Signatiure (Comments Resolved) /Dkte
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct Interpretation of Issues. Questions should be asked of the preparer directly.
_ S I
-t-i VYAPF 0017.04.(Sample) 18-0 AP 0017 Rev. S Page 1 of I
Page / of' ) VY CALCULATION REVIEW FORM Calculation Number: VtrC.-4e(ZC. Revision Number: 0 CCN Number: 07 1
Title:
RC.Tc. Sav~ L4l 62&' W 't^u Sd2 Reviewer Assigned: Rur . Cjre. Required Date:_________ Comments* Resolution X;/ AaD 5i 4 44 KZ Str*an OF Ffc A4ec.Arm B~o" D Qw'ZL-
.I / /cic Mot Th1,S CQL tc)SA @
4/ 43/Go we G~,AC C /3AND 4 0 7 6 4' i^,-A A*_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ IL o A- V)O - , 1Y/oo loop" CalculatdIn Preparer (Comments Resolved) Method of Review: (PCalculation/Analysisleiew O Alternative Calculation 1 1,4 3*
/t a,--I-010 0
O Qualification Testing Reviewer Signature (Comments Resolved) I15ate
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
VYAPF 0017.04.(Sample) AP 0017 Rev. S r Page I of 1
I Page L of VY CALCULATION REVIEW FORM Calculation Number: \St!,L4(gZC, Revision Number: ° CCN Number: t)1 '
Title:
Rc7tci S5Cam LiUnA, AvaJk Wji2 l rz Si1 el Reviewer Assigned: C p0M -o.n; Required Date: I/Az1/2ooo L Comments* Resolution UQfA Q, /N I , - ;af -M -,. 0-
/S~~
/./rA Reviewer Signatfe 41(A lculsti 2W 4 , / 7- 1A3 too
- /Date Preparer(Comments Resolved) at N Calculation/Analysis Method of Review:
O Alternative o Qualification Testing Review Calculation 'i I~. I v~o.Y A Review& Signature (Comments Resolved)
.. / .
IDite 60 N 00 n
- Comnents shall be specific, not general. Do not list questions or sugggestions unless suggesting wording to ensure the correct Interpretation of issues. Questions should be asked of the preparer directly.
w VYAPF 0017.04.(Sample) u AP 0017 Rev. S Page I of 1
Page I of VY CALCULATION REVIEW FORM Calculation Number: V\--41oZc-. Revision Number: 0 CCN Number: O*_
Title:
RC.1c S6 L, A, W-" - I YL. r~b'
&1aAl Reviewer Ass igned: LgJc,0e'4VL-;C Required Date: l/z9/z-oo Comments* Resolution 6 - ut Pi.) AOQ i-111 I--.1 rw-fzy la ) ,"/' A -20.Aa , I3/1 ir M' 11 C-fculaticn) Preparer (Comments Resolved) Dat 11:
Method of Review: .Calculation/Analysis Review 46-1 MhAlternative Calculation 1.) ,g \g , I ZN60 N nI 0 Qualification Testing ReViewefignature (Comments Resolved) Nte
- Comments shall be specific, not general. Dao not list questions or suggestions unless suggesting wording to ensure the correct interpretation of Issues. Questions should be asked of the preparer directly.
5
-jK VYAPF 0017.04.(Sample) a AP 0017 Rev. S Page 1 of I
Page I of VY CALCULATION REVIEW FORM Calculation Number: n-4toZC Revision Number: 0 CCN Number: 01 ' OI
Title:
RC-Ic. 5ham L-&m. e W6J lGprs" Sivazg4: Reviewer Assigned: _ Et) Required Date: Ik-11/20cp Comments* Resolution 1 _;%j4 C2A74 -iel 4< 0K 9 tA cAr /ftld a C d-~~~
*I _-
Ox'AQ0..2 -glw- -/&/3 00_ svd f _acl~ _rprr(omnt
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kP. O 21/co I Reviewergrnature D_ Method of ReZ El/alculation/Analysis Review O Alternative Calculation O Qualification Testing Review&Signatare (Comments Resolved) ID/te 00 1
*Conunents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of Issues. Questions should be asked of the preparer directly. co VYAPF 0017.04.(Sample)
AP 0017 Rev. S Page 1 of I
ATTACHMENT 7 TO BVY 05-068 CALCULATION NUMBER VYC-0706 REVISION 1, CONDENSATE STORAGE TANK LEVEL (RCIC) MONITORING, WITH CALCULATION CHANGE NOTICES CCN-01 AND CCN-02, AND TECHNICAL EVALUATION-NO. TE-2001-048, TABLE 1, CST LEVEL AND VOLUME ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
W- - 5n 8 - 5 a_- /;3 (! - 3/ ;7- / 7 ORIGINAL: PAGE 1 of 9 PAGES 0 - 7 k- /3
,F. /: L. -D57 Rev. 1: PAGE 1 of 26 PAGES QARECORD? X _ /
X YES 7f I/ a37 RECORD TYPE NO. 09.C16.004 NO Safety Class/P.O. NO. (if applicable) _ SC2 I SCE
- YANKEE ATOMIC ELECTRIC COMPANY CALCULATION/ANALYSIS FOR TITLE CONDENSATE STORAGE TANK LEVEL (ROIC) MONITORING PLANT VERMONT YANKEE CYCLE 20 CALCULATION NUMBER VYC-706 THIS REVISION IS A MAJOR RE-WRITE I
KEYWORDS: Instrument Uncertainty, RCIC. CST. APP R Safe S/D COMPUTER CODES: None EQUIP/TAG NOs.: LT-107-12A & B. LT-107-12A(M) & B(M). LI-107-12A. 13A-K46. 13A-K47 SYSTEMS: Reactor Core Isolation Cooling (RCIC). Condensate & Demineralized Water Transfer
REFERENCES:
See Section 6.0 FORM WE-103-1 Revision 5
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Table of Contents Page Table of Contents .......... ........................................................ 2 List of Tables .................................................................. 3 List of Attachments ............. . . . . . . ..... 4 History of Revisions .......... ....................................................... 5
- 1. PURPOSE ... 6 1.1 Calculation Objectives .. 6 1.2 System & Components .. 7 1.3 Instrument Loop Functions ..................... 7 1.3.1 Normal Operations ..................... ............................................. 8 1.3.2 Accidentl Post-Accident/ EOP Conditions ................... ............................. 8
- 2. METHODS AND ASSUMPTIONS .................................................................. 8 2.1 Methods .......... 8 2.2 Criteria .............................................................. 8 2.3 Assumptions .......... 9
- 3. INPUT DATA . . .14 3.1 Process and Loop Data .. 15 3.2 Environmental Conditions .. 16 3.3 Transmitter LT-107-12A and LT-107-12B Data .. 17 3.4 Trip Unit LT-107-12A(M) and LT-107-12B(M) Data . .18 3.5 Indicator LI-107-12A Data .. 19 3.6 Calibration M&TE Data .. 19
- 4. CALCULATION DETAIL ............................. 20
- 5. RESULTS AND CONCLUSIONS . . .20 5.1 Total Loop Uncertainty .. 20 5.2 Setpoint Evaluation .. 20 5.3 Calibration and Test Results ..... 21 5.4 Conclusions and Summary of Recommendations . .22 5.5 VYDEP-15 Impact Considerations .. 23
- 6. REFERENCES.......................................................................................................... 24 Vermont Yankee Design Engineering Page 2of 26
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 List of Tables Page Table 1: Component Identification .............................. ................................... 7 Table 2: Normal Area Temperatures ............................... ,. 9 Table 3: Process/Loop Inputs .................................................................. 15 Table 4: Environmental Input Data ................................. ................................. 16 Table 5: Transmitter Input Data ....................... ........................................... 17 Table 6: Trip Unit Input Data .................................................................. 18 Table 7: Indicator Input Data .................................................................. 19 Table 8: Calibration M&TE Input Data .................................................................. 19 Table 9: Total Loop Uncertainty ........................ 20 Table 10: Setpoint Results ........................ 21 Table 11: Module Calibration Ranges ........................................................... ...... 21 Table 12: Module Calibration Tolerances .............................. 22 Page 3 of 26 Vermnont Design Engineering Vermont Yankee Design Engineering Page 3 of 26
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I
- Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I List of Attachments ATTACHMENT A: Loop Sketch ATTACHMENT B VYC-1 844 Rev. 0, CST Vortexing (Excerpts)
ATTACHMENT C: Mathcad Computations of Loop Accuracy ATTACHMENT D: Input Data for Rosemount 1153GB5 Transmitter ATTACHMENT E: Input Data for Rosemount 510DU Trip Unit ATTACHMENT F: Input Data for Sigma 1151 Indicator ATTACHMENT G: VYC-1614 (1153) Input Data (Excerpts) ATTACHMENT H: VYC-1615 (510DU) Input Data (Excerpts) ATTACHMENT I: VYC-1616 (Sigma 1151) Input Data (Excerpts) ATTACHMENTJ: VYC-1758 (M&TE) Input Data (Excerpts) ATTACHMENT K: OP-4355 Input Data (Excerpts) ATTACHMENT L: Miscellaneous Application-Specific Data ATTACHMENT M: Correspondence ATTACHMENT N: WE-1 03 Calculation Review Form and Review Checklist amen, F d->,,: a.. 9*t,,4 Page 4 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 4 of 26
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I History'of Revisions Rev. No. Approval Reason & Description of Change Date ORIGINAL 6/9/89 Original Issue _-_. 9/- Major Re-write: Revise method and format to comply with VY Uncertainty and Setpoint Design Guide and to support implementation of Improved Technical Specifications (ITS). Revision 1 Incorporates new requirements for level based on vortexing as developed in VYC-1844 Rev. 0. Due to the extent of input/output and format changes, this revision is a major re-write and revision bars are not used. Page 5 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 5 of 26
'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I PURPOSE 1.1. Calculation Objectives This calculation has been developed in support of the Vermont Yankee Setpoints program and covers instrument loops LT-1 07-12A and LT-1 07-12B in the Condensate and Demineralized Water Transfer System and has the following major objectives:
- 1. Document the instrument loop functions and the basis for the setpoint(s).
- 2. Establish the total loop uncertainty for each output function and verify consistency with the design basis.
- 3. Calculate the limiting setpoints and Allowable Value (AV) for inclusion in the Improved Technical Specifications (ITS) if applicable.
- 4. Evaluate the adequacy of the existing setpoint and calibration limits.
- 5. Provide as-found and as-left tolerances for use in instrument calibration and functional test procedures. Determine Measuring and Test Equipment selection requirements. Verify and document process corrections, instrument scaling, and calibration methods.
- 6. VYDEP-15 requires that applicable operating procedures, alarm responses, and standard, off-normal, and emergency operating procedures be included in the evaluation. This requirement is accomplished by the inter-departmental review which supplements the WE-103 review process.
Design Engineering Page 6of26 Vermont Yankee Design Vermont Yankee Engineering Page 6 of 26
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 1.2. System & Components This calculation applies to the Condensate Storage Tank Level Monitoring Loops which provide automatic RCIC suction transfer as well as Appendix R Safe Shutdown level indication. The specific components addressed are as listed in Table 1 below. Table I Component Identification Tag Number Manufacturer Model l Rack/Cabinet l Description l SYS Flow l CWD l _ _ __._llJ (MPAC) Diagram l (B-191301) Rosemount 1153GB5 CST Local COND STORAGE 107 G-191176 Sheet 866 LT-107-12A Rack 25-66A TANK LEVEL Sheet I TRANSMITTER LT-107-12B Rosemount 1153GS5 CST Local COND STORAGE 107 G-191176 Sheet 866 Rack 25-66A TANK LEVEL Sheet 1 TRANSMI1TER LT-107-12A(M) Rosemount 510DU21602 CAB 25-6B RCIC SUCTION 107 G-191176 Sheet 1180 6A014 RB 280' TRANSFER Sheet 1 VOL21 ANALOG TRIP LT-107-12B(M) Rosemount 510DU21602 CAB 25-6B RCIC SUCTION 107 G-191176 Sheet 1180 6Ao14 RB 280' TRANSFER Sheet 1 VOL 21 ANALOG TRIP LI-107-12A Sigma 1151 CP 82-1 COND STORAGE 107 N/A Sheet 1177 RB 213' NW TANK LEVEL VOL 52 INDICATOR 1.3. Instrument Loop Functions The RCIC is a standby safety system that supplies makeup water to the reactor vessel if the reactor feedwater flow is lost during a reactor isolation condition. Temperatures would increase if the feedwater supply were lost, because steam generation would continue as a product of core fission decay heat. Therefore, the RCIC system must supply makeup water to maintain a sufficient reactor water level to prevent excessive temperatures. The makeup water is supplied until the reactor is depressurized to a point where the shutdown cooling mode of the Residual Heat Removal (RHR) system is placed in operation. The RCIC is automatically activated by a reactor vessel low-low water level signal. The RCIC turbine-driven pump is designed to supply make-up water into the vessel at the rate of 400 gpm over a reactor pressure range of 1135 to 165 psia. The Condensate Storage Tank is the initial source of water volume for the RFCI pump. When level has decreased to a low level setpoint, RCIC suction is transferred to the suppression chamber. These channels provide the indication and trip actuations associated with these functions. Attachment A is a simplified loop diagrams of the instruments and components described in Table 1 and below. Vermont Yankee Design Engineering Page 7 of 26
'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 1.3.1. Normal Operations During normal operation, the RCIC system is in standby mode and the LT-1 07-12A & B loops continuously monitors Condensate Storage Tank (CST) water level. The LT-107-12A loop also continuously displays CST water level on indicator LI-107-12A at RCIC Alternate Shutdown Panel CP 82-1 in the RCIC Room. These loops have no control room indications and have no automatic functions during normal operations. 1.3.2. Accidentl Post-AccidentlEOP conditions When system operation is initiated, the RCIC pump takes suction on the CST. CST water level is monitored by both the LT-1 07-12A & B loops and displayed on LI-107-12A at CP 82-1. At a low level setpoint, MasterTrip Units LT-107-12A(M) and 12B(M) trip to open valves Vi 3-39 and V13 -41 which transfers RCIC suction to the suppression chamber. Actuation of either trip unit causes both valves to operate. Indicator LI-107-12A is credited for Appendix R safe shutdown.
- 2. METHODS AND ASSUMPTIONS 2.1. Methods This calculation has been prepared in accordance with the WVermont Yankee Instrument Uncertainty and Setpoint Design Guide" [REF. 6.1], WE-103, Yankee Nuclear Services Engineering Instruction, 'Engineering Calculations and Analysis.'
[REF. 6.4], and Design Engineering Procedure VYDEP-15, 'Calculations,' [REF. 6.5]. This calculation is performed using the Class 1 graded approach since the trip function performed by these loops ensures a continuous RCIC suction and its failure to actuate at the correct level could result in failure of the RCIC system to supply makeup water to the reactor. Calculation of the CST level indication loop could be performed using the Class 2 approach because these loops provide no automatic function and provide indication to support operator actions. However, for simplicity, the Class I approach will be used throughout. Standard methods employed In this calculation are explained in the Design Guide, special techniques and criteria are explained below. 2.2. Criteria 2.2.1. Special Criteria None 2.2.2. Software Criteria Calculations in Attachment C (Mathsoft MathCad 7 Professional) have been manually verified using a hand calculator in accordance with WE-108 (Computer Codes) and designated with a check mark. No errors were found in Vermont Yankee Design Engineering Page 8 of 26
4Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I the manual verification of the calculations performed. MathCad 7 stores numbers with a 15-digit accuracy, all calculation outputs displayed within the calculation are rounded from the values stored in MathCad 7. Rounding errors induced by MathCad 7 are assumed to be negligible. Computer specifications: Gateway 2000 G6-233 - Serial number 0008583505 (1214/97) Intel Pentium II, 233 MHz we MMX Technology 96 MB RAM Integral Math Co-Processor Software specifications: Microsoft Windows 95 Microsoft Word Version 97 SR-1 Mathsoft MathCad 7 Professional 2.3. Assumptions 2.3.1. Calibration of instruments is assumed to be at a temperature within the ranges shown in the following table. The RCIC Room (Vol. 52) and Reactor Building (Vol. 21) reference temperatures are per the EQ Manual section 7.4 [Ref. 6.6]. The Condensate Storage Tank is located outside and the level transmitters are located on rack RK-25-66A inside an insulated and un-heated room attached to the side of the CST. The expected temperature extremes for the CST instrument room are based on discussions with the E&C System Engineer and a walkdown by the setpoint project site representative (Attachment M). The normal ambient air temperature extremes expected are as listed in Table 2. Table 2 Normal Area Temperatures Plant Area Minimum Maximum Condensate Storage Tank - Instrument Rack 25-66A 55 OF 85 OF RCIC Room - Volume 52 - 213' 88 F 112 'F Reactor Building -Volume 21 -280' 62F 106 'F 2.3.2. CST water minimum temperature is maintained 2 50 OF (as read on TI-1 07-3) per VY Procedure AP-0150, Auxiliary Operator Round Sheet TB/OUT, page 5 of
- 7. The tank is heated by auxiliary steam heating coils. As a conservative value for minimum temperature, the assumed value of 400 F from FSAR section 14.5.2 will be used [Ref. 6.2].
CST water maximum temperature is assumed equal to the maximum ambient temperature of 100 0F as identified in FSAR section 2.3.5 and on RCIC Process Diagram 5920-0605 [Ref. 6.25.1]. 2.3.3. The calibration interval for the level transmitters and master trip units is once every operating cycle or 684 days (547.5 days + 25%) per the 'Tech Spec Vermont Yankee Design Engineering Vermt Y e DPage 9 of 26
'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Condensate Storage Tank Level (ROtC) Monitoring VYC-706 Rev. I Selected Definitions". However, the trip units and LI-1 07-12A have been functionally tested (calibration checked) every month per OP-4355 [Ref. 6.73 and it is assumed that the indicator and trip units will be tested quarterly or every 114 days (91 days + 25%) with ITS implementation. It should be noted that the functional test of the trip units and indicator in essence constitute a calibration since as-found and as-left data is recorded during each test. 2.3.4. The loop instruments are currently calibrated either monthly or each operating cycle and the test equipment temperatures will be bounded by the ambient temperature extremes listed in Table 2 above. For the test equipment uncertainty evaluations performed under VYC-1758 [Ref. 6.13. Attachment J], the RB RHR Cmr Rm 232' environment conservatively bounds the environment to be expected at the CST instrument room, and will therefore be used as representative of the CST instrument room. The test equipment used for calibration of LI-107-12A is the 51ODU calibration and readout assembly located in panel 25-68 in RB Volume 21 at the 280' elev., therefore, the temperature variations for Reactor Building Occupied Areas will be used. 2.3.5. The temperature variation within a cabinet is the same as the variation of the room in which it is located. The temperature difference between the room and the cabinet is therefore constant. Calibration data are assumed collected with the equipment at the operating temperature of the cabinet. 2.3.6. Review of the Vermont Yankee Environmental Qualification Program Manual [Ref. 6.6 and Attachment L] indicates the following: The transmitters will not experience harsh temperature or radiation conditions for any accident and need only demonstrate operability under their normal service environment. Per Qualification Category B and Technical Basis Note 71, the trip units will experience harsh environmental conditions of various design basis accidents within which they need not function for accident mitigation. These trip units are relied upon to function prior to a harsh environment developing, however, due to their mounting within a rack containing other accident mitigation channels, they must be qualified to withstand the subsequent harsh environment without experiencing a failure that could adversely impact any safety function. The CST RCIC suction transfer function is required to function short-term (2 hours or less) following a small break LOCA. The level indicator LI-107-12A has no accident mitigation function and is only credited for Appendix R Safe Shutdown. Based on the above discussion, the RCIC CST auto suction transfer function of LT-107-12A(M) & LT-107-12B(M) will be evaluated for mild environmental conditions for up to two hours following a small break LOCA, with seismic. The trip units are qualified to operate in the harsh environment such that they will not fail, however, these conditions need not be evaluated with respect to auto-transfer trip setpoint uncertainty. The transmitter accident conditions will consider only their normal environmental conditions with seismic. The indicator LI-1 07-12A loop will be evaluated for normal conditions only. Vermont Yankee Design Engineering o YPage 10 of 26
'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. a Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 2.3.7. Calibration Tolerance is an output of this calculation, and will be based on the accuracy of the devices. The existing calibration tolerances are shown In Tables 5 through 7. 2.3.8. Published vendor specification data are assumed at a 2 sigma level probability with a confidence that the error will reflect the actual error 95% of the time (95195). 2.3.9. During instrument calibration, it is assumed full traverse testing is performed on all analog instruments. 2.3.10. It is assumed that the Rosemount 710DU readout assembly [Evaluated under VYC-1758 - Ref. 6.13] is used to simulate input signals for functional testing and calibration of LU-107-12A, LT-107-12A(M) and LT-107-12B(M). 2.3.11. The Sigma model 1151 has been seismically qualified to accelerations greater than those required for Vermont Yankee Control Room equipment. Seismic testing for the 1151 is documented in Test Report # SBI-3 [Ref. 6.18 and Attachment F]; the results indicate that the worst case seismic effect on the six (6) 1151 indicators tested was 0.8% full scale and the average effect of the other five instruments was 0.24%. A seismic effect of 0.24% to 0.8%, when compared to reference accuracy of 1.5% and repeatability of 2%, is insignificant and will be considered negligible for this calculation. 2.3.12. The Analyzed Drift term for the LT-1 07-12A & B CST Level Transmitters is derived from VYC-1614 Rev. 0 [REF. 6.10]. Specifically, the Analyzed Drift term is derived from drift data analyzed for group "Rosemount 11 53GB5 (LT-107-12A & B)'. The Rosemount 1153GB5 Analyzed Drift (ADR) is calculated based on the following considerations: a) The analyzed drift data shows the drift (ADR) to be 0.929%. b) From review of this drift analysis and the associated histogram, it is concluded that the data was not normally distributed. However, a review of the raw drift data Indicates that all points fall within 2a, and, therefore can be considered 'normal". Due to the small number of data points (14), the large TIF of 3.012 provides additional conservatism to the bounding drift term. c) The time dependency discussion for the 11 53GB5 (Attachment G), indicates there is a slope on the time dependency line that does not allow for an accurate approximation of time dependency. The Significance F Is greater than 0.05 for the 50% and 100% points and less than 0.05 at 0%, indicating some correlation between drift magnitude and time interval [Ref. 6.81. Since a magnitude of drift to time relationship cannot be ruled out, the 684-day Analyzed Drift Term will be derived from the 545-day ADR term as follows: A DR694-Atm =+ 64 xO.9292 = +/-1.0407% 545 Page 11 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 11 of 26
'Condensate Storage Tank Level (RCIC) Monitoring g VYC-706 Rev. I Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 d) The average drift value for this group is -0.015% at 0%, 0.048% at 50% and 0.079% at 100%. Since both the 0% and 50% values are less than 0.05% (N
- 20 and STDEV a 0.10%), and the 100% value is less than 0.12% (N
- 20 and STDEV 2 0.25%), this term is negligible and hence no bias effects are considered [REF. 6.8].
e) The transmitter ADR value for the operating cycle is as calculated above: ADR6uzy, = +/- 1.0407% 2.3.13. The Monthly Calibration Analyzed Drift term for the LT-107-12A(M) and LT-107-12B(M) trip units is derived from VYC-1615 Rev. 0 [REF. 6.11]. Specifically, the Analyzed Drift term is derived from drift data analyzed for Rosemount Trip Units
- Monthly Group. The Rosemount Trip Units - Monthly Group Analyzed Drift (ADR) is calculated based on the following considerations:
a) From review of this drift analysis and the histogram, it is concluded that the drift data is normally distributed. As indicated in the time dependency discussion for the Rosemount Trip Units - Monthly Group (Attachment H), the slope on the regression line is < 0.01% for 55 days. Since there is no indication of a drift to time relationship, the 38-day Analyzed Drift Term will be derived directly from the 30-day ADR term.. b) The average drift value for this group is 0.000%, hence no bias effects are considered [REF. 6.8]. c) The trip unit ADR value for monthly calibrations is calculated directly as follows: ADR3a4.y, = ADR3O0Da, = i 0.0871% 2.3.14. The Quarterly Calibration Analyzed Drift term for LT-107-12A(M) and LT-1 07-12B(M) trip units is derived from VYC-1615 Rev. 0 [REF. 6.11]. Specifically, the Analyzed Drift term is derived from drift data analyzed for Rosemount Trip Units
- Quarterly Group. The Rosemount Trip Units - Quarterly Group Analyzed Drift (ADR) is calculated based on the following considerations:
a) From review of this drift analysis and the histogram, it is concluded that the drift data is normally distributed. As indicated in the time dependency discussion for the Rosemount Trip Units - Quarterly Group (Attachment H), the slope on the regression line is insignificant. Since there is no indication of a drift to time relationship, the 114-day Analyzed Drift Term will be derived directly from the 77-day ADR term.. b) The average drift value for this group is 0.000%, hence no bias effects are considered [REF. 6.8]. c) The trip unit ADR value for monthly calibrations is calculated directly as follows: ADR11,4Day,= ADR 77.Days = +/- 0.299% 2.3.15. The Analyzed Drift term for indicator L-107-12A is derived from VYC-1616 Rev. 0 [REF. 6.12]. Specifically, the Analyzed Drift term is derived from drift data Engineering Design Engineering Yankee Design Page 12 of 26 Vermont Yankee Page 12 of 26
KCondensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I analyzed for Surveillance Group 1. The Surveillance Group 1 Analyzed Drift (ADR) at either the 10%, 50%, or 90% point (whichever value is most conservative with respective to drift magnitude and time dependency) is calculated based on the following considerations: a) The analyzed drift data shows the 90% point to be the largest value at 1.4338% with the 50% value at 1.3488%, and the 10% point at 1.3095%. The 100% analyzed drift value is largest, and will be used as a conservative drift value. b) From review of this drift analysis and the histograms, the data exhibits a normal distribution for all points. As indicated in the time dependency discussion for Surveillance Group 1 (Attachment J), time dependency is exhibited at all points. However, the Significance F at all points Is much greater than 0.05, indicating no correlation between drift magnitude and time interval. Since there is no indication of a drift to time relationship, the 38-day Analyzed Drift Term will be derived directly from the 31-day ADR term. c) The average drift value for this group is -0.0081% at 0%, -0.0173% at 50%, and -0.0107% at the 100% point. Since these are all less than 0.09% (N > 120 and STDEV 2 0.50%), this term is negligible and hence no bias effects are considered [REF. 6.8]. d) The indicator ADR value for monthly calibrations is calculated directly as follows: ADRu, = ADR 31D = +/- 1.4338% e) Since the indicator and trip units are tested at the same time, and since the Trip Units will be calibrated quarterly under ITS, the indicator quarterly calibration drift must be determined. Although no time to drift magnitude relationship was determined for these indicators, the 114 day drift will be conservatively derived from the 31 day ADR term as follows: ADR 14 -1 xl.43382 +2.7495% 2.3.16. Calibration of LI-107-12A under OP-4355 (Ref. 6.7 and Attachment K] is performed using the Rosemount Readout Assembly and Calibration Current adjustments to simulate a current input to trip unit LT-107-12A(M). The auxiliary analog output (1-5 Vdc) of the trip unit in turn provides the voltage output (for the given input current level) to LI-107-12A. Based on the calibration method used, the Monthly and Quarterly drift associated with the auxiliary analog output circuit of master trip unit LT-107-12A(M) will be assumed to be included in the Monthly and Quarterly Analyzed Drift term for indicator LI-i 07-12A. OP-4355 [Ref. 6.7] does not address calibration of the auxiliary analog output circuit of the master trip unit over the range of 4-20 mAdc input. Therefore, calibration effect for the indicator will be assumed to include calibration effect associated with the analog output circuit. Page 13 of26 Vermont Design Engineering Yankee Design Vermont Yankee Engineering Page 13 of 26
' Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Condensate Storage Tank Level (ROIC) Monitoring VYC-706 Rev. I Given that Indicator Analyzed Drift (DA) includes trip unit analog output circuit drift, and auxiliary analog circuit Calibration Effect (CE) is included in Indicator CE, and since Seismic Effect of the trip units is 0.0% (2.3.19), the indicator Normal, Testing, and Accident uncertainties will be assumed to include all uncertainties associated with the trip unit auxiliary analog output circuit. 2.3.17. Given that Analyzed Drift (ADR) data is available for each loop component evaluated under this calculation, and given that LI-1 07-12A and LT-107-12A(M) and LT-107-12B(M) are all currently calibrated monthly (trip units may be calibrated quarterly under ITS), these loops will be evaluated for mild environmental conditions for the Reactor Building Vol. 21 and 52 (i.e. normal conditions), and it is assumed that the Analyzed Drift (ADR) term for each includes Temperature Effect (TE), Readability (RD), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), Humidity Effect (HE), and Radiation Effect (RE) for the indicator and trip units [Ref. 6.1 section 3.6.5] under both normal and accident conditions. 2.3.18. Given that Analyzed Drift (ADR) data is available for transmitters LT-107-12A & B, and given that LT-107-12A & B are calibrated each operating cycle, the transmitters will be evaluated for mild environmental conditions (i.e. normal conditions), and it is assumed that the Analyzed Drift (ADR) term includes Temperature Effect (TE), Deadband (DB), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), and Humidity Effect (HE) [Ref. 6.1 section 3.6.5] under both normal and accident conditions. Radiation Effect (RE) at the CST is assumed to be negligible. 2.3.19. Seismic Qualification testing of the Rosemount 51ODU Trip Calibration System is documented in Rosemount Report 3768A Rev. B [Ref. 6.6.1 and Attachment El. The documented results of testing indicate that the worst case seismic effect on the trip point setting for the twelve (12) channels tested was 0.024% span. 32 of the remaining 35 data results yielded setpoint effects of less than 0.012%. A seismic effect of 0.024% maximum, when compared to repeatability of 0.13%, is insignificant and will be considered negligible for this calculation. 2.3.20. The environmental conditions for the Rosemount 510DU specified in Table 5 of Reference 6.15 [Attachment E] provide the limiting environments to be used for choosing the appropriate performance specifications. Since the temperature, humidity, and radiation conditions listed for the nNormal - High3 environment bound the conditions expected for LT-107-12A(M) & 12B(M) under normal and mild accident conditions (See Table 4), the Trip Point Repeatability and Auxiliary Analog Output specifications of
- 0.20% will be used [Tables 6 and 7 of Attachment E] for both normal and accident conditions.
- 3. INPUT DATA Data used to calculate loop uncertainties, process corrections, setpoints, and decision points are tabulated in the following sections with the applicable reference or basis noted.
Page 14 of 26 Design Engineering Vermont Yankee Design Eingineering Page 14 of 26
t ondensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 3.1. Process and Loop Data Process data used to evaluate process corrections, decision points, and setpoint limitations are tabulated below with the applicable references. Table 3 ProcesslLoop Inputs Basis Description Data Ref. 6.2 Section 14.5.2.3 & CST Water Temperature Minimum 40 OF Assumpt. 2.3.2 Ref. 6.2 section 2.3.5 & CST Water Temperature Maximum 100 'F Ref. 6.25.1 Ref. 6.14 (Attachment B) Process Limit (ITSICTS) - 2 26.5" above CST' bottom Critical height submergence (Vortexing) 24.7 " above CST bottom Additional margin for switchover 1.8" above critical height TS 3.2.9 & Table 3.2.9 Technical Specification Limit (CTS) Low CST Water Level Trip (RCIC auto suction transfer) Ref. 6.14 (Attachment B) 2 3% CST Volume VYC-706 Rev. 0 3% CST Level 23.7" above CST bottom Section 3.3.6 11.7" = 3%(390') + 12" = tap location above CST bottom Ref. 6.14 & Attach. B Lowest point credited for RCIC Suction 20.7" above CST bottom Ref. 6.26.3 Reference Elevation; floor at rack 25-66A El. 252' 6" Walkdown (Attach. M) Transmitter Center Line El. 253' 8" Ref. 6.26.3 Transmitter Sensing Tap Elevation El. 254' I This limit includes consideration for the TS Limit of a 3%. Critical height of submergence prevents Introduction of air into RCIC suction prior to completion of transfer of suction to suppression pool; Includes consideration for CST Vortexing based on RCIC flow [See Attachment B]. Page 15 of 26 Vermont Design Engineering Yankee Design Vermont Yankee Engineering Page 15 of 26
I 'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Sorae ankLeel(RCC)MontoingWC708Re.
'Codesat 3.2. Environmental Conditions The following information provides the environmental conditions expected for the components located at the Condensate Storage Tank and in the Reactor Building.
Table 4 Environmental Input Data Basis Description Data Ref. 6.2 Table 2.3.2 CST Area Ambient Temperature Extremes -33 to 100F Assumption 2.3.1 CST Rack 25-66A Normal Ambient Temperature 55 to 850 F Assumption 2.3.6 CST Rack 25-66A Accident Ambient Temp. 55 to 850F CST Rack 25-66A NormaUAccident Humidity Ambient Ref. 6.6 & Attach. L RB 280' Elev. (Vol. 21) Normal Temperature 62 to 1060 F Ref. 6.6 & Attach. L RB 280' Elev. (Vol. 21) Accident Temperature 62 to 1060F 2 RB 280' Elev. (Vol. 21) Norm./Accident Humidity 40 to 75% Ref. 6.6 & Attach. L RB 213' Elev. (Vol. 52) Normal Temperature 88 to 1120F Ref. 6.6 & Attach. L RB 213' Elev. (Vol. 52) Accident Temperature 88 to 112OF2 Ref. 6.6 & Attach. L RB 213' Elev. (Vol. 52) Norm./Accident Humidity 60% average Reactor Bldg. 280'- Vol. 21 (Trip Units) Ref. 6.6 & Attach L Normal Radiation (40 yr.) 3.50 x 103 Rad y Ref. 6.6 & Attach L Normal Radiation (Quarterly Dose) 2.73 x 101 Rad y Reactor Bldg. 213' - Vol. 52 (Indicator) Ref. 6.6 & Attach L Normal Radiation (40 yr.) 3.50 x 104 Rad y Ref. 6.6 & Attach L Normal Radiation (Quarterly Dose) 2.73 x 102 Rad y 2 Accident temperatures for small break LOCA (mild environment) before two hours. Vermont Yankee Design Engineering o YPage 16 of 26
,Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 3.3. Transmitter LT-107-12A and LT-107-12B Data Table 5 Transmitter Input Data Basis Description Data Ref. 6.16 and Minimum span 0 to 125 inches water Attachment D Maximum span (URL) 0 to 750 Inches water Maximum zero suppression 500% Calibrated Span Maximum zero elevation 600% Calibrated Span Normal Operating Temperature Limits 40 to 200OF Normal Operating Humidity Limits 0 to 100% Accuracy rating +/- 0.25% Calibrated Span3 Rated drift +/- 0.20% URL for 30 months Rated temperature effect +/- (0.75% URL + 0.5% Span)/1 00F Static pressure span correction N/A Rated static pressure zero effect N/A Rated overpressure effect +/- 1.0% URL after 2,000 psi Rated deadband (sensitivity) None Power Supply Voltage Effect < 0.005% of output SpanNolt Mounting Position Effect No span effect; zero shift up to 1.5 inWC can be calibrated out Ref. 6.7 (Att. K) Input Span 0 to 390 inWC Existing calibrated input span 4 to 394 inWC Existing calibrated output span 4.00 to 20.00 madc Existing Calibration Tolerance +/- 0.04 mAdc (+/- 0.25%) Assumption 2.3.6 Radiation effect N/A Ref. 6.16 & Att. D Steam Pressure/Temperature +/- 5.0% URL during and after exposure Performance to steam at 265TF (24 psig for 35 hrs.) Ref. 6.16 & Att. D Seismic Effect +/- 0.5% URL during/after ZPA 4 g's Assumption 2.3.12 Analyzed Drift (DA) +/- 1.0407% (+/- 4.059 InWC) Ref. 6.3 and 6.10 Calibration Frequency Each operating cycle (684 days) 3 includes combined effects of linearity, hysteresis, and repeatability. Vermont Yankee Design Engineering Page 17 of 26
,, Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 3.4. Trip Unit LT-107-12A(M) and LT-107-12B(M) Data Table 6 Trip Unit Input Data Basis Description Data Ref. 6.7 Input Span (CS) 4.0 to 20.0 madc (0 to 390 inWC) Ref. 6.15 Auxiliary Analog Output 1-5 Vdc (4 to 20 mAdc) Ref. 6.7 Existing nominal setpoint 4.64 +/- 0.06 madc (19.6 +/- 1.463 inWC)' Ref. 6.15 & Att. E Operating Temperature/Humidity Range Normal Conditions - Normal Environ. 60 to 900 F - 40 to 50% RH Adverse Conditions - Normal Environ. 40 to 120OF - 10 to 60% RH Normal Conditions - High Environment 40 to 104OF - 20 to 90% RH Adverse Conditions - High Environment 40 to 1560 F - 20 to 99% RH Ref. 6.15 &Att. E Reset Differential Adjustment 0.5% to 7.5% Span5 Assumption 2.3.20 Trip Point Repeatability +/- 0.20% Span for 6 months Assumption 2.3.20 Aux. Analog Output Accuracy +/- 0.20% Span for 6 months Drift rating None given Assumption 2.3.19 Seismic Effect +/- 0.0% Span Ref. 6.7 Existing Calibration Tolerance +/- 0.06 madc (+/- 0.375% Span) Ref. 6.11 & Analyzed drift (DAm) Monthly +/- 0.0871% Span (+/- 0.3397 inWC) Assumption 2.3.13 Ref. 6.11 & Analyzed drift (DA0) Quarterly +/- 0.299% Span (+/- 1.1661 InWC) Assumption 2.3.14 4 Setpoint level (19.6") indicates inches water applied to the transmitter including 4 inches static head; this setpoint is equivalent to 27.6 inches above the bottom of the CST. 5 Reset differential is adjustable from 0.5% to 7.5%. Vermont Yankee Design Engineering Page 18of 26
'Condensate Storage Tank Level (RCIC) Monitoning WYC-706 Rev. I 3.5. Indicator LI-107-12A Data Table 7 Indicator Input Data Basis Description Data Assumpt. 2.3.16 & Input Span 1-5 Vdc MPAC Ref. 6.7 Calibrated Span 0-100% Attachment M Output Scale Indication 0-100% Minor Scale Division 2% Readability (1/2 of minor division) 1% Ref. 6.17 & Att. F Operating Temperature Range -40 F to 122°F Ref. 6.7 Existing Calibration Tolerance +/- 2.0% Ref. 6.17 Accuracy +/- 1.5% FS Repeatability +/- 2.0% FS Assumpt. 2.3.11 Seismic Effect +/- 0.0% FS Ref. 6.12 & Analyzed drift (DAM) Monthly +/- 1.4338% Span Assumption 2.3.15 (+/- 5.5918 inWC) Ref. 6.12 & Analyzed drift (DA 0 ) Quarterly +/- 2.7495% Span Assumption 2.3.15 (+/- 10.7231 inWC) 3.6. Calibration M&TE Data Table 8 Calibration M&TE Input Data Basis Description Range Resolution Accuracy Accuracy (% Rdg or Span) (Calibr. Units) Attachment J HP 34401A 20 mAdc 0.0001 mAdc 0.0924% rdg 0.0185 DMM _ 20 mAdc mAdc Attachment J HP 3466A 100 mAdc 0.001 mAdc 0.0984% rdg 0.0197 DMM @ 20 mAdc mAdc Attachment J Heise 901B 0-400" H2 0 0.01 "H20 0.1449% span 0.5797" H2 0 Attachment J Heise 901B 0- 1000* H2 0 0.1 -H2 0 0.1452% span 1.4524" H2 0 Attachment J Heise CMM 0 - 800" H 20 1.0 "H-2 0 0.1616% span 1.2925" H 20 Attachment J Heise CMM 0 - 830" H2 0 1.0 "H 2 0 0.1613% span 1.33912 H2 0 Attachment J Heise 730A-03 -100- 860" 0.1 1H2 0 0.1691% span 1.6236" H20 H 20_ _ _ _ _ _ _ _ _ _ _ Attachment J Rosemount 0-28 mAdc 0.01 mA 0.0707% @ 20 0.0141 mAdc Readout Assy. mAdc (.003525 Vdc) Page 19 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 19cof 26
' Condensate Storage Tank Level (RCIC) Monitoring VYC706 Rev. I
'Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I
- 4. CALCULATION DETAIL The detailed calculation of loop uncertainties, setpoints, testing tolerances, and margins have been performed using MathCad and are documented as Attachment C.
- 5. RESULTS AND CONCLUSIONS 5.1. Total Loop Uncertainty Total Loop Uncertainties (TLU) have been evaluated for the RCIC CST Level indication and trip loops and the results are presented in Table 9 below.
Table 9 Total Loop Uncertainty TLU TLU TLU TLU Normal Normal Accident Accident Output Instrument Calibration +/- % CS +/- Cal Units +/- % CS +/- Cal Units LT-107-12A(M) & B(M) Monthly 1.150 / 0.184 mAdc, 1.506 / 0.241 mAdc, (CTS)__ _ _ ___ _ _ _ LI-107-12A Monthly 3.187 3.187 % 3v354 3.354 % (CTS) __ _ _ ___ _ _ _ LT-107-12A(M) & B(M) Quarterly 1.181 0.189 mAdc/ 1.538 0 0.246 mAdclo (IT S) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Li-107-12A Quarterly 4.068 / 4.068 % 4.195 / 4.195 %,- __ __ __ __ _ _ _ _ _ _ _ _(IT S) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 5.2. Setpoint Evaluation 5.2.1. Current Low Level Suction Transfer setpoint As evaluated in Attachment C, section 5.1, the existing Low Level suction transfer setpoint of 4.64 mAdc (decreasing) cannot be supported based on the new requirements for critical height of submergence of the RCIC suction. The revised Process Umit of 2 26.5 from CST bottom [Ref. 6.14 and Attachment B] includes consideration for the TS requirement that the setpoint be > 3% and that there be 10,000 gallons reserve at the suction transfer point See Table 10 below. 5.2.2. Revised Low Level Suction Transfer setpoint A revised setpoint is evaluated In Attachment C, section 5.3; the proposed setpoint of 4.87 mAdc (decreasing) supports the requirements for critical height of submergence of the RCIC suction + 10,000 gallon reserve and has adequate margin from LSP to SP. See Table 10 below. Engineering Page 20 of 26 Yankee Design Vermont Yankee Design Engineering Page 20 of 26
" Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I "Condensate Storage Tank Level (ROIC) Monitoring VYC-706 Rev. I Table 10 Setpoint Results Existing Setpoint New Setpoint (CTS) New Setpoint (ITS) (4.64 rnA) (4.87 mA) (4.87 mA) Inches Inches Inches6 Inches7 Inches6 Cal Units7 Process Umit (PL) Ž26.5 v 18.5 Ž 26.5 2 18.5 2 26.5 218.5 Accident Uncertainty 5.885 5.885 5.885 5.885/ N/A N/A (Monthly Cal - U,12m) , Accident Uncertainty N/A N/A N/A N/A 5.989 / 5.989 (Quarterly Cal -U,2ai) , , Limiting Setpoint 32.385 24.385 32.385/ 24.385 32.489 24.489 (LSP) , , , . ,_, Setpoint (SP) 27.6 / 19.6 / 25.2 33.2 25.232 Margin (M1) -4.785 -4.785 A 0.815 0.815 V 0.711 0.711 / 5.3. Calibration and Test Results In order to support and Implement the results of this calculation, the loop instruments are to be calibrated at nine points based on the following ranges: Table 11 Module Calibration Ranges Description Value Units Transmitter Input range 4 to 394 Inches H20 Transmitter output range 4.0 to 20.0 m/Adc Indicator Input range (Cal current adjust) 4.0 to 20.0 mAdc Indicator output range Oto 100 / Trip Unit input range 4.0 to 20.0 m/Adc Trip Unit Lo Setpoint - Auto Suction Xfer 4.87 decr /Adc Test as-found tolerances (FT) and as-left tolerances (CT) are shown below. 6 Referenced to tank bottom. 7 As sensed bytransmitter; level above transmitertap (0 including 4" statc head. Engineering Design Engineering Yankee Design Page 21 of 26 Vermont Yankee Page 21 of 26
-Condensate Storage Tank Level (RCIC) Monitoring FVYC-706 Rev. 1 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Table 12 Module Calibration Tolerances As Found (FT) As Left (CT) Tag Number Calibration % CS +/- Cal Units +/-% CS l Cal Units LT-107-12A & B Operating Cycle 1.069 0.171 mAdcr 0.25 0.04 mAdc LT-107-12A(M) & Monthly (CTS) 0.250 0.04 mAdc 0.19 0.03 mAdc B(M) _ LI-I107-12A 8 Monthly (CTS) 2.0 2.0 % v 2.0 2.0 % LT-107-12A(M) & Quarterly (ITS) 0.375 0.06 mAdc 0.19 0.03 mAdc B (M ) _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ LI-107-12A 8 Quarterly (ITS) 3.0 3.0 % 2.0 2.0 % 5.4. Conclusions and Summary of Recommendations / 5.4.1. Revise setpoint to 4.87 mAdc decreasing. The setpoint is no longer based on simply being greater than or equal to 3% level as per TS Table 3.2.9. Based on tank vortexing effects evaluated under VYC-1844 Rev. 0, the limiting consideration is now based on maintaining a minimum level above the RCIC suction to prevent air entrainment due to vortexing, with the 10,000 gallon reserve requirement added. As such, the references in OP-4355 Rev. 14 to "Tech Spec Setting of 2 3%' and VY Trip Setting of '4%' should be revised to reflect the new bases. 5.4.2. For transmitter calibrations, only the Heise 901B (0-400') is acceptable as the pressure source. Both the HP 3466A and HP 34401A DMMs are acceptable for transmitter calibration. OP-4355 should be revised to incorporate the change in test equipment requirements. All calibrations should be revised to nine-point calibrations. 5.4.3. Applicability list for VYEM-0055 shows model number for LT-107-12A & B as 1153G85 instead of 1153GB5. Revise accordingly. 5.4.4. MPAC for LT-107-12A says Model Number is 1153G85 instead of 1153GB5. Revise accordingly. 5.4.5. Since there is no Analytical Limit (AL) associated with the RCIC CST Level Indication or suction transfer functions, evaluation of Allowable Value (AV) is not performed for this calculation. VYC-1 844 Rev. 0 [Ref. 6.14] determines the process limit for the low level suction transfer point based on system operability requirements. The process limit used for this calculation concurrently satisfies the existing Technical Specification requirement of a 3%. 8 Indicator tolerances rounded for readability. Vermont Yankee Design Engineering o YPage 22 of 26
Condensate Storage Tank Level (RCIC) Mon'Roring, VYCG706 Rev. 1 Condensate Storage Tank Level (RCIC) Monitoring, WC-706 Rev. I 5.5. VYDEP-15 Impact Considerations VYDEP-15 Section 2.1 [Ref. 6.5] requires that applicable alarm responses, standard and off normal operating procedures, and EOPs be included in the evaluation. This calculation will evaluate the accuracy of loop components, including Indicators and recorders where applicable. The accuracy determined by this calculation will be used as an Input for generic evaluations for alarm response, operating procedure, off normal operating procedure, and EOP impact. The interdepartmental review will also ensure associated procedures or operator interfaces are considered as an output of this calculation. Therefore, this calculation adequately addresses the impact to the License and Design bases of the plant as well as the Impact to plant procedure and operations. The following has been considered and is either addressed in this analysis or via the Inter-departmental review process: FSAR changes Technical Specifications (Custom & Improved Technical Specifications) Procedures Technical Programs Prints Related Design Basis Calculations (input/output) Design Basis Documents Based on the above, all Impact considerations of VYDEP-1 5 are addressed. Design Engineering Page 23 of 26 Vermont Yankee Design Engineering Page 23 of 26
'I
.Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Condensate Storage Tank Level (RCIC) Monitoring WC-706 Rev. I
- 6. REFERENCES 6.1. Instrument Uncertainty and Setpoints Design Guide," Vermont Yankee, Rev. 0.
6.2. "enmont Yankee Final Safety Analysis Report' Sections 2.3, 4.7.5, 11.8.3. 14.5.2, and Tables 1.7.1, 2.3.2, and 4.7.1. 6.3. "Vermont Yankee Technical Specifications", 314.2.9, and Tables 3.2.9/4.2.9 (through amendment 162) 6.4. WE- 03, Yankee Procedure, "Engineering Calculations and Analyses,' Rev. 18. 6.5. VYDEP-15, Vermont Yankee Project Procedure, "Calculations,' Rev. 2. 6.6. uVermont Yankee Environmental Qualification Program Manual," Rev. 36 (Excerpts - Attachment L). 6.6.1. QDR 5.2, Rosemount Model 510DU Trip/Calibration System, Rev. 5, through EQDI-98-115 (5/20/98) (Excerpts - Attachment E). 6.7. OP-4355, -RCIC - Auto Suction Transfer Water Level Functional/Calibration," Rev. 14, 09118/98 (Excerpts-Attachment K). 6.8. VYI 31/97, "ISP Application of Analyzed Drift Values in Setpoint Determination, Rev. 1,' Memo from G. J. Hengerle to File, dated 5/15197. 6.9. VYI 92/97, 'Application of CT, CE and A for Single Point Devices, Rev. 1,' Memo from G. J. Hengerle/R.T. Vibert to Distribution, dated 6/26198. 6.10. VYC-1614, Drift Calculation For Rosemount Transmitter Models 1151, 1152, 1153,' Rev. 0, 4/12/97. (Excerpts - Attachment G) 6.11. VYC-1615, "Drift Calculation For Rosemount Trip Unit Models 510DU & 710DU," Rev. 0, 415/97. (Excerpts - Attachment H) 6.12. VYC-1616, "Drift Calculation For Panel Mounted Electronic Loop Indicators,' Rev. 0, 9/17197. (Excerpts - Attachment 1) 6.13. VYC-1758, 'Measuring & Test Equipment Uncertainty Calculation,' Rev. 0 (Excerpts - Attachment J). 6.14. VYC-1 844, CST Vortexing Effects on level measurement," Rev. 0 (Excerpts - Attachment B). 6.15. VYEM-0052, "Rosemount Trip/Calibration System," Rev. 1, 7/22/92. 6.16. VYEM-0055, "Rosemount Nuclear Service Pressure Transmitters - Instruction Manual, Model 1153 Series B,' Rev. 2, 9/20/95. 6.17. VYEM-0196, "Series 1151 & 1251 Instruments, Installation, and Maintenance Instructions," Rev. 1, 8/14/95. 6.18. International Instruments Test Report #SBI-3, 'Seismic Qualification Test Report for Indicating Control Instrument Model 9270 and Meter Models 1122, 1136, 1151," Rev. 1, February 10, 1976, (Excerpts - Attachment F) Vermont Yankee Design Engineering Page 24 of 26
-1
- Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 6.19. GEK 9614, Operation and Maintenance Instructions, Reactor Core Isolation Cooling System, dated 12170.
6.20. GEK 32441, Process Instrumentation Subsystem of the Reactor Core Isolation Cooling System, dated 10170. 6.21. GE Document No. 257HA351, "Reactor Core Isolation Cooling System - System Design Specification," Rev. 2, 3125169. 6.22. GE Document No. 257HA351AK, "Reactor Core Isolation Cooling System - System Design Specification & Data Sheet," Rev. 3, 611517O. (Excerpts - Attachment L) 6.23. Control Wiring Diagrams 6.23.1. Drawing 8-191301 Sheet 866, *ECCS Analog Trip Division II, SH. 2," Rev. 7. 6.23.2. Drawing B-191301 Sheet 1177, *RCIC Alternate Shutdown System,' Rev. 3. 6.23.3. Drawing B-191301 Sheet I180, "RCIC Logic System SH. 1," Rev. 16. 6.23.4. Drawing B-191301 Sheet 1195, 'RCIC Pump Suction From Suppression Chamber Valve VI 3-39,' Rev. 14. 6.23.5. Drawing B-191301 Sheet 1196, *RCIC Pump Suction From Supp Chamber Valve V13-41," Rev. 15. 6.24. Flow Diagrams 6.24.1. Dwg. G-191176 Sh I of 2,'Condensate & Demineralized Water Transfer System," Rev. 36. 6.24.2. Dwg. G-1 91174 Sh I of 2,"Reactor Core Isolation Cooling System," Rev. 33. 6.25. Vendor Drawings 6.25.1. Drawing 5920-0605, 'Process Diagram, Reactor Core Isolation Cooling," (729E949), Rev. 3 6.25.2. Drawing 5920-1926, 'Elementary Diagram, RCIC System,' Sh. 3, (730E283), Rev. 19. 6.25.3. Drawing 5920-1929, 'Elementary Diagram, RCIC System,' Sh. 6, (730E283), Rev. 19. 6.25.4. Drawing 5920-6041, 'Condensate Storage Tank Instrumentation Racks (RK 25-66 & 66A)," Rev. 1. 6.26. Miscellaneous Drawings 6.26.1. Drawing G-1 91259, 'Misc. Instrument Arrangement,' Rev. 0. 6.26.2. Drawing 8I-191 260, Sheets 107.2, Vermont Yankee Instrument Ust, (Superseded by MPAC). 6.26.3. Drawing G-191261 Sheet 658, "Tank Level Instrument Hookups,' Rev. 6. Page 25 of 26 Vermont Design Engineering Vermnont Yankee Design Engineering Page 25 of 26
"Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Condensate Storage Tank Level (ROIC) Monitoring VYC-706 Rev. I 6.26.4. Drawing B-191265, Sheet 4 of 6, Reactor Building Instrument Arrangement, Rev. 20. 6.26.5. Drawing B-191259, "Misc. Instrument Arrangement," Rev. 0. 6.27. OASME Steam Tables," Thermodynamic and Transport Properties of Steam, Sixth Edition, 1993. (Excerpts -Attachment L) 6.28. AP-01 50, "Conduct Of Operations And Operator Rounds", Rev. 31, 7/1596, through Dl 98-388. Ven-nont Yankee Design Engineering o YPage 26 of 26
12/09/1998 10:59 5182510180 ANDERSON M OR S PAGE 01
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CALCULATION/ANALYSIS REVIEW? CALCULATION NO. VYLf- ' h _ REVISOIQI NO. 4I COMMENTS RESOLUTION LVreAhSU. tf044.5 C&S5, aP4s Awv> bmrvaoAi//-/8f 4v r.pweS. b Y 3 9_A_______ IL v&Il . - /6- vo7?Suw dt VA3-8At> z,<
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(OI As-s -.AL Vie*W01, on &Y est 11 C., AL ts '{- o.o4" t C° c..S.., 4 .r 4g l-CA; 1r ,- Pb Identify method(s) of review: (& '/v 006tw zv
*A Calculetion/analysis review O Alternative calculational method O Qualificatlon testing Resolution By:
%PrepareriD6{e Comments Continued on/ age: t Concurrence with Resolutlo.- CFt 0*g
'Revfwer/Daee WE-103-26 FORM UE.103-3 Revision 5
12/09/1998 10:59 5182518188 ANDERSON M OR S PAGE 82 N
- y=Wj!-~* 04 CALCULATION/ANALYSIS REVIEW CALCULATION NO. REVISION NO. _ _
COMMENTS RESOLUTION s J f]5 (4-J N/&.16 A lIf Z - )
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-L4yVI meho4s)ofrevew 3717/P/ -V
- Calculation/analys1s review O Alternative calculat1onal method O Quallffcatlon testing Resolution By: -d 2 L4JW9sV
'reparer/Doe Comments Continued on ge:
Concurrence w1th Resolut1on c*0. 4/k.f" [ Rev1 re-r/Dae WE- 103-26 FORH WE-103-3 Revision 5
-1 APPENDIX B WE-103 REVIEW CHECKLIST Preparer _ Reviewer (please print) 4 AC (please print) C ML Organization Organization VytEg 5 4 qA. WF3 sae.4 signature Signature Vate 9 / / ' Date _______________°
- . /
Requirement Preparer Reviewer Ensure the title page is appropriately filled out.
- Correct number of pages.
- OA Record filled out. I Record number filled out (13.CO9.001 included if microfiche or hard copy of computer runs are attached to the calculation).
- Descriptive title.
I Plant. cycle number and calculation number included. N/A' can be used for plant and cycle number. Signatures and dates are included. and are in correct chronological I order. Print the name and individuals' organization (if other than YAEC) below the signature. The title page reviewer and approver dates do not pre-date any date in the calculation except for changes containing that Individual's Initials and date.
- All WE-108 computer codes and other keywords not in the title which can be used to retrieve the calculation are listed In the keyword field. 'v4AJo-Ensure the Form WE-103-2 is included and properly completed when a computer code is used. ,Q4 Ensure Form WE-103-3 is included, and has signatures/dates from both the preparer and the reviewer and that all comments have been addressed. If no comments. use the following statement: 'Reviewed in accordance with WE-103 with no comments."
Ensure review of the calculation can be done without recourse to the originator. N/A Ensure computer codes are used in accordance with WE-103 Steps 4.1.4.4 through 4.1.4.6. Ensure the calculation includes a title page. objective. method. inputs. assumptions. calculations. results. conclusions and references. Ensure the inputs are referenced to formal documents. e.g.. WE-103. The reference cannot be a YAEC report unless formal QA records are checked and also referenced. N/A Ensure design input internal and external correspondence is prepared and reviewed, and is. therefore. a QA record. If there is only one signature on the correspondence. verify that it is a QA record. N/A WE-103-B-1
. ffi APPENDIX B WE-103 REVIEW CHECKLIST (Continuted)
Cv Requirement Preparer Reviewer Ensure that if design specifications were used as-input to the calculation, the performance characteristics are verified In writing by the provider of the component/product or by cognizant YAEC/plant personnel. AL4 V/A Ensure that input and modeling uncertainties are explicitly addressed in the calculation. Ensure that the applicable input considerations from WE-1OG. Table I have been incorporated and are explicitly addressed within the 4- N/A calculation. N/A Ensure individuals responsible for each portion of the calculation are identified when multiple preparers and/or reviewers are utilized. Page initialing is optional. even in the cases where initial boxes are provided on the pages. Ensure each page has a page number and the calculation number and revision number, If applicable. Dates on each page are optional. Ensure that every page of every attachment (or Appendix) contains its attachment (or Appendix) number. Ensure corrections are addressed in one of the following approaches:
- Retyped and identified by a vertical line with revision number. if applicable. in the right margin: OR
- Lined out. Initialed and dated by preparer: OR
- Photocopy of original to eliminate any previous correction tape.
whiteout. or erasures. Ensure enhancements and clouding are initialed and dated. Confirm legibility meets WE-103. Appendix A. Specific pages can be exempt If they are: (1) documents received from another organization who is the original QA custodian, or (2) supplemental pages included for information only. In these two cases. make sure a memo was issued to RMS per WE-002. Section 3.4.3. Review of IOCFR50.46 reporting requirements has been documented for 4- 'VP- - analyses which assess conformance with IOCFR50.46. A/4 N/A Ensure computer codes are validated for the computing environment. NIA Ensure script files are Included in the calculation or referenced to another calculation. Also. ensure the preparer identifies how the code/script was run. l/A Ensure applicable outstanding Condition Reports (CRs) have been reviewed for influence on the calculation and note review In calculation. N/A Ensure relevant conditions/limitations have been reviewed for their effect on this calculation and the review is noted in the calculation. VEMcYNKNTDEMGNHG wc~lKwc ?64' ) RMMMkNNO 7e4 KE"ayak-WE-103-B-2
02/04/99 TU :10:o00 FAX 18022585771 VT Yankee Nuclear Power ZJ002 VERMONT YANKEE SEIPOINT CONTROL PROGRAM "EGONTEYDESGNENGNIEING INTERDEPARTMENTAL REVIEW OF CALCULATION: NO W 57cG REMISIONNO. I VYC- 706 Revision I ATMACMENT_ PA:gI OF VYC-706 Revision 1, has been prepared and independently reviewed. The Departments Impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recommendations, and document the departmenuCs acceptance prior to the calculation being approved.
- 1. Surnrg: This calculation evaluates the uncertainty for the Renctor Core Isolation Cooling (RC!C) Systerm Avto Suction Transfer on Low CST Level as well as the RCTC alternate shutdown CST Level Indication Loon for normal and Post Accident conditions. The loop components evaluated are as follows:
LT-107-12A & B, LT-107-12A(M) & B(M), and L[-107-12A
- 2. Calculation Open Items: AP-0028 to be Assigned None
- 3. DcatmentReview - contact he Setpoint Program Marnager (G. Hentcrle) if not in agreement with the conclusions/statements.
3.1. Vermont Yankee E&C 3.1.a. The Calibration Sections of OP-4355 for LT-107-12A & B. LT-107-12A(M) & B(M). and LI-107.12A will require the following changes based on CTS and mont;ily calibrations for the indicator and trip units: I. Add to procedure OP-4355 as follows: L LIniting Setpoint (LSP): 8 Iev./9 CTS LT-107-12A(M" & B(M) 32.315S inches * (4.$/-VmnAdc)
- Referenced to Tark Bottom (equivalent to 24.365 inches applied at transmitter)
- b. LT-107-12A &: TrBnsmitter Module Calbration As-Found A:-Fo7nd LT-107-12A & B +/-0.171 mnAdc
- c. LT-107-12A(M) & B(M) Trip Unit Module Calibration As-Found As-Found i* o.,P Auto Suction Transfer (Monthly Cal) :mR3-Adc .r I--I'
- d. LI-107-12A Indicator Module Calibration As-Found:
As-Found LI-1 07-12A (Monthly Cal) ;L 2.0 'Ae
- e. Revise Head to reflect: NIA
- f. Revise thc M&TE requirements ofOP-4355 to remove thc Heisc 730A-03.
The following test equipment (or equivalent) is recommended for use: Gauge Heise 901B (0-400 inwc) DMM HP3440SAor3466A
02/04/99 THU 10:00 PAX 18022585771 VT Ynkee Nuclear Power z0l03 Vermont Yankee Setpoint Control Prograrn lnterdepartnental Review of Calculation VYC-706 Rev. I
- 2. In the body of OP4355 and the data sheet rcvise as follows:
- a. Module Calibration Tolerances From -ToON LT-107-12A & B i 0.04 mAdc Nochange LT-107-12A(M)& B(M) +/- 0.06 mAdc
- 0.03X5Aidc* >,, ,, ,ZA LT-107-12A :*2.0 % No change Per calculation section 3.3.1.2, the tightening of the calibration tolerance is based on past performance and trip unit repeatabllity.
- b. Trip Setpoint LT-107-12A(M) & B (M) F6romA TO Auto Suction Transfer 4.64 rnA 4.87 mAdc'
- Indication at trip point Isapproximately 5S% (5.44 % rounded to nearest I "cA for readability)
- c. Revlse calibration data to reflect head correction of: N/A VMIONT YAME DESIGN ENGINEERING
- d. Insert a 9-point module calibration for the following iteuments: CALHAlON NO. VYC- 70cC Thnsmtacr Uvel Iridcto REIlStONNO. ._ I LT4O-1 2 tAt B-107Z12
,h ATTAC'UENT 0 PAGE . .OF27 Input Ouqtut Inpux Output 394.0 jnWC 20.0mA 1T4 9o.0' 296.5JPWC -6.Om 16.0t 75.0%
199.0 inWC I2AOniA I.Om- 30.0ph 103 InWC 8.0 mA 25.0 OA 4WC 4.0 iA 5.6 mA 10.0 $ 3.1.b. Tle following commentsrecommendations apply: Concur
- 1. None Sign & Date 1 VetmoV YajeKIM xCfSnltWve / /
3,2. Vermont Yankee Reactor Engineering 3:2.a. None Sign &D)ate _ __ ___ /__ Veimont Yankee RE Represertative
*3.3. Vermont Yankee Operations 33 .a. OP-3126xppendirC step 10. reqdiresthe operatorto zshOl RCPCpump suction to the supprf sion pool when LI-107-12A Indicates 5S. Basedon the new minimum vortcxingheightrequirement of
Ž26.5" above CST bottow (YYC-1844), andcakoulated normal TLUfor the indication loop, manual ironsfer of RClC must occur Ž$7% indlcagedlcvel (Ž38.93"above CSTbotrom and roundedfor Indicatorreadab lity) to cnsure )C1Cpu-nsp suction is not compromised. Recommendrevising OP-3126,AppendirC CST Level Indicationa tranrferto Ž 7.
02/04/99 T}1U 10:01 FAX 18022585771 VT Yankee Nuclear Power lQ 004 1 Vermont Yankee Setpolnt Control ProgrRM Interdepartmental Review of Calculation VYC-706 Rev. 1 VEMONT I DESIGN ENGINEERJNG CCIIIATiAINjn 11r'7V, or Da1- I QRqv.20 VW -Zd_ $v SCon ATTAcHMENr Q PAGE. tOF_7 Sign & Date rI / ?1/5 Vermont Yankee Operations Representative 3.4. Vermont Yankee Systems Manager Cone'r Commet 3.4.a. 7l*is analysis supports the design basis for the RCIC System fA__,_ ____ and the Condensate DWrinerallzed Uaterl'rahsfer System. Sign& Date 144h9 V tan1teY VngineEng Rpe resentatlve 3.5. YNSD NuclearEngineering Concur Comments 3.5,a Custom Technical Specifications (After setpoint change to 4.87 mA)
- 1. Process Limit used in auto-ansfer setpoint evaluaton: 2 265 incbes 1
- 2. Potential Normal Trip Point CST Level 28.75 inchess
- 3. Potential Accident Trip Point (LOCA) CST Level - 27.34 inches' It
- 4. Potential Accident Trip (HELB): - N/A 3.5.b. Improved Technical Specifcations (After setpolnt change to 4.87 MA)
I. Process Limit used in auto-tnsfer setpoint evaluation: 2 265jnches 0
- 2. Potential Normal Trip Point CSTLevel228.61 nches*
- 3. Potential Accident Trip Point (LOCA)* CST Level = 27.23 inches*
- 4. Potential Accident Trip (HELB): WIA O Referenced to Tank Bottom
' Small break LOCA with Seismic Sign & Date /
DNBED Rcp-sentativc 3.6. Vermont Yankee DBD Manager Yes No 3.6.a. Whc Emergency Diesel Gederator DBD should reference this analysis. The DB3D Is complete (an AP-M28 to follow) O l The DBD is not completo. Incorporate reference to thlis analysis as 0 G appropriate. / Sign & Date - ZA 2-Y4 '
?SP Prvgan Manager 3.7. Vermont Yankee Lieonsing Impact Yes No 3.7.a. FSAR Changes (AP-0028 to follow) None 0 a Note: Based on revisedprocesslimit requfremCntS of 'YC-1844 Rev. O,the 7Srequirem"en of 23 Is no longerthe limitingconsideratlonIn setpolntdelermninallon. he S requiremenrof2 3& Li consideredto be satisfied concurrentlywith salsfactlon ofthe minimum vortexcng level requirement (ProcessLimit).
02/04/99 THU 10:01 FAX 18022585771 0~oo VT Yankee Nuclear Power YMMOWYANKEEUESIGNENGINEEING Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-706 Rev. I CALCRAXINN1. 70G YesRISIONNO. 3.1.b. Olher impact on licensing basi:s: tNone ci bCHlMElZ 0 PvGEJYOF Sign & Date ; / Žwv-S 40 og mr;fn anager 3.8. Vermont Yankee ITS Manager Yes No 3.8.a. Tlis analysis provides an input to the ITS. An Allowable Valuc applies. 0 a Allowable Value N/A 3.8.b. This analysis provides an inpmt to Technical Requirements Manual. Jncorporate as appropriate. N/A Sign & Date / . (/_Sj Pr Maaer 3.9. Other Department(s)/Progm=(s)ANone Concur 3.9.a. Impact assessment/reconmnend iations: hA 0-Sign & Date _ :, 0 / 2- 's:59
'1SP Pr Manager
- 4. Setpoint Program Manager Comp leted 4.1. Concurs with above.
4.2. IDterdeparinental Review form (copylsteps I through 3) incotporuted 0t into calculation. 4.3. Calculation has been approved. Approved on 4.4. AP-0028 commitmtents have been assigned and forwarded for Incorporation into the Commnltment Thcking System. Sign & Date
~ISP Prgi Manager S. Post-Approval Requirements
- a. E&C (perfon as appropriate):
- Initiate AP0022 Setpoint Change Request AP0028 VWe-070620I /O
- Update MPAC
- Revise calibration/functional/logic test procedure
- Inform the following after changes are implemented:
- Setpoint Coordinator
- Setpoint Program Manager
- Training (notified via AP-0022 if initiated)
- Operations (notified via AP-0022 If initiated)
- Design Engineering
- b. Setpoint Prograrn Manager: Update Program Manual AP0028 V/)/ 6 70oRC1 I- 0 z (after step S.a).
- c. Setpoint Coordinator: Update Setpoint Data Base AP002S VVdo/y7o e Pco I -O3 (after step 5.B)
02/04/99 THU 10:01 FAX 18022585771 VT Yankee Nuclear Power
-W ONTWKEE0ESIGN 9GEIN Vennont Yankee Setpoint Control Progrnx c&MATINo Wc 7o(
Interdcpartmental Review of Calculation VYC-706 Rev. 1.I_
- d. DesignEnginweing: Initiate FSARJDBD changes. APOOU2 ________________________
as appropriate (if DBD has been completed Comments: -s -
02/04/99 THU 10:01 FAX 18022585771 VERMONT YANKEE DESIGN ENGINEERING CALCUILlON NO y, 0~ Phillips, David RnSONNO. From: Hengerle, George ATACHMEN`AC Sent: Tuesday, January 05, 1999 8;07 AM To: 'brianfd~eroIs.com'; Phillips, David
Subject:
RE: WC-706-Rcsolutlon to Plant Comment Brian: Thank you for the quick turm around. The only change to the IRF Is the AS LEFT (from 0.032 mnA to 0.03 mA), the AS FOUND (0.035 mA to 0.04 mA) and the Umiting Setpolnt (from 32.385 Inches (4.835 mAdc) to 32.385 Inches (4.84 tnAdc). Dave: A revised IRF is attached. Please, either pen & Ink the changes to the one you have or replace the attached version. The body of the text and the MathCad attachments will change slightly (also attached). The changes stilI need to be Independently reviewed. However, I looked them over and believe they are good such that the department reviews should not be held up. Thanksl GJH -Original Message-From: Brian F. Davidson [mallto:brlanfd~erols.com] Sent: Monday, January 04,1999 8:39 PM To: george.hengerdetvynpc.corn
Subject:
VYC-706
- George, Attached are the revised Word File, MathCad (Attach C), and Interdepartmental Review Form for VYC-708. As we discussed earlier. I had to adjust the as-left (CT) for trip units to 0.03 ma versus 0.032.
I also had to adjust the as-found (e-test) to 0.04 ma versus 0.035 ma (CTS) and 0.08 ma versus 0.058 (ITS). Also, since the trip unit normal and test uncertainties are equal, I also had to adjust the normal uncertainties up to 0.04 and 0.06 respectively since we should not have etest larger than e-normal. Accident module uncertainties were also affected similarly since ea2RQ = en2RQ and ea2RM = en2RM (sections 3.3.2.3.1 and 3.3.2.3.2). Based on these changes, most of the MathCad file changed, albeit only slightly. The end results show an Increase In normnaVaccident TLU of only 0.03 inVWs, and thus, the existing calculated setpoint of 4.87 Is still acceptable. The only changes to the Word Doc are In Tables 9, 10, and 1?. The changes to Mathcad Attach C were in sections 3.3.1.2, 3.3.2.1.1, 3.3.2.1.2, 3.3.221, 3.3.2.2.2, 3.3.2.3.1, and 3.3.2.3.2 on pages 8, 11, and 12 of 31. These changes resulted in a ripple effect through the rest of the MathCad computations in sections 4.1.1, 4.1.3, 4.2.1. 4.2.3, and In the results and conclusions sections 4.5, 5.2, and 5.3. New originals of all affected pages went out to Mike Anderson via FEDEX Ovemight and should be to him by tomorrow mominglaftemoon depending on his local delivery. In hindsight, we could have probably gotten away with simply rounding the As-Found and As-Left values as requested and recognizing the fact that the impact is so minor (0.03 inWC) compared to the existing margin to selpoint in eal cases, however, you would lose the explanation and connection to the limiting Indication on the calibration readojt assemblies which I've added In the associated sections.
VERMONTYANKEE DESIGN ENGINEERING V CALCULATION NO. VYC- 76( RE'ASION NO. l ATTACHMENT PAE 7F 1/~ >;46 a44h4 /- el~ 1-7-- gogg/.2- A// Z.S,/.Z ,0 Z 3JsZ.Z,/ f i/7 I&Do,;,/;,, 1
/g~rT/,/IC, Io --
7 4-. qC/ 66 /1- 6t ______
CONDENSATE STORAGE TANK LEVEL (RCIC) MONITORING LT-107-12B -- LT-107-12B(M)
~13A-K46 CP 2548 l RK 25s4A CONDENSATE r-------J II STORAGE TANK s LT-107-12A.- -LT-107-12A(M) _------
TK-4-IA _ RK2MA C2548 13A-K47 LI-107-12A V13-39 V13-41 CP 821 THIS FUNCTIONAL ARRANGEMENT APPLIES TO THE FOLLOWING LOOP: VYC-706 REV. I LT-I07-12A, LT-107-12A(M), LI-107-12A, 13A-K46 ATTACHMENT A LT-107-12B, LT-107-12B(M), 13A-K47 PAGE I OF I
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 1 of 31 Calculation Index Page 1.0 Loop Calibration Conditions 2 2.0 Process Measurement Effects 3 3.0 Module Uncertainties 4 3.1 Primary Element (e.) 4 3.2 Transmitter LT-107-12A and LT-107-12B (Module 1 -el) 4 3.2.1 Transmitter Uncertainty Elements 4 3.2.2 Transmitter Total Module Uncertainty 7 3.3 Master Trip Unit LT-107-12A(M) & B(M) (Module 2 - e2 ) 7 3.3.1 Trip Unit Uncertainty Elements 8 3.3.2 Master Trip Unit Total Module Uncertainty 11 3.4 Indicator U-107-12A (Module 1 - ej) 13 3.4.1 Indicator Uncertainty Elements 13 3.4.2 Indicator Total Module Uncertainty 16 4.0 Total Loop Uncertainty 17 4.1 Master Trip Unit Auto Suction Transfer TLU - Monthly Calibrations (CTS) 17 4.1.1 Normal Conditions 17 4.1.3 Accident Conditions 18 4.2 Master Trip Unit Auto Suction Transfer TLU - Quarterly Calibrations (ITS) 19 4.2.1 Nonnal Conditions 19 4.2.3 Accident Conditions 20 4.3 CST Level Indication Loop TLU - Monthly Calibrations (CTS) 21 4.3.1 Normal Conditions 21 4.3.3 Accident Conditions 22 4.4 CST Level Indication Loop TLU - Quarterly Calibrations (ITS) 24 4.4.1 Normal Conditions 24 4.4.3 Accident Conditions 25 4.5 Summary of Results 26 4.5.1 Module As-Left Calibration Tolerances (CT) 26 4.5.2 Module As-Found Calibration Tolerances (FT) 27 4.5.3 Monthly (CTS)NormallAccident Total Loop Uncertainty (TLU) 27 4.5.4 Quarterly (ITS)Normal/Accident Total Loop Uncertainty (TLU) 27 5.0 Setpoint Evaluation 28 5.1 Setpoint Requirements 28 5.2 Evaluation of Current Setpoint 29 5.2.2 Conclusion 29 5.3 Evaluation of Revised Setpoint 30 5.3.1.2 Conclusion 30
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 2 of 31 Service: Condensate Storage Tank Level (RCIC) Monitoring Equipment l.D.: LT-107-12A & B, LT-107-12A(M) & B(M), LI-I07-12A 1.0 Loop Calibration conditions psi := 1b inr2 inWC, 1 27.7276 psi LRL:= 125inWC LRL = 125.0 einWC Transmitter Upper and Lower Range Limits URL:= 750-inWC URL = 750.0 .inWC CS min' 44inWC CS max := 394-inWC CS := (CS max - CS min) CS = 390.0 inWC X A Transmitter calibrated span in inWC from OP-4355 [Ref. 6.7]
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 3 of 31 2.0 Process Measurement Effects The o nly process measurement effects associated with these channels are due to density changes over the credible range of CST fluid temperatures of 40oF to IOOOF (calculation Table 3). v = specific volume at given CST temperatures L = height of water In CST being monitored PM = process measurement error due to density changes 0.01605 = specific volume of water at 700F (Ref. 6.27) and 15 psia v 40 := 0.01602-ft3 lby1 Specific volume at 400F [Ref. 6.27 p. 229] W/ v 70 := 0.01605-fl?-1b 1 V Specific volume at 700F [Ref. 6.27 p. 2291 V 100 := 0.01613-f 3*1b-t Specific volume at 100IF [Ref. 6.27 p. 229] n:= 0 4 Ln := ((n.97.5)..+4).inWC PM pos := L- 40-L Positive process measurement error resulting nV70 from a change in temperature from 700F to 400F. PM neg v 100 7 L 7 L Negative process measurement error resulting n n V70 n from a change in temperature from 70oF to
%Level := n 25% LI 100F.
As Indicated in Ref. 6.1, section 3.1, a negative process measurement bias error indicates sensed level is less than actual level. Conversely, a positive process measurement bias error indicates sensed level is greater than actual level. Since these errors are fixed errors, they will be algebraically added to the statistical errors.
VYC-706 Rev. I ATTACHMENT C Calculation Dtaill CST Level (RCIC) Monitoring Page 4 of 31
%Leveln PM neg PM pasn n
Positive and negative process measurement 0/0 inWC InWC inWC bias errors at 0, 25, 50, 75, and 100% level over 0 -0.020 L 4.0 0.007 / the calibrated range of LT-107-12A/B. 25.0 -0.506 & 101.5 0.190 a/ 50.0 //
-0.992 to 199.0 0.372 V/
75.0 -1.478 v 296.5 / 0.554 a/ 100.0 -1.964 394.0 0.736 i/ 3.0 Module Uncertainties 3.1 Primary Element ( eO) There is no primary element associated with the measurement of CST level. 3.2 Transmitter LT-107-12A and LT-107-12B ( Module I - es) CT 1 := 0.25-%-CS CT I = 0.975 *inWC Z Calibration Tolerance In equivalent inWC CT j.16/ CT mA:: CT MA= 0.04 / Calibration Tolerance = 0.04 mA per Procedure OP4355, Rev. 14 hC := 4-inWC There is 4 inches static head at the transmitter zero point. 3.2.1 Uncertainty Elements 3.2.1.1 Reference Accuracy (A) A 1 := 0.25-%-CS A I = 0.975 einWC / Accuracy includes combined effects of hysteresis, linearity and repeatability (see Table 5). 3.2.1.2 Calibration Effect (CE) CE= CT= A Since these transmitters will be calibrated with a Where: full traverse Increasing and decreasing, CE will CT = Calibration tolerance of transmitters equal CT (per Methodology Section 3.6.2.C). A = Instrument Reference (vendor) accuracy CT I = 0.975 -inWC CE i :=CT i CE 1 = 0.975 -inWC 4/ Transmitter Calibration Effect
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 5 of 31 3.2.1.3 Dead Band (DB) There is no deadband for Rosemount 1153 DB I:= 0-inWC transmitters per Table 5. 3.2.1.4 Measurement & Test Equipment (MTE) The M&TE uncertainty should be less than or equal to the reference accuracy of the device being calibrated [Ref. 6.1] MTE = (M12 + Mr22)"2 Where: A = Accuracy of the Transmitter In this section, the required accuracy of the CS = Calibrated span of the Transmitter pressure measurement is calculated based on the MI, m2 = Uncertainty of input and output test instrument in mAdc accuracy of the mA measurement. Mr, M2 = Uncertainty of input (M1) and output (M2) test equipment in inWC MTE = M&TE uncertainty in inWC Test equipment uncertainties from Table 8 A I = 0.975 .inWC Accuracy of Transmitter = 0.25% CS m I := 0.0197*mA m 1 = 0.0197*mA mAdc accuracy for 3466A @ 20 mAdc [Table 81 M 1: 1-m -CS M I = 0.4802 *inWC /O Milliamp measurement uncertainty in inWC. In order for total M&TE uncertainty (MTE) to be less than or equal to reference accuracy (A), the limiting accuracy of test gauge(s) used for the transmitter calibration is found as follows. MTE is set equal to A = 0.975 inWC. MTE:= A MTE = 0.975 .InWC M 2 := ,MTE 2 -M 2 1 M 2 = 0.849 inWC / For this evaluation of the potential test equipment listed in Table 8, only the gauges with accuracies better than or equal to 0.849 inWC will support the requirement for M&TE uncertainty better than or equal to 0.25% span (0.975 inWC). The only pressure gauge with an accuracy less than 0.849 is the Heise 901 B (0-400 inWC). MTE 1 o~inWC 0.0= MTE 1 0.000inWC Transmitter MTE uncertainty is included in the
= Analyzed Drift term (Assumption 2.3.18).
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 6 of 31 3.2.1.5 Analyzed Drift (DA) DA lo:= 1.0407 % DAI%= 1.041*% Transmitter drift in % (Assumption 2.3.12) DA 1 := DA 1 %.CS DA I = 4.059 *inWC v/ Transmitter drift in inWC 3.2.1.6 Temperature Effect (TE) TE', = TE81 = 0.0 inWC Temperature effect during normal and accident conditions are the same and included in the Analyzed Drift term (Assumption 2.3.18) TE := 0.0InWC TE I = 0.000 'InWC 3.2.1.7 Barometric Pressure Effect (PB) Barometric pressure effect is either the effect on the vented side of gage pressure The 1153G35 Is a gage pressure transmitter transmitters, or the error associated with calibration of an absolute pressure transmitter monitoring a tank vented to atmosphere, therefore using gauge pressure test Instruments. this effect Is negligible per Ref. 6.1 section 3.6.8. PB 1 := 0-inWC 3.2.1.8 Humidity Effect (HE) Humidity effect during normal and accident HE :- 0inWC conditions are the same and Included in the associated Analyzed Drift term (Assumption 3.2.1.9 Radiation Effect (RE) 2.3.18) REal = REn1 = 0.0 inWC Radiation exposure at the CST is negligible and assumed Included In the Analyzed Drift term (Assumption 2.3.18) RE I := 0.0olnWC RE I = 0.000 .inWC 3.2.1.10 Seismic Effect (SE) SE 1 := o.5*%*URL SE I = 3.750.inWC / Seismic effect from Table 5 & Attachment D 3.2.1.11 Process Pressure Effects (SP) Since the maximum pressure felt by the transmitter Is 394 inWC+ ambient pressure, static pressure and over-pressure effects and SP i := 0.0 InWC SP 1 = 0.000 'inWC corrections for this application are not applicable
vyC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 7 of 31 3.2.1.12 Power Supply Voltage Effect (VE) Power Supply Voltage Effect during normal and accident conditions are the same and included in VE1 := 0.0 inWC VE 1= 0.000 inWC the Analyzed Drift termn (Assumption 2.3.18) 3.2.2 Transmitter Total Module Uncertainty 3.2.2.1 Normal Conditions CE i = 0.975 einWC DB I = 0.000 *InWC MTE, TE, PB, HE, RE and VE are included in DA I = 4.059 *InWC Analyzed Drift term (Assump. 2.3.18), SP = 0. enlR :=CE1 112DA 12 e n.1 R = 4.174 oinWC Normal transmitter module uncertainty (erlR) for calibration every 684 days 3.2.2.2 Testing Conditions MTE, PB, TE, HE, RE and VE are included in etlR:= CE1 2 I-+DB1 DA1 2 Analyzed Drift term (Assump. 2.3.18), and SP = 0. Testing transmitter module uncertainty (etR) e tl R = 4.174.inWC / for calibration every 684 days 3.2.2.3 Accident - LOCA (small break) with Seismic &without Radiation CE I = 0.9756 inWC DB I = 0.000 -inWC DA 1 = 4.059 *inWC SE I = 3.750 *inWC MTE, PB, TE, HE, RE and VE are Included In the Analyzed Drift term (Assump. 2.3.18), SP 2 i-DA 2 iSE 2 = 0, and mild environments. e a1R :=JCE 1 2DB 1 1 Accident transmitter module uncertainty (ealR) ea1R = 5.611 einWC / for calibration every operating cycle (684 days) 3.3 Master Trip Unit LT-107-12A(M) & B(M) (Module 2- e2) CT 2mA:= 0.06 mA CT 2mA = 0.06 *mA Existing Calibration Tolerance in mAdc per OP-4355 [Ref. 6.71 and Table 6. CT 2mA 2%:16-mA CT 2% = 0.375 0% Z Calibration Tolerance in % span
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 8 of 31 3.3.1 Uncertainty Elements 3.3.1.1 Reference Accuracy (A) A = (AX 2 + h2 1 12 + r2) 2 Where: A = Reference accuracy of instrument AX = Vendors stated basic accuracy expression h = hysteresis I = linearity r = repeatability AX 2 := 0o%-CS 12:= 0 %.CS h22%= oCS r2:= 0.200-%-CS Repeatability spec for "Normal-High" environment per Assumption 2.3.20 and Table 6. A 22:= AX 2 21+h 2 +1 2 2 + r 2 2 A 2 = 0.780 *inWC Master Trip Unit Accuracy in inWC 2 A2% := A 2 A 2% = 0.200 a% / A 3.3.1.2 Calibration Effect (CE) CE= CT=A Where: Since these master trip units are single point CT = Existing Calibration tolerance of master trip units devices, CE will equal CT [Ref. 6.91. A = Instrument Reference (vendor) accuracy A 2 = 0.780 -inWC Existing calibration tolerance CT 2mA := 0.06-mA CT 2 %= 0.375*% As stated in Reference 6.1 section 3.6.2, if the as-left calibration tolerance (CT) Is larger than the vendor's stated accuracy of the device, then the accuracy cannot be adequately verified during calibration. Following review of raw calibration data (Attachment H)for LT-107-12A(M) and B(M), it is apparent that the trip unit as-found and as-left data has consistently been less than 0.03 mA (0.1875%); the Calibration Tolerance will be revised to 0.1875% such that CT will be slightly less than A and provide a tolerance consistent with calibration readout assembly readability to 0.01 ma. CT 2% := 0.1 875- % CT 2% = 0.1 875 *% New Trip Unit Calibration Tolerance in %
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 9of fl CT 2 := CT 2%*CS CT 2 = 0.731 oinWC New Trip Unit Calibration Tolerance in inWC -- CE 2 := CT2 CE 2 = 0.731 -inWC Trip Unit Calibration Effect In inWC 3.3.1.3 Dead Band (DB) Deadband for the trip unit is associated only with DB 2 := 0.0-inWC DB 2 = 0.000 sinWC the adjustable reset band of the trip setpoint [Table 6 and Attachment El and is not a concern for this calculation. 3.3.1.4 Measurement & Test Equipment (MTE) The M&TE uncertainty should be less than or equal to the reference accuracy of the device being calibrated [Ref. 6.1] MTE = (m12 + M22)112 Where: A = Accuracy of the Master Trip Unit In this section, the required accuracy of the mAdc CS = Calibrated span of the Transmitter measurement is evaluated. MI, M2 = Uncertainty of input and output test Instrument in mAdc Mr, M2 = Uncertainty of input (Ma) and output (M2) test equipment In inWC MTE = M&TE uncertainty in inWC Test equipment uncertainties from Table 8 A2 A 2mA:= -*16-mA A 2mA = 0.032 enA V/ 0 Accuracy of Master Trip Unit in mAdc Since the only test equipment used for calibration of the trip units Is the Rosemount Readout Assembly and calibration current adjustments, its accuracy must be better than the reference accuracy of 0.032 mA. Per Table 8 and Attachment J, the Rosemount Readout Assembly accuracy is 0.0141 mAdc, and is therefore acceptable for Trip Unit setpoint calibration. MTE 2 := O.0-InWC MTE 2 = 0.000 .inWC Trip Unit MTE uncertainty is included in the Analyzed Drift term (Assumption 2.3.17). 3.3.1.5 Analyzed Drift (DA) 3.3.1.5.1 Monthly Calibrations (CTS) DA 2M% := 0.0871-% DA 2M% = 0.087 0% vi Trip Unit Analyzed Drift for Monthly calibrations as a percent (Table 6 and Assumption 2.3.13). DA 2X2 := 0.0871-%-CS DA 2M = 0.3397 inWC / Trip Unit Analyzed Drift for Monthly calibrations as inWC (Table 6 and Assumption 2.3.13). _ .."MW-
VYC-706 Rev. I ATTACHMENT C Calculation Detall CST Level (RCIC) Monitoring Page 10 of31 3.3.1.5.2 Quarterly Calibrations (ITS) DA 20% 0.299 % DA 2 Q% = 0299 I% Trip Unit Analyzed Drift for Quarterly calibrations DA 2Q:= DA 2 Q%-CS DA 2 Q = 1.1661 InWC 7V as a percent (Table 6 and Assumption 2.3.14). Trip Unit Analyzed Drift for Quarterly calibrations as inWC (Table 6 and Assumption 2.3.14). 3.3.1.6 Temperature Effect (TE) Temperature effect during normal and accident conditions is included in the Trip Unit Analyzed TEn2 = TE8 2 = 0.0 inWC Drft term (Assumption 2.3.17 and 2.3.20) TE 2 :=0.inWC TE 2 =0.000.inWC 3.3.1.7 Humidity Effect (HE) Humidity effect during normal and accident conditions are the same and included in the HE 2:= O-InWC HE 2 = 0.000 ainWC Trip Unit Analyzed Drift term (Assumption 2.3.17 and 2.3.20) 3.3.1.8 Radiation Effect (RE) Radiation effect during normal and accident RE82 = REn2 = 0.0 inWC conditions are the same and included in the Trip Unit Analyzed Drift term (Assumption 2.3.17 and 2.3.20) RE 2 := O.O.inWC RE 2 = 0.000 -inWC 3.3.1.9 Seismic Effect (SE) SE 2 := 0.0-%-CS SE 2 = 0.000 oinWC Assumption 2.3.19 3.3.1.10 Power Supply Voltage Effect (VE) Power Supply Voltage Effect during normal and accident conditions are the same and Included in the Trip Unit Analyzed Drift term (Assump. VE 2 := °-° inWC VE 2 = 0.000 *lnWC 2.3.17) rPWWF"P"W"---
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 11 of 31 3.3.2 Master Trip Unit Total Module Uncertainty 3.3.2.1 Normal Conditions 3.3.2.1.1 Monthly Calibrations CE 2 = 0.731 #inWC a/ DB 2 = 0.000 *inWC DA 2M = 0.340 -inWC / MTE, TE, HE, RE and VE are included in Trip Unit Analyzed Drift term (Assump. 2.3.17). en2RM: 4CE 2 2+ DB 2 2i.DA2 M2 e n2RM = 0.806 einWC V/ / Normal trip unit module uncertainty (en2RM) for calibration monthly (38 days) e n2RM:= 0.975-InWC e n2RM = 0.975 .InWC / 49 v'iNormal trip unit module uncertainty (enRM) for calibration monthly (38 days) Is set equal to the equivalent inWC for 0.04 ma to allow for trip calibration readout assembly readability 3.3.2.1.2 Quarterly Calibrations CE 2 = 0.731 .inWC V DB 2 =0.000
° inWC DA 20 = 1.166 OnWC MTE, TE, HE, RE and VE are included in Trip Unit Analyzed Drift term (Assump. 2.3.17).
e n2RQ:= CE2 2 + DB 22 + DA 2 Q2 Normal trip unit module uncertainty (en2Rq) for e n2RQ = 1.376 .inWC // calibration quarterly (114 days) e n2RQ := 1.462.inWC e n2RQ = 1.462 *inWC /'V Normal trip unit module uncertainty (e,2RO) for calibration quarterly (114 days) is set equal to the equivalent inWC for 0.06 ma to allow for trip calibration readout assembly readability 3.3.2.2 Testing Conditions 3.3.2.2.1 Monthly Calibrations CE 2 = 0.731 .inWC / De 2 = 0.000 .inWC DA 2M = 0.340 einWC MTE, TE, HE, RE and VE are all included in Trip e t2RMtA := JCE 22 tDB 22+ DA 2 M2 Unit Analyzed Drift term (Assumption 2.3.17). e t2RM = 0.806 oinWC / Testing trip unit module uncertainty (eURM) for calibration monthly (38 days)
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page12of31 e t2RM = 0.975 'InWC // Testing trip unit module uncertainty (egRM) for e t2RM:= 0.975'inWC calibration monthly (38 days) Is set equal to the equivalent inWC for 0.04 ma to allow for trip calibration readout assembly readability 3.3.2.2.2 Quarterly Calibrations CE 2 = 0.731 einWC DB 2 = 0.000 .InWC DA 20 = 1.166 'inWC MTE, TE, HE, RE and VE are all included in Trip e t2RQ := JCE 22 + DB 22 + DA 2Q2 Unit Analyzed Drift term (Assumption 2.3.17). e t2RQ = 1.376 einWC / Testing trip unit module uncertainty (etRQ) for calibration arlartv (114 dnavs e t2RQ :=1.4625dinWC I. _,, R-Testing trip unit module uncertainty (et2RQ) for I e t2RQ = 1.462 in 1/ calibration quarterly (114 days) is set equal to the equivalent inWC for 0.06 ma to allow for trip calibration readout assembly readability 3.3.2.3 Accident - LOCA (small break) with Seismic & without Radiation 3.3.2.3.1 Monthly Calibrations CE 2 = 0.731 sInWC DB 2 = 0.000 .InWC DA 2M = 0.340 *InWC SE 2 °0.000 InWC MTE, TE, HE, RE and VE are included in Trip e a2RM := e n2RM + SE 2 Unit Analyzed Drift term (Assump. 2.3.17), and mild environments (see section 3.3.2.1.1). e a2RM = 0.975 -inWC Accident trip unit module uncertainty (eORM) for monthly calibrations (38 days) 3.3.2.3.2 Quarterly Calibrations CE 2 = 0.731 .inWC DB 2 = 0.000 .inWC DA 2 Q = 1.166 *inWC SE 2 = 0.000 oinWC MTE, TE, HE, RE and VE are Included In Trip Unit Analyzed Drift term (Assump. 2.3.17), and mild environments (see section 3.3.2.1.2). e a2RQ := e n2RQ + SE 2 e a2RQ = 1.462-inWC // Accident trip unit module uncertainty (ea2RO) for quarterly calibrations (114 days)
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 13 of 31 3.4 Indicator LI-O7-172A (Module 3 - e3) CT 3 0 :=20% CT 3 % = 2.000 e% / Existing Calibration Tolerance in % per OP-4355 [Ref. 6.73 and Table 7. CT 3 := CT 3 %.CS CT 3 = 7.800 .InWC / Calibration Tolerance in equivalent InWC 3.4.1 Uncertainty Elements 3.4.1.1 Reference Accuracy (A) A = (AX2 + h2 4- + rP 4 Where: A = Reference accuracy of instrument AX = Vendoes stated basic accuracy expression h = hysteresis I = linearity r = repeatability AX 3 := 1.500-% CS 13 0%CS h 3 :=-0*%*CS r 3 := 2.000 %-CS A 3 := 4AX 3X2 + h 32 + 132 + r32 A 3 = 9.750 eInWC L/ Indicator Accuracy in equivalent inWC A 3 %:= A 3 A 3% = 2.500o% V/4 Indicator Accuracy in % span 3.4.1.2 Calibration Effect (CE) CE= CT=A Where: Since these indicators will be calibrated with a CT = Calibration tolerance of alarm units full traverse calibration, CE will equal CT [Ref. A Instrument Reference (vendor) accuracy 6.9]. Existing CT Is less than calculated accuracy of A 3% = 2.500 e% 2.5%; however, readability Is to 1% per Table 7. Past calibration data shows that Indicator CT 3% := 2.0 % CT 3 % = 2.000 A% as-found has been within 2.0% on 43 of 46 calibrations [Ref. 6.12 and Attachment 13, therefore CT will be remain at 2.0%.
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 14 of a1 CT 3 := CT 3 %*CS CT 3 = 7.800 -inWC Indicator Calibration Tolerance in inWC CE 3 :=CT 3 CE 3 = 7.800 .inWC / Indicator Calibration Effect in inWC 3.4.1.3 Readability (RD) Uncertainty RD 3 % := (0.25-2.0)-% RD 3 % = 0.500 *% Readability uncertainty = 1/4 minor division; included In the Indicator Analyzed Drift term RD 3 := RD 3 %-CS RD03 1.950*inWC / f (Assumption 2.3.17). 3.4.1.4 Measurement & Test Equipment (MTE) The M&TE uncertainty should be less than or equal to the reference accuracy of the device being calibrated (Ref. 6.11 MTE = (M1 2 + rn 2)1'2 2 Where: A = Accuracy of the Indicator In this section, the required accuracy of the mAdc CS = Calibrated span of the Transmitter measurement is evaluated. Mi, m2 = Uncertainty of input and output test instrument in mAdc M1, M2 = Uncertainty of input (M1) and output (M2) test equipment In inWC MTE = M&TE uncertainty In inWC Test equipment uncertainties from Table 8 A3 A 3mA := .-16mA A 3mA = 0.400 -mA I/ Accuracy of Indicator = 2.5% CT 3 CT 3MA= _-16-rnA CT 3MA = 0.320 .mA / CT of indicator = 2.0% Cs Since the only test equipment used for calibration of the indicator is the Rosemount Readout Assembly and calibration current adjustments, its accuracy must be better than the reference accuracy of 0.400 mA; however since CT is more restrictive than Accuracy (A), MTE must be more accurate than CT of 0.320 mA. Per Table 8 and Attachment J, the Rosemount Readout Assembly accuracy is 0.0141 mAdc, and is therefore acceptable for Trip Unit setpoint calibration. MTE 3 := 0.0-inWC MTE 3 = 0.000 i-nWC Indicator MTE uncertainty Is Included in the Indicator Analyzed Drift term (Assumptions 2.3.17).
VYC-706 Rev. 1 ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 15 of &I 3.4.1.5 Drift (DR) 3.4.1.5.1 Monthly Calibrations (CTS) DA 3M% :=1.4338 % DA 3MOo = 1.434 *% Indicator Analyzed Drift for Monthly calibrations as a percent (Table 7 and Assumption 2.3.15). DA 3M:= DA 3 M%-CS DA 3M = 5.5918 einWC / Indicator Analyzed Drift for Monthly calibrations as inWC (Table 7 and Assumption 2.3.15). 3.4.1.5.2 Quarterly Calibrations (ITS) DA 30% := 2.7495-% DA 3Q% = 2.749 0% Indicator Analyzed Drift for Quarterly calibrations as a percent (Table 7 and Assumption 2.3.15). DA 3Q= DA 3 Q%-CS DA 3Q = 10.7231 oinWC /A Indicator Analyzed Drift for Quarterly calibrations as inWC (Table 7 and Assumption 2.3.15). 3.4.1.6 Temperature Effect (TE) TEn3 = TE,3 = 0.0 inWC Temperature effect during normal and accident conditions are the same and included In the TE := 0.OinWC Indicator Analyzed Drift term (Assump. 2.3.17) TE 3 = 0.000 *InWC 3.4.1.7 Humidity Effect (HE) Humidity effect during normal and accident conditions are the same and included in the HE 3:= 0-inWC HE 3 = 0.000 einWC Indicator Analyzed Drift term (Assump. 2.3.17) 3.4.1.8 Radiation Effect (RE) Radiation effect during normal and accident RES,3= RE,3 = 0.0 inWC conditions are the same and Included In the Indicator Analyzed Drift term (Assumption RE 3 0.0*inWC RE 3 = 0.000 *inWC 2.3.17) 3.4.1.9 Seismic Effect (SE) SE 3 := o.O-%*CS SE 3 = 0.000 .inWC Assumption 2.3.11 3.4.1.1 0 Power Supply Voltage Effect (VE) Power Supply Voltage Effect during normal and accident conditions are the same and Included in VE 3 := 0.0 inWC VE 3 = 0.000 .inWC the Indicator Analyzed Drift term (Assump. 2.3.17)
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 16 of S1 3.4.2 Indicator Total Module Uncertainty 3.4.2.1 Nornal Conditions 3.4.2.1.1 Monthly Calibrations CE 3 7.800 .inWC DA 3M = 5.592 -inWC MTE, RD, TE, HE, RE and VE are included in Indicator Analyzed Drift term (Assump. 2.3.17). en3RM:: 4CE 3 2 +DA 3 M 2 Normal indicator unit module uncertainty e n3RM = 9.597 *inWC / (eORM) for monthly calibrations (38 days) 3.4.2.1.2 Quarterly Calibrations CE 3 = 7.800 -InWC DA 30 = 10.723 *inWC MTE, RD, TE, HE, RE and VE are included in Indicator Analyzed Drift term (Assump. 2.3.17). e n3RQ := 4CE 32 + DA 3Q2 e n3RQ = 13.260*inWC */ Normal Indicator module uncertainty (en3RQ) for quarterfy calibrations (114 days) 3.4.2.2 Testing Conditions 3.4.2.2.1 Monthly Calibrations CE 3 = 7.800OinWC DA 3M = 5.592 *InWC MTE, RD, TE, HE, RE and VE are included in Indicator Analyzed Drift term (Assump. 2.3.17). e t3RM:= CE 3 %.DA3M e t3RM = 9.597 'inWC 7/ Testing Indicator unit module uncertainty (et3RO. for monthly calibrations (38 days) 3.4.2.2.2 Quarterly Calibrations CE 3 = 7.800 OinWC DA 3a = 10.723 .inWC MTE, RD, TE, HE, RE and VE are Included in Indicator Analyzed Drift term (Assump. 2.3.17). e t3RQ := ICE 32 DA 3 2 Testing Indicator module uncertainty (et3RO) e t3RQ = 13.260 *inWC / for quarterly calibrations (114 days)
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 17 of 31 3.4.2.3 Accident - LOCA (small break) with Seismic & without Radiation 3.4.2.3.1 Monthly Calibrations CE 3 = 7.800 .InWC DA 3M = 5.592 GinWC SE 3 = 0.000 *inWC MTE, RD, TE, HE, RE and VE are Included In Indicator Analyzed Drift term (Assump. 2.3.17). e a3RM :=4CE 3 2 DA 3 M21tSE 3 2 Accident indicator unit module uncertainty e a3RM = 9.597 eInWC / (e,3RM) for monthly calibrations (38 days) 3.4.2.3.2 Quarterly Calibrations CE 3 - 7.800.*nWC DA 3Q = 10.723 *inWC SE 3 = 0.000 sInWC MTE, RD, TE, HE, RE and VE are Included in Indicator Analyzed DrIft term (Assump. 2.3.17). e a3RQ :=CE3 21. DA 3 Q2 t SE 3 2 Accident Indicator module uncertainty (e,3RO) e a3RQ = 13.260 inWC / for quarterly calibrations (114 days) 4.0 Total Loop Uncertainty 4.1 Master Trip Unit Auto Suction Transfer TLU ( LT-107-12A & B, LT-107-12A(M) & B(M) - Monthly Calibrations (CTS) 4.1.1 Normal Conditions 4.1.1.1 Random e n1R= 4.174*inWC Transmitter normal uncertainty from section 3.2.2.1 e n2RM = 0.975 *inWC / Trip Unit normal uncertainty from section 3.3.2.1.1 UnRI2M2 ~e nl R t n2RM 2 U nR12M = 4287 oinWC %/14- 4 ormal Random Uncertainty for trip unit loop with monthly calibration.
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 18 of I1 4.1.1.2 Bias %Leveln PM negn nL PM posn From section 2.0. magnitude of bias depends on point of interest InWC inWC inWC 0 -0.020 $/ 4.0 / 0.007 V/ 25.0 -0.506 i. 101.5 0.190 d' 50.0 -0.992 &/ 199.0 0.372 .' / For trip unit actuation on decreasing level, PM bias:= 0.190-InWC 75.0 -1.478 / 296.5 0.554 o positive bias is limiting (sensed level higher than 100.0 -1.964I/ 394.0 / 0.3 actual). The process temperature bias is U nBl2 pos:= PM bias conservatively chosen at the 25% span point with the setpoint expected to be less than 10% U nBl21pos = 0.190 *InWC Z (25 inWC setpoint/390 inWC span). 4.1.1.3 Normal Total Loop Uncertainty (TLU) U nl2M:= U nR12M t U nBl2_pos U nl2M = 4.477 inWC a/ Normal TLU in inWC for monthly calibration 4.1.2 Loop Testing Conditions These channels are not tested as a loop 4.1.3 Accident - Small Break LOCA with Seismic 4.1.3.1 Random e alR = 5.611 *inWC Transmitter accident uncertainty from section 3.2.2.3 e a2RM 0.975 iInWC Trip Unit accident uncertainty from section 2 e -e e U aRl 2M := je a1 R + e a2RM U aR1 2M = 5.695 inWC / Accident Random Uncertainty for trip unit loop with monthly calibration.
VYC-708 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 19 of 31 4.1.3.2 Bias %Level, PM negn Ln PM posn From sectIon 2.0. magnitude of bias depends on point of interest inWC inWC InWC 0 -0.020 1/ 4.0 / 0.007 PM bias := 0.1 90inWC For trip unit actuation on decreasing level, 25.0 -0.506 '/ 101.5 / 0.190 / positive bias is limiting (sensed level higher than 50.0 -0.992 199.0 0.372 . U aB12_pos PM bias actual). The process temperature bias is
/ conservatively chosen at the 25% span point 75.0 -1.478- 296.5 0.554 ,/
with the setpoint expected to be less than 10% 100.0 -1.964 ^/ 394.0 / 0.736 / U aB12pos = 0.190 .inWC / (25 inWC setpointl390 inWC span). 4.1.3.3 Accident Total Loop Uncertainty (TLU) U al2M = U aR12M
- U aB12_pos U a12M - 5.885 *InWC ;/V/ Accident TLU in inWC 4.2 Master Trip Unit Auto Suction Transfer TLU ( LT-107-12A & B, LT-107-12A(M) & B(M) - Quarterly Calibrations (ITS) 4.2.1 Normal Conditions 4.2.1.1 Random e n1 R = 4.174 *inWC Transmitter normal uncertainty from section 3.2.2.1 e n2RQ = 1.462 *InWC .1/ 1Trip Unit normal uncertainty for quarterly calibrations from section 3.3.2.1.2 U nR12Q:= 4e`n1R +en2RQ U nR12Q = 4.423 -inWC t/1#ioirmal Random Uncertainty for trip unit loop with quarterly calibration.
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 20 of 31 4.2.1.2 Bias
%Leveln PM negn Ln PM posn From section 2.0. magnitude of bias depends on point of interest inWC InWC InWC 0 -0.020 a./0 4.07/ 0.007 ./
25.0 -0.506 A, 101.5 C/ 50.0 -0.992 - Of 199.0 / 0.372 '- PM bias:= 0.190 InWC For trip unit actuation on decreasing level, 75.0 -1.478 c, 296.5 -/ 0.554 7 positive bias Is limiting (sensed level higher than 100.0 -1.964 394.0 / 0.736 U ril!pos actual). The process temperature bias is U 1_pos
- = PM bias conservatively chosen at the 25% span point with the setpoint expected to be less than 10%
U nB12.pos = 0.190.inWC (25 inWC setpoinU390 inWC span). 4.2.1.3 Normal Total Loop Uncertainty (TLU) U n12Q := UnR12Q + U nB12_pos U n12Q = 4.613 inWC s/ll Normal TLU in inWC for quarterly calibration 4.2.2 Loop Testing Conditions These channels are not tested as a loop 4.2.3 Accident - Small Break LOCA with Seismic 4.2.3.1 Random e a1R = 5.611 *inWC Transmitter accident uncertainty from section 3.2.2.3 e a2RQ = 1.462 *inWC V' Trip Unit accident uncertainty for quarterly calibration from section 3.3.2.3.2 U aRl2Q0 jea R 4- ea2RQ U aRI2Q = 5.799*InWC /> Accident Random Uncertainty for trip unit loop with quarterly calibration.
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 21 of 31 4.2.3.2 Bias %Level, PM negn Ln PM pos n From section 2.0. magnitude of bias depends on point of interest inWC InWC inWC 0 -0.020 / 4.0 / 0007 / PM bias := 0.1 90 inWC For trip unit actuation on decreasing level, 25.0 -0.506 / 101.5 / 0.190 / positive bias is limiting (sensed level higher 50.0 -0.992 / 199.0 / 0.372 / UaBl2_pos PM bias than actual). The process temperature bias is 75.0 -1.478 ./ 296.5 / 0.554 I/ conservatively chosen at the 25% span point 100.0 - 1.964 394.0 / 0.736 / with the setpoint expected to be less than U aB12 pos.os 0.190 *inWC 1/ 10% (25 inWC setpointl390 inWC span). 4.2.3.3 Accident Total Loop Uncertainty (TLU) U a12Q U aR12Q + U aB12_pos Ua12Qz 5.989*InWC Z // Accident TLU for quarterly calibration in inWC 4.3 CST Level Indication Loop TLU (LT-107-12A, LT-107412A(M), LI-107-12A) - Monthly Calibrations (CTS) 4.3.1 Normal Conditions 4.3.1.1 Random e n1R = 4.174*InWC Transmitter normal uncertainty from section 3.2.2.1 e n3RM = 9.597 .inWC Indicator normal uncertainty for monthly calibration from section 3.4.2.1.1 U nRI3M:= e n1R2 + e n3RM U nR13M = 10.466.inWC Z Normal Random Uncertainty for indicator loop with monthly calibration. 4.3.1.2 Bias %Level, PM neg. Ln PM posh From section 2.0. magnitude of bias depends on point of Interest 0 25.0 inWC
-0.020 /1
-0.506 .
inWC 4.0 7 101.5 / inWC 0.007 Z 0.190 I/ 4 UnB13 neg ::.PM neg
- nneg For the Indication function, both positive and negative bias at all points are considered.
50.0 -0.992 >./ 199.0 0.372 , 75.0 -1.478 / 296.5 V 0.554 f U nB13_pos := PM pos pon 100.0 -1.964 " 394.0 U- 0.736
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 22 of 31 4.3.1.3 Normal Total Loop Uncertainty U nR13 := U nR13M n U nR13M = 10.466 oinWC Z Normal Random uncertainty term for monthly calibration U nfl3posn := U nR13n+ U nBl3_posn Normal positive TLU with bias (Monthly Cal) U n13_negn :=(U nRl3,){1) + U nB13_negn Normal negative TLU with bias (Monthly Cal)
%Leveln U nR13n U nB13._neg, U nB13_posn U n13 neg, U n13 posn n inWC inWC inW C inWC inWC
_ 0 10.4566 -0.020 / 0.007 /- -10.486 / 10.473 . 25.0 10.466 -0.506 -' 0.190 . -10.972 V 10.655 LZ 50.0 10.466 -0.992 ./- 0.372 z' -11.458 -," 10.838 v' 75.0 10.466 -1.478 V 0.554 c/ -11.944 v'- 11.020 ' 100.0 110.4661 1.964 (./ 0.736 / -1 .43/ 11.202 o' U nl3M :=12.430 inWC U n13M = 12.430-InWC The bounding normal TLU (Monthly Cal) of 12.430 inWC conservatively chosen for all points. 4.3.2 Loop Testing Conditions These channels are not tested as a loop 4.3.3 Accident - Small Break LOCA with Seismic 4.3.3.1 Random e alR = 5.611 IlnWC Transmitter accident uncertainty from section 3.2.2.3 e a3RM = 9.597 *InWC Indicator accident uncertainty from section 3.4.2.3.1 U aR13M: eaR +ea3RM U aR13M = 11.117einWC V/ Accident Random Uncertainty for Indicator loop with monthly calibration.
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 23 of 31 4.3.3.2 Bias %Level, PM neg. PM P05n From section 2.0. magnitude of bias depends on Ln point of interest inWC inWC inWC 0 -0.020 / 4.0 0.007 /
-0.506 -- ' 101.5 0.190 / U aB!3_negn := PM neg, For the indication function, both positive and 25.0 negative bias at all points are considered.
50.0 -0.992 / 199.0 / 0.372 / 75.0 -1.478 / 296.5 0.554 ./ U aB133pos =-PM pos 100.0 -1.964 / 394.0 0.736 "I 4.3.3.3 Accident Total Loop Uncertainty U aRI3M = 11.117 inWC U aRI 3n = U aR13M Accident Random uncertainty term (monthly cal) 3 Accident positive TLU with bias (monthly cal) U a130posn = U aR13n U aB13_pos, U a13_negn := (U aRI3a).(-1) + U aBl3_negn Accident negative TLU with bias (monthly cal) 0/oLeveln U aR13n U aB13_negn U aB13._pos° U a13_negn U a13_posn n inwc inwc inWC inWC inWC 0 0 0.007 V -11.137 / 11.125 / 25.0 11.117 -0.506 0.190 / -11.623 11.307 / 2 50.0 11.117 -0.992 Z 0.372 / -12.109 / 11.489 / 75.0 U4 100.0 11.117 11.117
-1.478 /
-1.964 /
0.554 / 0.736 /
-12.595 / 11.672 /
11.854 / A^ U al3M:= 13081-tnWC U a13M = 13.081 *InWC 7 The bounding accident TLU (monthly calibration) of 13.081 inWC is conservatively chosen for all points.
VYC-706 Rev. 1 ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 24 of 31 4.4 CST Indication Loop TLU ( LT-107-12A, LT-1 07-1 2A(M), LI-107-12A) - Quarterly Calibrations (ITS) 4.4.1 Normal Conditions 4.4.1.1 Random e n1R = 4.174 mInWC Transmitter normal uncertainty from section 3.2.2.1 e n3RQ = 13.260 'inWC Indicator normal uncertainty for quarterly calibration from section 3.4.2.1.2 U nR13Q:= en1R en3RQ U nR13Q = 13.901 *inWC / Normal Random Uncertainty for indicator loop with quarterly calibration. 4.4.1.2 Bias
%Level. PM negn L PM Posn From section 2.0. magnitude of bias depends on point of interest
% inWC TnWC InWC 0 -0.020 / 4.0 / 0.007 /
25.0 -0.506 101.5 / 0.1907 U nB13_negn := PM neg, For the indication function, both positive and negative bias at all points are considered. 50.0 -0.992 / 199.0 / 0.372 / 75.0 -1.478 296.5 / 0.554 / U nB13_pos :-=PM P°s n n 100.0 1.964 / 394.0 / 0.736 4.4.1.3 Normal Total Loop Uncertainty U nR13 :- U nR13Q UnR13Q = 13.901 *lnWC ' Normal Random uncertainty term for quarterly calibration U nl3_pos :=U nR13 + U nBl3pos Normal positive TLU with bias (Quarterly Cal) U n13inegn = (U nR13:(Q1) + U nB13_negn Normal negative TLU with bias (Ouarterly Cal) am
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 25 of 31
%Leveln U nBl3_posn U n13.negn U n13_pos, n InWC InWC InWC 0 0 0.007 I/ -13.921l / 13.909 /
25.0 0.190 / -14.407 / 14.091 / 2 50.0 0.372 / -14.893 / 4.2-73 / 3 75.0 0.554 ^/ -15.379 / 14.456 4 100.0 0.736 / -15.865 */ 1.I 3 ./ g
/ The bounding normal TLU (Quarterly Calib) of U nl3Q :=15.8651nWC Un13Q= 15.865 inWC 7/ 15.865 inWC conservatively chosen for all points 4.4.2 Loop Testing Conditions These channels are not tested as a loop 4.4.3 Accident - Small Break LOCA with Seismic 4.4.3.1 Random e aIR = 5.611I inWC Transmitter accident uncertainty from sectlon 3.2.2.3 e a3RO = 13260 alnWC Indicator accident uncertainty (quarterly cal) from section 3.4.2.3.2 UaRI 3Q:= ea1R 1.ea3RQ U aRi 3Q = 14.398 inWC / Accident Random Uncertainty for indicator loop with quarterly calibration.
4.4.3.2 Bias %ILeveln PM negn Ln PM Posn From section 2.0. magnitude of bias depends on point of interest InWC inWC inWC 0 -0.020 , 0/'1 4.0 / 0.007 / 25.0 -0.506 . 101.5 0.190 '.1- U aB13 negn-n = PM neg eg For the indication function, both positive and 50.0 199.0 negative bias at all points are considered.
-0.992
- 4/
4. 0.372 - 75.0 -1.478 296.5 0.554 *-o U aB13 pos =:PM pos I, n 100.0 -1.964v. 394.0 0.736 /
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 26 of 31 4.4.3.3 Accident Total Loop Uncertainty U aR13Q = 14.398 -inWC U aR1 3 = U aR13Q Accident Random uncertainty term (quarterly n cal) U al3_posn = U aR13n + U aBI3_pos Accident positive TLU with bias (quarterly cal) U aI3_negn =(U aRl3n)'(-1) + U aB13.._negn Accident negative TLU with bias (quarterly cal)
%Level, U aR13 U aB13_negn U aB13.._posn U a13-neg, U a13_posn n inWC inWC
- inWC L/Z InWC 14.398 / -0.020 Z/
InWC 0.007 -14.418 14.406 / 25.0 14.398 Z.5F06 -, 0.190/ 74 904 '/ 14.588 V, Ii 50.0 14.398 -0.992 --- 0.372 V' - 15.390 I/ 14.7-70 V" 75.0 14.398 - 1.478 --,
-6 -.
0.554 - -15.876 / 1s.13s --" T4-.952 4 14.398 0.736 Il -. 62 W U a13Q:= 16.362-inWC UaI3Q= 16.362inWC Z The bounding accident TLU (quarterly calibration) of 16.362 inWC is conservatively chosen for all points. 4.5 Summary of Results 4.5.1 Module As-Left Calibration Tolerances (CT) Module CT (InWC) CT (CalIbration Units) Transmitter LT-107412A & B CT I = 0.975 .inWC CT I Cs
.C 16 -A = 0.040.mA 7/
Master Trip Unit LT-107-12A(M) & B(M) CT 2 = 0.731 *InWC CT2 C2 16 mA = 0.03 emA x19 CT 3 Indicator LI-107-12A CT 3 = 7.800 .InWC _-= CS 2.000.% 7/O
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 27 of 31 4.5.2 Module As-Found Calibration Tolerances (FT) Monthly Calibration (CTS1 Quarterly Calibration (CTS) Module FT (inWC) FT (Calibration Units) FT (inWC) FT (Calibration Units) Transmitter e tIR / LT-1 07-12A& LT-1 etR e t1 R = 4.174 sinWC e 16 mA = 0.171 ojnA / 9Cs 7-12= 4.174 inWC
& CS 16 mA = 0.171 emA Cs Master Trip Unit e I2RM = 0.975 *inWC e t2RM 16 mA = 0.04 *mAv4/1/ e t2RQ = 1.462 ;inWC -Es- 1RQ 0.06 mA X/.,-
LT-107-12A(M) & B(M) CS et3RM et3RQ 3.400 / Indicator e t3RM = 9.597 oinWC = 2.481 .% 7/ e t3RQ = 13.260.InWC LI-I 07-1 2A CS Cs 4.5.3 Monthly (CTS) Normal/Accident Total Loop Uncertainty (TLU) Loop Normal (inWC) Normal (Calib. Units) Accident (inWC) Accident (Calib. Units) U n12M 16rnA 0,184amA a12 M.16 mA= 0.241 emA V/ Master Trip Unit U nl2M =4.477.InWC CS .17"n .18 nA & U a12M = 5.885 *inWC %, LT-107-12A(M) & B(M) Cs Indicator U n1 3M = 12.430 inWC n13M = 3.187 e% 1/ U a13M = 13.081 *inWC _a_3M = 3.3540% V/ LI-I 07-12A Cs Cs 4.5.4 Quarterly (ITS) NormallAccident Total Loop Uncertainty (TLU) Loop Normal (inWC) Normal (Calib. Units) Accident (inWC) Accident (Calib. Units) Master Trip Unit U n12Q = 4.613 einWC CSQ16 mA =0.189,MA V/11'V/ U aI2Q = 5.989 InWC-' / 1 16 mA = 0.246 emA /o LT-107-12A(M) & B(M) Cs Cs Indicator U n1 30 = 15.865iflnWC CS =4.068 .,% V' X U a I3Q 18.382 efnWC =S3 4= 5a /1 LI-107-12A Cs
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 28 of 31 5.0 Setpoint Evaluation 5.1 Setpolnt Requirements For the auto-suction transfer setpoint of LT-107-12A(M) & B(M) to be acceptable, the setpoint must satisfy three requirements: 1.) TS Limit - selpoint is > 3% Tank Volume [TS Table 3.2.9] 2.) > Critical height of submergence [Ref. 6.14; WC-1844] 3.) 10,000 gallons useable volume available at switchover [Ref. 6.14; VYC-1844] Since the direction of interest is decreasing level, and since the reset point of the trip unit provides no required function, only the positive loop uncertainties need be considered. VYC-1844 [Ref. 6.14] has evaluated the three requirements above and determined a new process limit value which satisfies all three requirements. Lo = Tank Bottom = 253' 00" = o" [Attachment B - CST Volumetric Evaluation] Li = RCIC Minimum Suction Level = 254' 8.7" = 20.7" above tank bottom [Attachment B - CST Volumetric Evaluation] L2 = Instrument Level Tap = 254' 00" - 12" above tank bottom [Attachment B - CST Volumetric Evaluati L3 = Internal Standpipe = 259' 03" = 6' 03" (75") above tank bottom [Attachment B - CST Volumetric Evaluation] L4 = Tank Overflow = 286' 06" = 33' 06" (402") above tank bottom [Attachment B - CST Volumetric Evaluation] Ls = Process Limit = > 255' 2.5" = 26.5" above tank bottom [Ref. 6.14] Gal = Gallons per inch = 1223.996883 gal [Attachment B - CST Volumetric Evaluation] Head = Static head on transmiters at 0" sensed level = 4" [Attachment B - CST Volumetric Evaluation] SP = Existing setpoint = 4.64 mA = 15.6" above transmitter tap = 27.6" above tank bottom [Ref. 6.7 & Attachment K] Gal:= 1223.996883*gal in-f Gal = 1223.997*gal81n 1 L o= 0-in L 0 = 0.00 -in Tank bottom L I := 20.7-Tn L 1 = 20.70 -in L 2 := 12-in L 2 = 12.00 -in L 3:= O.ft + 3-in L 3 = 75.00 -n L 4 := 33f+6-In L 4 = 402.00 -In L 5 := 26.5-in L 5 = 26.50 -in New Process Limit per Ref. 6.14 & Attach. B head := 4-in head = 4.00 -in Static head on transmitter SP mA := 4.64-mA SP mA = 4.64 amA Current setpoint in mA
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 29 of 31 SP (SP MA mA) SP = 27.600*in / Current setpoint referenced to tank i6-mA bottom. It should be noted that the previously calculated setpoint did not consider the requirement for minimum height of submergence due to the effects of potential vortexing within the CST; in addition, the calculated TLU used in the setpoint determination was +1-6.82". 5.2 Evaluation of Current Setpoint (4.64 mA = 27.6 InWC above tank bottom) 5.2.1 Current Tech Specs (CTS) - Monthly Testing LSP = Process limit + TLU (accident) = Ls + U,12M M, = SP - LSP SP = 27.600 #in U a12M = 5.885 *InWC U a12M.j LSP:= LS+ InWC InW n LSP = 32.385 -in A// MI1 := SP - LSP M I = -4.785 -n /in 5.2.2
Conclusion:
The current setpoint of 4.64 mA is not acceptable because it does not satisfy the minimum level requirement of _ 26.5" above tank bottom [Ref. 6.14 & Attachment B] plus Trip Unit TLU. Since the minimum level requirement cannot be met, a new setpoint must be derived which will meet the minimum level requirement for both CTS & ITS. Since the ITS-related uncertainties are more limiting, the quarterly TLU for accident conditions will be used to determine the proposed new setpoint Requirement Required Level LSP Current Setpoint Marain to LSP Process Limit > 26.5" above bottom (Lo LSP = 32.385 -in I/ SP = 27.600 oin M 1 = -4.785 *In / 7X2
VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 30 of f1 5.3 Evaluation of Revised Setpolnt 5.3.1 Improved Tech Specs (ITS) - Quarterly Testing An arbitrary value of 33.2" Is chosen as a proposed new setpoint such that it Is larger than the minimum level requirement of 26.5" plus accident uncertainties for quarterly testing. LSP = Process limit + TLU (accident) = L5 + U8120 M 1 =SP - LSP L 5 = 26.500 in U al2Q = 5.989 *InWC // SP:= 33.2-in SPF 33.200 -In Proposed new setpoint referenced to tank bottom Process Limit referenced to bottom of L 5 = 26.500 -in tank Accident Trip Unit TLU from section U a120 = 5.989 -inWC t/ 4.2.3.3 LSP := L 5 + .- in /LSP = 32.489'in a/ inWC M1 := SP- LSP M I = 0.711 ein / Setpoint Margin for proposed setpoint 5.3.1.1 Determination of calibration setpoint value SP Cal := [ (SP - L2 ) + head] linWC / SP cal = 25200 einWC I/ New calibration setpoint in InWC as Lin sensed by the transmitter SP mA:= l ( i )-168mA
* + 4 mA W/ SP mA = 4.870 -mA Z New calibration setpoint in mA as L 3901r1n measured at trip/calibration unit readout assembly.
5.3.1.2
Conclusion:
The revised setpolnt of 4.87 mA is acceptable because it is higher than the Limiting Setpoint by a Margin of 0.71 1".
VYC-706 Rev. I ATTACHMENT C Calculation Deall CST Level (RCIC) Monitoring Page 31 of ON Requirement Required Level LSP New Sbtpoont Marain to LSP Process Limit > 26.5" above bottom (L) LSP = 32.489 *in / SP= 33.200 -n ,/ M 1 =0.711 *inz 5.3.2 Custom Tech Specs (CTS) - Monthly Testing LSP = Process limit + TLU (accident) = Ls + U,12M M1 = SP - LSP SP = 33.200 -in Proposed referencednew setpoint to tank bottom L 5 = 26 '500 -in Process Limit referenced to bottom of 1 ~ *intank
=26:50 U a12M =al2M5.885 inWC
-4.1.3.3
/ Accident(Monthly Trip UnitCal)
TLU from section LSP:= L 5+ Ua12M in /LSP= 32.385#inf inWC M 1 =SP - LSP M 1 = 0.815 -in Setpoint Margin for proposed setpoint 5.3.2.1
Conclusion:
The revised setpoint of 4.87 mA is acceptable because it is higher than the Limiting Setpoint by a Margin of 0.815". Requirement Required Level LSP New Setpoint Marain to LSP Process Limit > 26.5" above bottom (L5) LSP = 32.385 *inVI SP= 33.200-in /" M I = 0.815*in
1'3/4 VY CALCULATION CHNGE NOTICE (CCN) 1VYC706 Rev. I CCNOI PaSel..of 3^2 CCN Number: l Calulaation Number v-K 70 No. _Rv. CalculationlTld rCnm<saStng Tank
- pel (RCTC) M witnrng Initiating Document RVW 94476 FThnil Spcif Pona ro i ChangeN 917)
VYDCNMMWI/SP Nolother Safty Evaluation Num r WNA (CS=t C tnldnt) Superseded Docueat W/A Reason for Change: Technical Specificatico Proposed Change No. 217 requests a surveillance fimctoal test Interval cnica frnm monthly to quarterly. An assessment needs to be performed to evaluate the impact ofthe increase on the Setpoints listed in VYC-706 Revision 1. Description of Chang
- 1. Ibis Change is being implemnted as a CCN since the identified impact is not technically significant retive to the exsting calculation's outpz
- 2. Added a ent to the calculation obectives to include an evaluation of the impact of increasing the CTS surveillance mteaval firo mcaothly to quarterly and idded calibration I testing Interval evaluatio [Section 52.3] vffi necessary tale and calculatio detail updates for clarificatka
- 3. Mlnor corrections of discrepancies identified during review for CCN that had no tecnical impact on calculation conchusions.
Technical Justification for Change: Extension of Technical Specification fimctional testing interna needs to be evaluated for potential impact on calaclation wutputs and to idenify any wtput document changes reqaired to support the requested testing interval.
Conclusions:
- 1. Eidsting Setpoint (as recommended) and Uncertainties will support a quarterly fimctkioallcalibwatioa surveillance testing interval.
- 2. Output documents require change to support a quarterly testing interval (see CCN Open ltemns)
- 3. This CCN does not require a safety evaluation. This calculation or CCN is not an Implemnenting document Any necessary changes to plant procedures to implement calculation outputs wwuld be screened during the applicable pcdure changeproc.
- 4. This CCN has no impact on relevant conditions/limitations of the calalaticnu Prepred By/Date Interdiscipline Review By/Date Independent Review By/Date Approved B.lDate See Atahed Review Forms t- ix o Mark S. McKinleyJon IL Lewis James l Installation Verification / ldIh ?
Signat76/
/ /
Note. WAPF 0017.07 should be includd immediately following this fom. VYAPF 0017.08 (Sample) AP 0017Rev. 5 Page I of I DI #99-381
W CALCULATION DATABASE INPUT FORM VYC-706 Rev. 1 CCN-l >4 I Page a of 32 J vvr-70f 1 (/ rr.ft 1 N/A N/A W Calculation/CCN Number Revision Number Vendor Calculation Number Revision Number Vendor Name NIA PO Numbert N/A Calculation Type (Originating Department) W esign Fngineering (FTA) VV Implementation Required? X Yes 03 No Asset/Equipment ID Number(s)' I-T-l710 A A 1 TT-107-117 AM & B(M) M-A107-12A Asset/System ID Number(s) 10n7 Keywords No New KqmmrA& General References RIDee C. a eiecil (icudn Rev.;A D-UNoAA--A. l ;C. -at "M A -. A M-lc~k(e 31.17 Cr ui-anc
'Io C t';- R-r-1Da~ - f 'k
. No New General References _
Design Input Documents - The following documents provide design input to this calculation. Document # Document rnld Cnchlin Rev, No. and Date. ifarylicable) Critkal Referenc I(1 No New Innut Documents Design Output Documents - This calculation provides output to the following documents. Docuat# Docuncwt Tile Cridcal Rcfncc ("1 No New Output Documents WAPF 0017.07 (Sample) AP 0017 Rev. 5 Page I of I
VYC-706 Rev. I CCN-01 IPage 3.I of 3a! 1,) Page 1 of I VY CALCULATION OPEN ITEM LIST Calculation Number: WVC-706 Revision Number: 1 CCN Number: __ Open Item Resolution Method of 01 Tracking or Date Closed 1 T1pon npprvnvl gnd nmp1emgntntinn nf Technienl Specifieition rhnnge Nn 17, n-r-ort thf11znn
. irri,,rriUI Milo Ml11lwirix A Tkr' - implement ehnngete nerqnpry tn.
OP-4155 tn n the qginrerfly adammnrte tetint ;interval-R. T*('- Ipdste (P-41SS to refleet new 1Rnrterly whien fnr I SD sin A Fontnd Tnoleranet (T:T) nc ientifind In Tahbli 1n nninI . ( etnlign Fnginxaiyng-i cdnte the -
.Retpnnt Mstrhe fn1Inwing ehtnges to pp4'4 5S VYAPF 0017.05 (Sample)
AP 0017 Rev. 5
VYL--'1to ZFV I CQ - -1 PPAGE *H OF 32 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 PURPOSE 1.1. Calculation Objectives This calculation has been developed in support of the Vermont Yankee Setpoints program and covers instrument loops LT-107-12A and LT-107-12B in the Condensate' and Demineralized Water Transfer System and has the following major objectives:
- 1. Document the instrument loop functions and the basis for the setpoint(s).
- 2. Establish the total loop uncertainty for each output function and verify consistency with the design basis.
- 3. Calculate the limiting setpoints and Allowable Value (AV) for inclusion in the Improved Technical Specifications (ITS) if applicable.
- 4. Evaluate the adequacy of the existing setpoint and calibration limits.
- 5. Provide as-found and as-left tolerances for use in instrument calibration and functional test procedures. Determine Measuring and Test Equipment selection requirements. Verify and document process corrections, instrument scaling, and caibration methos
,Al/ - i a i o p sponses,and II" standard, off-normal, and emergency operating procedures be included in the evaluation. This requirement is accomplished by the inter-departmental review which supplements the WE-1 03 review process. (a. Evatumte. 41'ma. &.p% i carrest AnTac-60al, 5r0e41 5Lvrveailuocre_ tc&Qoru&d ;ri>?A Monwhly +t QwL.irterly or%+ka/
$Poirs5
_GQAb mvd [lr-.cPrvoicastz -Pc C-T-q. Engineering Design Engineering Page 6 of 26 Yankee Design Vermont Yankee Page 6 of 26
I VYX-30t RLJ. I CM-O( PAGE 5 aO 3;2 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Selected Definitions". However, the trip units and LI-107-12A have been functionally tested (calibration checked) every month per OP-4355 [Ref. 6.7] and it is assumed that the indicator and trip units will be tested quarterly or every 114 days (91 days + 25%) witlTS implementation. It should be noted that the functional test of the trip units d indicator in essence constitute a VIn calibration since as-found and as-left dat The loop instruments are currently calibrate cycle and the test equipment temperatures will be bounded by the ambient temperature extremes listed in Table 2 above. For the test equipment uncertainty evaluations performed under VYC- 758 [Ref. 6.13. Attachment J], the RB RHR Cmr Rm 232' environment conservatively bounds the environment to be expected at the CST instrument room, and will therefore be used as representative of the CST instrument room. The test equipment used for calibration of LI-1 07-12A is the 510DU calibration and readout assembly located in panel 25-6B in RB Volume 21 at the 280' elev., therefore, the temperature variations for Reactor Building Occupied Areas will be used. 2.3.5. The temperature variation within a cabinet is the same as the variation of the room in which it is located. The temperature difference between the room and the cabinet is therefore constant. Calibration data are assumed collected with the equipment at the operating temperature of the cabinet. 2.3.6. Review of the Vermont Yankee Environmental Qualification Program Manual [Ref. 6.6 and Attachment L] indicates the following: The transmitters will not experience harsh temperature or radiation conditions for any accident and need only demonstrate operability under their normal service environment. Per Qualification Category B and Technical Basis Note 71, the trip units will experience harsh environmental conditions of various design basis.accidents within which they need not function for accident mitigation. These trip units are relied upon to function prior to a harsh environment developing, however, due to their mounting within a rack containing other accident mitigation channels, they must be qualified to withstand the subsequent harsh environment without experiencing a failure that could adversely impact any safety function. The CST RCIC suction transfer function is required to function short-term (2 hours or less) following a small break LOCA. The level indicator LI-107-12A has no accident mitigation function and is only credited forAppendix R Safe Shutdown. Based on the above discussion, the RCIC CST auto suction transfer function of LT-1 07-12A(M) & LT-1 07-1 2B(M) will be evaluated for mild environmental conditions for up to two hours following a small break LOCA, with seismic. The trip units are qualified to operate in the harsh environment such that they will not fail, however, these conditions need not be evaluated with respect to auto-transfer trip setpoint uncertainty. The transmitter accident conditions will consider only their normal environmental conditions with seismic. The indicator LI-107-12A loop will be evaluated for normal conditions only. Page 10 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 10 of 26
\4C-l70( REU I r-LI-D F'M6E ID OF 3-2 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 analyzed for Surveillance Group 1. The Surveillance Group 1 Analyzed Drift (ADR) at either the 10%, 50%, or 90% point (whichever value is most conservative with respective to drift magnitude and time dependency) is calculated based on the following considerations:
a) The analyzed drift data shows the 90% point to be the largest value at 1.4338% with the 50% value at 1.3488%, and the 10% point at 1.3095%. The 100% analyzed drift value is largest, and will be used as a conservative drift value. b) From review of this drift analysis and the histograms, the data exhibits a normal distribution for all points. As indicated in the time dependency discussion for Surveillance Group 1 (Attachment J), time dependency is exhibited at all points. However, the Significance F at all points is much greater than 0.05, indicating no correlation between drift magnitude and time interval. Since there is no indication of a drift to time relationship, the 38-day Analyzed Drift Term will be derived directly from the 31-day ADR term. c) The average drift value for this group is -0.0081% at 0%, -0.0173% at 50%, and -0.0107% at the 100% point. Since these are all less than 0.09% (N > 120 and STDEV > 0.50%), this term is negligible and hence no bias effects are considered [REF. 6.8]. d) The indicator ADR value for monthly calibrations is calculated directly as follows: ADR 3 ,Dys=ADR 3 1-Wp= +/- 1.4338% C.TS Surly i : 17 1 e) Since the indicator and trip units are tested at e same time, and since the Trip Units will be calibrated quarterly unde TS, the indicator quarterly calibration drift must be determined. Although no time to drift magnitude relationship was determined for these indicators, the 114 day drift will be conservatively derived from the 31 day ADR term as follows:
.DA, v li xl.A338' =+2.7495%
. 31 2.3.16. Calibration of LI-1 07-12A under OP-4355 [Ref. 6.7 and Attachment K] is performed using the Rosemount Readout Assembly and Calibration Current adjustments to simulate a current input to trip unit LT-107-12A(M). The auxiliary analog output (1-5 Vdc) of the trip unit in turn provides the voltage output (for the given input current level) to LI-107-12A. Based on the calibration method used, the Monthly and Quarterly drift associated with the auxiliary analog output circuit of master trip unit LT-1 07-12A(M) will be assumed to be included in the Monthly and Quarterly Analyzed Drift term for indicator LI-107-12A.
OP-4355 [Ref. 6.7] does not address calibration of the auxiliary analog output circuit of the master trip unit over the range of 4-20 mAdc input. Therefore, calibration effect for the indicator will be assumed to include calibration effect associated with the analog output circuit. niern ae1 f2 Vermon Vermont YaeDsg Yankee Design Engineering Page 13 of 26
YPrE-0D R7 OI UN-O2. 'Z PAGE 7 OF SZ Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 J Given that Indicator Analyzed Drift (DA) includes trip unit analog output circuit drift, and auxiliary analog circuit Calibration Effect (CE) is included in Indicator CE, and since Seismic Effect of the trip units is 0.0% (2.3.19), the indicator Normal, Testing, and Accident uncertainties will be assumed to include all uncertainties associated with the trip unit auxiliary analog output circuit. 2.3.17. Given that Analyzed Drift (ADR) data is available for each loop component evaluated under this calculation, and given that LI-107-12A and LT-107-12A(M) and LT-107-12B(M) are all currently calibrated monthly ?may be a"71 calibrated quarterl y ;, these loops will be eval mild environmental condmtionsTthe Reactor Building Vol. 21 and 52 (i.e. normal conditions), and it is assumed that the Analyzed Drift (ADR) term for each includes Temperature Effect (TE), Readability (RD), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), Humidity Effect (HE), and Radiation Effect (RE) for the indicator and trip units [Ref. 6.1 section 3.6.5] under both normal and accident conditions. 2.3.18. Given that Analyzed Drift (ADR) data is available for transmitters LT-107-12A & B, and given that LT-107-12A & B are calibrated each operating cycle, the transmitters will be evaluated for mild environmental conditions (i.e. normal conditions), and itis assumed that the Analyzed Drift (ADR) term includes Temperature Effect (TE), Deadband (DB), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), and Humidity Effect (HE) [Ref. 6.1 section 3.6.5] under both normal and accident conditions. Radiation Effect (RE) at the CST is assumed to be negligible. 2.3.19. Seismic Qualification testing of the Rosemount 51ODU Trip Calibration System is documented in Rosemount Report 3768A Rev. B [Ref. 6.6.1 and Attachment E]. The documented results of testing indicate that the worst case seismic effect on the trip point setting for the twelve (12) channels tested was 0.024% span. 32 of the remaining 35 data results yielded setpoint effects of less than 0.012%. A seismic effect of 0.024% maximum, when compared to repeatability of 0.13%, is insignificant and will be considered negligible for this calculation. 2.3.20. The environmental conditions for the Rosemount 510DU specified in Table 5 of Reference 6.15 [Attachment E] provide the limiting environments to be used for choosing the appropriate performance specifications. Since the temperature, humidity, and radiation conditions listed for the 'Normal - HighW environment bound the conditions expected for LT-107-12A(M) & 128(M) under normal and mild accident conditions (See Table 4), the Trip Point Repeatability and Auxiliary Analog Output specifications of + 0.20% will be used [Tables 6 and 7 of Attachment E] for both normal and accident conditions.
- 3. INPUT DATA Data used to calculate loop uncertainties, process corrections, setpoints, and decision points are tabulated in the following sections with the applicable reference or basis noted.
Vermont Yankee Design Engineering Page 14 of 26
MWfo7 REV I CLUJ-0I. PAGE DE 3 2-Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. i
- 4. CALCULATION DETAIL The detailed calculation of loop uncertainties, setpoints, testing tolerances, and margins have been performed using MathCad and are documented as Attachment C.
- 5. RESULTS AND CONCLUSIONS 5.1. Total Loop Uncertainty Total Loop Uncertainties (TLU) have been evaluated for the RCIC CST Level indication and trip loops and the results are presented in Table 9 below.
Table 9 Total Loop Uncertainty
.lU TLU TLU TLU Normal Normal Accident Accident Output Instrument Calibration +/- % CS + Cal Units +/- % CS + Cal Units LT-107-12A(M) & B(M) Monthly 1.150 / 0.184 mAdc 1.506 / 0.241 mAdc, -
LI-107-12A Monthly 3.187 3.187 % 3.354 7 3.354 % LT-107-12A(M) & B(M) Quarterly 1.181 0.189 mAdc/ 1.538 0.246 mAdc .- LI-107-12A Quarterly 4.068 4/.068 % 4.195 4.195 % 5.2. Setpoint Evaluation ,/ 5.2.1. Current Low Level Suction Transfer setpoint As evaluated in Attachment C, section 5.1, the existing Low Level suction transfer setpoint of 4.64 mAdc (decreasing) cannot be supported based on the new requirements for critical height of submergence of the RCIC suction. The revised Process Umit of 2: 26.5' from CST bottom [Ref. 6.14 and Attachment BJ includes consideration for the TS requirement that the setpoint be 2 3% and that there be 10,000 gallons reserve at the suction transfer point. See Table 10 below. 5.2.2. Revised Low Level Suction Transfer setpoint A revised setpoint is evaluated in Attachment C, section 5.3; the proposed setpoint of 4.87 mAdc (decreasing) supports the requirements for critical height of submergence of the RCIC suction + 10,000 gallon reserve and has adequate margin from LSP to SP. See Table 10 below. 6-, I le Vermont Yankee Design Engineering Page 20 of 26 Vermont Yankee Design Engineering Page 20 of 26
IW CALCULATION SHEET VYC-706 Rev. 1CCN-01 Page -% of '52 Calculation Number wVC-706 Revision NunberL I Number 01 Insert I tiOl 5.2.3 CalibrationITesting Interval With implementation of the revised Setpoint [Ref Section 5.2.2], the results of this calculation as 0A presented in Table IOshow positive margin for both monthly and quarterly calibration intervals. Based on this, calculation outputs will not be impacted by a surveillance interval extension from monthly to quarterly. VYAPF 0017.03 (Sample) AP 0017 Rev. 5
WYe-7WO REJ. I CLVJ-DI FPSE 1D O F 37-Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Table 10 Setpoint Results ____ Existing Setpoint New Setpoint New Setpoint (4.64 mA) (4.87 mA)' (4.8711A) Inches' inches7 Inches6 IncheS7 Inches , Process Limit (PL) Ž26.5 2 18.5 Ž26.5 -,218.5 Ž26.5 v Ž 18.5 Accident Uncertainty 5.885 5.885 5.885 5.885 N/A N/A (Monthly Cal - U.12m)_ Accident Uncertainty N/A N/A N/A N/A 5.989 5.989 (Quarterly Cal -Ua__2_)_ Limiting Setpoint 32.385 24.385 32.385/ 24.385 .32.489 24.489 ( IS P ) _ __ I__ _ _ _ _ _ __I_ _ _ _ _ Setpoint (SP) 27.6 / I.2 19.6 / 25.2 33.2 2/.25 Margin (MI) -4.785 .4.785 0.815 A 0.815 0.711 Z 0.711 5.3. Calibration and Test Results In order to support and implement the results of this calculation, the loop instruments are to be calibrated at nine points based on the following ranges: Table 11 Module Calibration Ranges Description Value Units Transmitter input range 4 to 394 , Inches H20 Transmitter output range 4.0 to 20.0 7mAdc Indicator input range (Cal current adjust) 4.0 to 20.0 mAdc Indicator output range Oto 100 %7 Trip Unit input range 4.0 to 20.0 m/Adc Trip Unit Lo Setpoint - Auto Suction Xfer 4.87 decr / mAdc Test as-found tolerances (FT) and as-left tolerances (CT) are shown below. 6 Referenced to tank bottom. As sensed by transmitter;level above transmittertap (0") including 4 static head. Vermont Yankee Design Engineering Page 21 of 26
'iYe-70(f RY l CbJ Ol
< PAGE l OF 32 Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Table 12 Module Calibration Tolerances As Found (FT) As Left (CT)
Tag Number Calibration : % CS Cal Units C +/- % CS +/- Cal Units LT-107-12A & B Operating Cycle 1.069 0.171 mAdc/ 0.25 0.04 mAdc 7 LT-107-12A(M) & Monthlye ) 0.250 0.04 mAdc v 0.19 0.03 mAdc -o B'(M ) _ _ _ _ _ _ _ _ _ _ _ LI-1 07-12A8 Monthly 6RS 2.0 2.0 % 2.0 2.0 % LT-107-12A(M) & Quarterly ) 0.375 0.06 mAdc 0.19 0.03 mAdc V
>(M) _ _
LI-107-12A 8 Quarterly fl 3.0 3. [ 2.0 2.0 %/ 5.4. Conclusions and Summary of Recommendations j/ 5.4.1. Revise setpoint to 4.87 mAdc decreasing. The setpoint is no longer based on simply being greater than or equal to 3% level as per TS Table 3.2.9. Based on tank vortexing effects evaluated underVWC-1844 Rev. 0, the limiting consideration is now based on maintaining a minimum level above the RCIC suction to prevent air entrainment due to vortexing, with the 10,000 gallon reserve requirement added. As such, the references in OP-4355 Rev. 14 to 'Tech Spec Setting of 2 3%" and VY Trip Setting of "4%" should be revised to reflect the new bases. 5.4.2. For transmitter calibrations, only the Heise 901 B (0-400") is acceptable as the pressure source. Both the HP 3466A and HP 34401A DMMs are acceptable for transmitter calibration. OP-4355 should be revised to incorporate the change in test equipment requirements. All calibrations should be revised to nine-point calibrations. 5.4.3. Applicability list for VYEM-0055 shows model number for LT-107-12A & B as 1153G85 instead of 1153GB5. Revise accordingly. 5.4.4. MPAC for LT-107-12A says Model Number is 153G85 instead of 1153GB5. Revise accordingly. 5.4.5. Since there is no Analytical Limit (AL) associated with the RCIC CST Level Indication or suction transfer functions, evaluation of Allowable Value (AV) is not performed for this calculation. VYC-1 844 Rev. 0 [Ref. 6.14} determines the process limit for the low level suction transfer point based on system operability requirements. The process limit used for this calculation concurrently satisfies the existing Technical Specification requirement of > 3%. 8 Indicator tolerances rounded for readability. Page 22 of 26 Vermont Vermnont Yankee Design Engineering Yankee Design Engineering Page 22 of 26
VYC.-'76 RSV. C.C--01 VYC-706 Rev. I ATTACHMENT C FF\GE 0 O1 32. Calculation Detail CST Level (RCIC) Monitoring Page 1 of 31
-4; Calculation Index Paqe 1.0 Loop Calibration Conditions 2 2.0 Process Measurement Effects 3 3.0 Module Uncertainties 4 3.1 Primary Element (e 0) 4 3.2 Trabnsmitter LT-107-12A and LT-107-12B (Module 1 - Q1) 4 3.2.1 Transmitter Uncertainty Elements 4 3.2.2 Transmitter Total Module Uncertainty 7 3.3 Master Trip Unit LT-107-12A(M) & B(M) (Module 2 - e2) 7 3.3.1 Trip Unit Uncertainty Elements 8 3.3.2 Master Trip Unit Total Module Uncertainty 11 3.4 Indicator Li-l 07-12A (Module I - e3 ) 13 3.4.1 Indicator Uncertainty Elements 13 3.4.2 Indicator Total Module Uncertainty 16 4.0 Total Loop Uncertainty 17 eCN-otAt 1(1410 4.1 Master Trip Unit Auto Suction Transfer TLU - Monthly Calibrations 17 4.1.1 Normal Conditions 17 4.1.3 Accident Conditions 18 U-S,0t of.Aylgl 4.2 Master Trip Unit Auto Suction Transfer TLU - Quarterly Calibrationsl 19 4.2.1 Normal Conditions 19 4.2.3 Accident Conditions 20 I ezt A 7 J / t' /
4.3 CST Level Indication Loop TLU - Monthly Callbrations19) 21 4.3.1 Normal Conditions 21 4.3.3 Accident Conditions 22 I Ct tInta 4.4 CST Level Indication Loop TLU - Quarterly Calibrationsfons;J 24 I VlO I t /t y/co 4.4.1 Normal Conditions 24 4.4.3 Accident Conditions 25 4.5 Summary of Results 26 4.5.1 Module As-Left Calibration Tolerances (CT) 26 4.5.2 Module As-Found Calibration Tolerances (FT) 27 4.5.3 Monthl ormallAccident Total Loop Uncertainty (TLU) 27 C..\ C- °t 2111t ./y~ 4.5.4 Quarteri or allAccident Total Loop Uncertainty (TLU) 27 5.0 28 5.1 Setpoint Requirements 28 5.2 Evaluation of Current Setpolnt 29 5.2.2 Conclusion 29 5.3 Evaluation of Revised Setpolnt 30 5.3.1.2 Conclusion 30
fYv--'7 RF. L-2 VYC-706 Rev. I ATTACHMENT C PlGP- 13 OF 3Z Calculation Detail CST Level (RCIC) Monitoring Page 9 of 31
-S CT 2:= CT 2%-CS CT 2 = 0.731 elnWC to/ New Trip Unit Calibration Tolerance in inWC -'
CE 2 := CT 2 CE 2 = 0.731 oinWC Trip Unit Calibration Effect in inWC 3.3.1.3 Dead Band (O)B) Deadband for the trip unit Is associated only with DB 2 := 0.0-inWC DB 2 = 0.000 #InWC the adjustable reset band of the trip setpoint (Table 6 and Attachment El and is not a concern for this calculation. 3.3.1.4 Measurement & Test Equipment (MTIE) The M&TE uncertainty should be less than or equal to the reference accuracy of the device being calibrated [Ref. 6.11 MTE = (m1 2 + rn22 )1 2 Where: A = Accuracy of the Master Trip' Unit In this section, the required accuracy of the mAdc CS - Calibrated span of the Transmitter measurement is evaluated. Mi, m2 = Uncertainty of Input and output test Instrument in mAdc M,, M2 = Uncertainty of input (M1) and output (M2 ) test equipment in inWC MTE = M&TE uncertainty in inWC Test equipment uncertainties from Table 8 A2 A 2mA := mA A 2mA = 0.032 mA i/70 Accuracy of Master Trip Unit in mAdc Since the only test equipment used for calibration of the trip units is the Rosemount Readout Assembly and calibration current adjustments, its accuracy must be better than the reference accuracy of 0.032 mA. Per Table 8 and Attachment J, the Rosemount Readout Assembly accuracy is 0.0141 mAdc, and is therefore acceptable for Trip Unit setpoint calibration. MTE 2 := 0.0 InWC MTE 2 = 0.000 ainWC Trip Unit MTE uncertainty is included in the Analyzed Drift term (Assumption 2.3.17). 3.3.1.5 Analyzed Drift (DA) 3.3.1.5.1 Monthly Calibratlonsk DA 2M% := 0.0871-% DA 2M% = 0.087 0% 7- Trip Unit Analyzed Drift for Monthly calibrations as a percent (Table 6 and Assumption 2.3.13). DA 2M := 0.0871-%-CS DA 2M = 0.3397 einWC / Trip Unit Analyzed Drift for Monthly calibrations as InWC (Table 6 and Assumption 2.3.13).
YF-P70 lo RigO UC--O1 FPPE 141 OF 3Z VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 10 of 31 3.3.1.5.2 Quarterly Calibrationsp IC.C.I-ii A VIVO DA 2Q% := 0.299-% I , q I,, DA 2Q% = 0.299 *% Trip Unit Analyzed Drift for Quarterly calibrations as a percent (Table 6 and Assumption 2.3.14). DA 2Q := DA 2 Q%-CS DA 2Q = 1.1661 *inWC Trip Unit Analyzed Drift for Quarterly calibrations as InWC (Table 6 and Assumption 2.3.14). 3.3.1.6 Temperature Effect (TE) Temperature effect during normal and accident conditions is included In the Trip Unit Analyzed TEn2 : TEa2 - 0.0 inWC Drift term (Assumption 2.3.17 and 2.3.20) TE 2 -0.0inWC TE 2 = 0.000 inWC 3.3.1.7 Humidity Effect (HE) Humidity effect during normal and accident conditions are the same and included in the HE 2 := OinWC HE 2 =0.000.inWC Trip Unit Analyzed Drift term (Assumption 2.3.17 and 2.3.20) 3.3.1.8 Radiation Effect (RE) Radiation effect during normal and accident RE. 2 = REn2 = 0.0 inWC conditions are the same and included in the Trip Unit Analyzed Drift term (Assumption 2.3.17 and RE 2 = 0.000oinWC 2.3.20) RE 2:= 0.O-inWC 3.3.1.9 Seismic Effect (SE) SE 2 := 0.0-%CS SE 2 = 0.000 alnWC Assumption 2.3.19 3.3.1.10 Power Supply Voltage Effect (VE) Power Supply Voltage Effect during normal and accident conditions are the same and included in the Trip Unit Analyzed Drift term (Assump. VE 2 := 0-0 inWC VE 2 = 0.000 *inWC 2.3.17) I.
\nrI rE-o RFg I CLIO-01 VYC-706 Rev. 1 ATTACHMENT C rxcEE m DE 32 Calculation Detal]
CST Level (RCIC) Monitoring Page 15 of 31 3.4.1.5 Drift (DR) 3.4.1.5.1 Monthly Callbratlonsf 3 CC.M-t ,YO DA 3M% :=1.4338-% DA 3M% = 1.434 a% Indicator Analyzed Drift for Monthly calibrations A div,x as a percent (Table 7 and Assumption 2.3.15). DA 3M:= DA 3 M%.CS DA 3M = 5.5918einWC / Indicator Analyzed Drift for Monthly calibrations as inWC (Table 7 and Assumption 2.3.15). 3.4.1.5.2 Quarterly Calibrationsn Ji1Iu DA 3Q% := 2.7495-% DA 30% 2.749 o% Indicator Analyzed Drift for Quarterly calibrations as a percent (Table 7 and Assumption 2.3.15). DA 3Q:= DA 3 Q%'CS DA 3Q = 10.7231 'inWC t Indicator Analyzed Drift for Quarterly calibrations as inWC (Table 7 and Assumption 2.3.15). 3.4.1.6 Temperature Effect (TE) TEn 3 = TE,3 = 0.0 inWC Temperature effect during normal and accident conditions are the same and Included In the TE 30:= 0.0inWC Indicator Analyzed Drift term (Assump. 2.3.17) TE 3 - 0.000 -inWC 3.4.1.7 Humidity Effect (HE) Humidity effect during normal and accident HE 3 := OInWC HE 3 0.000oinWC conditions are the same and Included In the Indicator Analyzed Drift term (Assump. 2.3.17) 3.4.1.8 Radiation Effect (RE) Radiation effect during normal and accident RE03 = REn3 = 0.0 InWC conditions are the same and Included In the Indicator Analyzed Drift term (Assumption RE 3:= 0.0OInWC RE 3 0.000 'InWC 2.3.17) 3.4.1.9 Seismic Effect (SE) SE 3 :=00%CS SE 3 = 0.000 *InWC Assumption 2.3.11 3.4.1.10 Power Supply Voltage Effect (VE) Power Supply Voltage Effect during normal and accident conditions are the same and Included in VE 3:= 0.0 InWC VE 3 = 0.000 inWC the Indicator Analyzed Drift term (Assump. 2.3.17)
lyerJQ(6 RFAI. I C '01 VYC-706 Rev. 1 ATTACHMENT C ?r6E; tob DF 32. Calculation Detail CST Level (RCIC) Monitoring Page 17 of 31 3.4.2.3 Accident - LOCA (small break) with Seismic &without Radiation 3.4.2.3.1 Monthly Calibrations CE 3 = 7.800 einWC DA 3M = 5.592 oinWC SE 3 = 0.000 inWC MTE, RD, TE, HE, RE and VE are included in Indicator Analyzed Drift term (Assump. 2.3.17). e a3RM ::CE3 2+DA 3 M2+SE 3 2 Accident Indicator unit module uncertainty e a3RM = 9.597 -InWC / (ea3RM) for monthly calibrations (38 days) 3.4.2.3.2 Quarterly Calibrations CE 3 = 7.800 oInWC DA 3Q = 10.723 *inWC SE 3 = 0.000 inWC MTE, RD, TE, HE, RE and VE are included in e a3RQ:= lCE 32 + DA 3Q2 +SE 32 Indicator Analyzed Drift term (Assump. 2.3.17). e a3RQ = 13.260 sinWC / Accident indicator module uncertainty (ea3RQ) for quarterly calibrations (114 days) 4.0 Total Loop Uncertainty IU-O I 4,1 Master Trip Unit Auto Suction Transfer TLU ( LT-107-12A & B, LT-107-12A(M) & B(M) - Monthly Callbratlons) Jfi tity/oo 4.1.1 Normal Conditions q 2117/0u 4.1.1.1 Random e nIR = 4.174 *inWC Transmitter normal uncertainty from section 3.2.2.1 e n2RM = 0.975 oinWC Z Trip Unit normal uncertainty from section 3.3.2.1.1 UnR12M:" 4 e n1R + en2RM U nR12M = 4.287 oinWC %/4A X4 ormal Random Uncertainty for trip unit loop with monthly calibration. 1:
ViN-t70ra REVE. FLN-OS I VYC-706 Rev. I ATTACHMENT C PAGE II OF 3z Calculation Detail CST Level (RCIC) Monitoring Page 19 of 31
-4..
4.1.3.2 Bias %Leveln PM negn Ln PM pose From section 2.0. magnitude of bias depends on point of interest
% inWC inWC inWC
-0.020 V/ 4.0 V/ 0.007 .- PM bias := 0.190-inWC For trip unit actuation on decreasing level,
/
25.0 0.506 / 101.5 1/ 0.190 '- positive bias is limiting (sensed level higher than 50.0 -0.992 -/ 199.0 / 0.372 b1 U aB12_pos = PM bias actual). The process temperature bias is 75.0 - 1.478 / 2965 /. 0.554 , conservatively chosen at the 25% span point 1 00.0 0.736 , I with the setpoint expected to be less than 10% 1.9 64 / U aB12_pos = 0.190 *inWC / (25 InWC setpointU390 InWC span). 4.1.3.3 Accident Total Loop Uncertainty (TLU) U a12M - U aR12M I U aB12_pos U a12M = 5.885 *inWC /1 /' Accident TLU in inWC 4.2 Master Trip Unit Auto Suction Transfer TLU ( LT-107-12A & B, LT-107-12A(M) & B(M) - Quarterly Calibrationst I I 4.2.1 Normal Conditions 2A7fli 4.2.1.1 Random e nIR= 4.174 'inWC Transmitter normal uncertainty from section 3.2.2.1 e n2RQ = 1.462 olnWC I/ Trip Unit normal uncertainty for quarterly calibrations from section 3.3.2:1.2 UnRl2Q '4 e fR21 ~en2RQ2 U nR12Q = 4.423 alnWC jv3/4Normal Random Uncertainty for trip unit loop. with quarterly calibration. .
Er-01 VYC-706 Rev. I ATTACHMENT C FPKE l3 OF Calculation Detail CST Level (RCIC) Monitoring Page 21 of 31 4.2.3.2 Bias %Level1 PM negn L PM posn From section 2:0. magnitude of bias depends on
% point of interest inWC InWC InWC 0 -0.020 . 4.0 / 0.007 VI PM bias = 0.190 inWC For trip unit actuation on decreasing level, 25.0 -0.506 / 101.5 / 0.190 VI positive bias is limiting (sensed level higher 50.0 -0.992 ~ 199.0 / 0.372 V/ than actual). The process temperature bias is U aB12_pos PM bias 75.0 -1i.478 ~/ 296.5 / 0.554 V
/ conservatively chosen it the 25% span point with the setpoint expected to be less than 1 00.0 -1.964 394.0 / 0.736 v / 10% (25 inWC setpointl390 InWC span).
U aB12I pos = 0.19oinWC / 4.2.3.3 Accident Total Loop Uncertainty (TLU) U al2Q= U aR12Q - U aB12_pos U a12Q =.5.989 ainWC Accident TLU for quarterly calibration in inWC I cctA-o t 474 1i/y/oo 4.3 CST Level Indication Loop TLU ( LT-107-12A, LT-107-12A(M), LI-107-12A) - Monthly Callbrationso I902/17/v / 4.3.1 Normal Conditions 4.3.1.1 Random e n1R= 4.174einWC Transmitter normal uncertainty from section 3.2.2.1 e n3RM = 9.597 oInWC Indicator normal uncertainty for monthly calibration from section 3.4.2.1.1 U nR13M :e n1R2 + e n3RM 2 U nR13M = 10.466 9InWC Normal Random Uncertainty for indicator loop with monthly calibration. 4.3.1.2 Bias
%LeVeln Ln PM posn From section 2.0. magnitude of bias depends on n point of interest inWC inWC 0
25.0 4.0 101.5 I/ 0.190 I/ 0.007 / U nB13 negn = PM neg
- negn For the indicatIon function, both positive and negative bias at all points are considered.
50.0 199.0 0.372 / 75.0 296.5 / 0.554 / U nB13_pos, := PM Posn 100.0 394.0 / 0.736/
YC.-r7016 RUAJ. I PCN-ODI VYC-706 Rev. 1 ATTACHMENT C PPRGE 19 OF 3;2 Calculation Detall CST Level (RCIC) Monitoring Page 24 of 31 4.4 CST Indication Loop FLU ( LT-107-12A, LT-107-12A(M), LI-107-12A) - Quarterly Calibrationss . I 9§/jCo 4.4.1 Normal Conditions 4.4.1.1 Random e n1 R = 4.174 *InWC Transmitter normal uncertainty from section
.3.2.2.1 e n3RQ = 13.260 ainWC Indicator normal uncertainty for quarterly calibration from section 3.4.2.1.2 UnR13Q:=leniR 2 +ien3RQ2 U nR13Q = 13.901 olnWC / Normal Random Uncertainty for Indicator loop with quarterly calibration.
4.4.1.2 Bias %I-eveln PM negn Lh PM posn From section 2.0. magnitude of bias depends on point of interest inWC inWC InWC
-0.020 / 4.0 / 0.007 /.
-0.506 / 101.5 / 0.190 / U nB13_neg, := PM negn For the indication function, both positive and
- 50. -0.992 / 199.0 / .372/ negative bias at all points are considered.
- 75. -1.478 / 29 6,5/ 54 / U nBI3_posn = PM posn 310. 1-1.964 / 394.0 / 0 4.4.1.3 Normal Total Loop Uncertainty UnR13 :-UfnR13Q U nR13Q = 13.901 ainWC VZ Normal Random uncertainty term for quarterly n
calibration U n13_pos = U nR13 dU nB13 pos Normal positive TLU with bias (Quarterly Cal) U n13_negn :=(U nR13n)'(i1) + U nB13_negn Normal negative TLU with bias (Quarterly Cal)
VYC-tob ROJ. I CXRU-O0 VYC-706 Rev. I ATTACHMENT C Pp6 '0O OF ?z Calculation Detail CST Level (RCIC) Monitoring Page 27 of 31 4.5.2 Module As-Found Calibration Tolerances (FT) Monthly Callbratlonn3 Quarterly Calibratio Module FT (inWC_ FT (Calibration Unitsi *FT*(inWCl
} _, .FT (Callbratioin Units)
. \
Transmitter LT-107-12A & B e ti R = 4.174 vinWC CS-16.mA =0.171 amA wl 8 ti R = 4.174 inWC eCSIR 16 mA = 0.171 cmA / Cs Master Trip Unit e t2RM = 0.975 *InWC c t216 mA = 0.04 .mA Cs Z/ e t2RQ = 1.462 'InWC e t2RQ 16 mA = 0.06 emA 71-LT-1 07-1 2A(M) & B(M) =s . Indicator e t3RM = 9.597 sInWC -= 2.461 .% 'l e t3RQ = 13.260 inlWC t3Q= 3.400 6% 1" LI-1 07-1 2A Cs Cs 4.5.3 Monthly~~ormal/Accident Total Loop Uncertainty (TLU) A UCb' znt LOOp Normal (inWC) Normal (Calib. Units) Accident (InWC) Accident (Calib. Units) Master Trip Unit U n12M = 4.477 .inWC n12M 16 mA = 0.184amA 7' Ual 2M = 5.885 inWC / aCSa2M 16mA = 0.241 omA / Cs LT-1 07-12A(M) & B(M) Indicator U n13M = 12.430ifnWC U1 =3M3.187 %VI U a13M = 13.081 InWC U a13M = 3.354 a% I, LI-1 07-1 2A Cs Cs 4.5.4 Quarterly66NormallAccident Total Loop Uncertainty (TLU) cIcCa t1i4Uits LooP Normal (inWC) Normal (Calib. Units) Accident (InWC) Accident (Calib. Units) Master Trip Unit U nI2Q - 4.613 einWC Un 12 Q-16 mA =0.189mA I- U aI2Q = 5.U89inWC - a12Q-16 mA = 0.246 'mA /11 LT-107-12A(M) & B(M) Cs Cs U ai3Q 415%; Indicator U a1 3Q = 16.362 lnWC - S 4.195a/o U n13Q = 15.865 linWC CS = 4.068 a% / X? Cs LI-1 07-1 2A
VYI-70fb RV 1N,0It, VYC-706 Rev. I ATTACHMENT C PRGE i )OF 3Z Calculation Detail CST Level (RCIC) Monitoring Page 30 of 31 5.3 Evaluation of Revised Setpioint 5.3.1 Quarterly Testing An arbitrary value of 33.2" is chosen as a proposed. new seppoint such that it is larger than the minimum level requirement of 26.5" plus accident uncertainties for quarterly testing. LSP = Process limit + TLU (accident) = Ls + U%120 M1 = SP - LSP L 5 = 26.500 *in U a12Q = 5.989.lnWC // SP := 33.2-in SP = 33.200-in Proposed new setpoint referenced to tank bottom Process Limit referenced to bottom of L 5 = 26.500 -in tank Accident Trip Unit TLU from section U aI2Q = 5.989 inWC Z 4.2.3.3 LSP :- L 5 + aII2Q in /LSP = 32.489 min / LnWC M 1:= SP- LSP M i= 0.711-in 1' W Setpoint Margin for proposed setpoint 5.3.1.1 Determination of calibration setpoint value SP Cal [= SP:=zal. (SP - L 2) + head] in lW 7 SP cal = 25.200 -InWC W New calibration setpolnt in inWC as sensed by the transmitter SP mA := [(SP 0 i ) 16 mAl 4mA 7 SP mA ^ 4.870 omA / New calibration setpoint In mA as measured at trip/calibration unit readout assembly. 5.3.1.2
Conclusion:
The revised setpoint of 4.87 mA Is acceptable because it is higher than the Limiting Setpoint by a Margin of 0.711".
VYI.-701o REBi I CMN-O1 VYC-706 Rev. 1 ATTACHMENT C PA-E £; OF 3Z Calculation Detail .0 CST Level (RCIC) Monitoring Page 31 of 31 Requirement Required Level LSP New Setpoint Marain to LSP Process Limit > 26.5" above bottom (L5) LSP = 32.489in ,/ SP = 33.200-in / M 1 = 0.711 -in V/ 5.3.2 f Monthly Testing
*c.Qt14- e
- VJ/A/oo LSP = Process limit + TLU (accident) = L5 + Ua02M Ml = SP - LSP SP = 33.200 -in Proposed new setpolnt referenced to tank bottom Process Limit referenced to bottom of U
L 26.5008 in tank Ua12M = 5.8 5.8854.1.3.3 / Accident Trip Unit TLU from section
/4nC (Monthly Cal)
LSP L5 U ai2M-in //LSP = 32.385.in / inWC M 1 :=SP- LSP M,1 = 0.815 .Tn / Setpoint Margin for proposed setpoint 5.3.2.1
Conclusion:
The revised setpoint of 4.87 mA is acceptable because It is higher than the Limiting Setpoint by a Margin of 0.815". Requirement Required Level LSP New Setpoint Marain to LSP Process Limit > 26.5" above bottom (Lo) LSP = 32.385 sin / SP = 33.200 sin Z M I = 0.815 in Z4
APPENDIX H VYC-706 Rev. I CCN-O1 Page 3 of 3Z REVIEW CHECKLIST (ER 961090_01) NIA any items not applicable to the calculation or CCN. Requiremant Preparer REeviewer
- 1. Ensure the title page is properly filled out (items that are applicable).
*. Calculation or CCN number on cover
- Title reflects subject Correct QA record status box checked
- Page numbering and count is correct
*. Cycle number is included CNA7 if not applicable)
Initiating document is listed SSC I.D. numbers listed Vendor calculation and revision number listed Vendor safety class P.O. number fisted Superseded calculations listed Keywords assigned Computer codes (input/output) listed Signatures and dates are included and are in correct 4-chronological order. The title page reviewer and approver dates do not predate other dates in the calculation
- 2. The following forms are properly filled out and attached (if applicable):
- Review forms VYAPF 0017.04 (Ensure dated signatures form the preparer and reviewer are included and all comments have been addressed)
- Open Item Listing VYAPF 0017.05 a Evaluation of Computer Code Use VYAPF 0017.06 4/41 AA- 4-a Calculation Database Input VYAPF 0017.07
- Calculation Change Notice VYAPF 0017.08 MIA
- 3. Ensure review of the calculation can be done without recourse to the 4.
originator. Screening EvaluationlSafety Evaluation included.
#-A&
11
- 5. Ensure individuals responsible for each portion of the calculation are Al/A identified when multiple preparers and/or reviewers are used.
Appendix H AP 0017 Rev. 5 Page 1 of 3
APPENDIX H (Continued) [VYC-706 Rev. I CCN-O I Page 2 Of 32 Eieparer Reviewer
- 6. Ensure that the calculation contains a title page, table of contents, calculation objective,method of solution, design inputs and sources, assumptions, calculation, results, conclusions and references.
- 7. Ensure that each page has a page number, calculation number, revision number and CCN number, if applicable.
- 8. Ensure that every page of every attachment (or Appendix) contains its attachment (or Appendix) number.
- 9. Ensure that the methods for revising and correcting the calculation meet the requirements of App. C of AP 0017.
- 10. Ensure that the legibility requirements of App. D of AP 0017 have been met.
- 11. Ensure that the appropriate design inputs (e.g. QA records) were used and the source of these inputs are dearly referenced.
- 12. Ensure that the calculation design information, both external and internal .X --
requirements have been met.
- 13. Ensure that if design specifications were used as input to the calculation the performance characteristics are independently verified and
-44 14.
documented. Ensure that all reviewers' comments have been addressed. 14 l/ 4V PI/ I
- 15. Ensure that input and modeling uncertainties are explicitly addressed in 9701 the calculation. (ER 961 090_02) 44&d
- 16. Ensure that any restrictions andlor limitations on the use of the calculation are clearly stated.
- 17. Ensure that computer codes are used in accordance with App. E of AP 0017.
- 18. Ensure that the applicable Input considerations from App. C to AP 6008 have been incorporated and are explicitly addressed within the calculation.
- 19. Ensure review of I OCFR50.46 reporting requirements has been documented for analyses which assess conformance to IOCFR5O0A6.
Appendix H AP 0017 Rev. 5 Page 2 of 3
APPENDIX H (Continued) VYC-706 Rev. I CCN-O I Page 2s of 3Z Requirement fibaaret Reviewer
- 20. Ensure relevant conditions/limitations have been reviewed for their effect on this calculation and the review is noted in the calculation.
-/ -- 'r --
PREPARER l REVIEWER Name (print) larA S. ItCVnleg.' Name (print) Age bows Organization Exe_ 'Ser-vICs / YDE Organization e , Signature Signature _ _ _ _ _- Date 2/17 Date ___ Appendix H AP 0017 Rev. 5 Page 3 of 3
Page i of I VY CALCULATION REVIEW FORM Calculation Numbers VYC'-7f,6 Revision NumberL-l CCN Number: . lI
Title:
rnAndenntel tnrvng Tnnke I .vel (R1Cr) Mnnitrnenng Reviewer Assigned: Inrdepenrinnt Reviewer - ........ Inhn T.Pwi,.. Required Date: VYC-706 Rev. 1 CCN-01 Comments* Resolution lPage z6-& of 3Z _i I 1 U. _eignature Reviewer Signature % ate Calculation Preparer (Comments Resolved) Date Method of Review: 'KCalculation/Analysis Review O Alternative Calculation s Y gt A , . 1 N' O Qualification Testing Reviewer !%iature (Comments Resolved) D6ate
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. 5
Page l of I VY r CALCULATION REVIEW FORM Calculation Number VC-'70f R evisionNumber- I CCN Number: 01
Title:
rnndenqnte Storage Tank Leval (RCrl) Monitoring Reviewer Assigned: T&C..
& hepartment Required Date: VYC-706 Rev. I CCN-0I Page -127 of 32 Comments* Resolution o sroD oo I //2-//S /
aeviewer gfature Date Calculation Preparer (Comments Resolved) Date Method of Review: 115lculation/Analysis Review O1 Alternative Calculation / O Qualification Testing Reviewer Signature (Comments Resolved) Date
- Commnents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. 5
Page % of t VY CALCULATION REVIEW FORM Calculation Number. wr -7re Revision Number! I CCN Number: 01
Title:
Cnnden-ste Stor11gf Tnnk L evel (RCTCY) Mnnitfnrin Reviewer Assigned: RPaet-tnr EnginPPeering Tlnnrtmnnf Required Date: WC-706 Rev. I CCN-01 1 Page Z bof 3z l Comments* Resolution V~D Ae ,.
-I
- //~IL za2/
aviewer Signature Date Calculation Preparer (Comments Resolved) Date Method of Review: W 'alculationIAn Mysis Review Alternative Calculation g/0 A / 4-e. LZ70 Qualification Testing Rbviewer Signature (Comments Resolved) afe
- Commnents shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. 5
Page I of 1 VY CALCULATION REVIEW FORM Calculation Numbert 7YC-76S Revision NumberL l CCN Number: t1.I
Title:
C(nnden-tfe. tnrsgwe Tikt I. lv(RcTc) Mwnitnring Tannt4v~nt DmA.,it-I I%,VI%.w R r103 5 ~ji5..LUl-A ce ;Vn (f..bfhtf4:af L.LLLLLL. JL14.La.LL&L-iL&A.... Required Date: VYC-706Rev. I CCN-0l page 21 of 3'Z Comments* Resolution Q0 G-~Minl4 t Reviewer Signature Date Calculation Preparer (Comments Resolved) Date Method of Review: E0Calculation/Analysis Review OAlternative Calculation O:Qualification Testing Revler Signature (Comments Resolved) Date
- Comnments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. S
Page I of I VY CALCULATION REVIEW FORM Calculation Number- VY(!-70n Revision Number- . CCN Number: nl
Title:
Condensate Storage TCnTLevel (CJC) Mnn;tnring Reviewer Assigned: System Fnginering neprtment Required Date: VYC-706Rev.1CCN-01 Comments* Resolution PaRe 30 of 2 .. I-
- T+ p S ;nJuiczc a? pc6as op cA
.e- 9 6 p -4. -%I > A.jC M A ^Yke-lpre nep .QtX TVlcW's u treAexeA 0 Yd a-& (vl t. .fv- . qe ;s kyeoMr. _
7e. 4 dl t1 4 * $O 7A.. A te l a fs
- ToB p ct v s 9r s- cc-ti. fhae nyi/ef
< Q 4UoA(-4JC cle A ffsaccM Q. cv ob-1gJ pcte s nc*4;. T~
7VatL e9- X4 0af e.tr+ erpAW -9AM M ch. Revi cr Signature Da e C culation Pr arer (C mments Resolved) Date Method of Review: E}5alculation/Analysis Review O3 Alternative Calculation / 7 G Qualification Testing ewer Sinatu (Commen Resolved) Dae
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. 5
f Page I of I VY CALCULATION REVIEW FORM Calculation Number wiVzn706 RevisionNumber l. CCN Number: _ L l
Title:
Condensate Stnroage Tank Level (RrTrl) Mnnitaring Reviewer Assigned: Nudwr Pnginering Dellartment (eflXP) Required Date: Rev.: ICCN-0 Comments* Resolution Paqe 3 t of .?z ho T 0T ecr Tqr'cN A 2nEV(E/W '
/
43 Reviewer Signature - Date Calculation Preparer (Comments Resolved) Date Method of Review: 3 Calculation/Analysis Review a Alternative Calculation / 03Qualification Testing Reviewer Signature (Comments Resolved) Date
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly. VYAPF 0017.04 (Sample) AP 0017 Rev. S
4 - 7-W Safety Analysis Review Screen Calculation No. Veyi- 70hL Rev. I CCN. I Pz1 C~'SZ This screen is designed to determine if new or revised setpointluncertainty analyses require review by responsible VY department. If necessary the calculation preparer can contact the responsible department for assistance in completing the screen. No Question Answer Has the analytical limit for either normal, accident or environmental conditions changed? 2 o Ifthe answer to question I is No the screening is complete and no review by responsible department is necessary. Ifthe answer to question I is Yes or Unknown, proceed to question 2. 2 Is the setpoint applicable to any of the analysis inthe following areas:3 Short-term containment analysis? (GE/OPL4A) Long-term containment analysis? (GE/OPL4A) Torus Temperature? (DE&S) Appendix R? (DE&S) LOCA? (GE/OPL4) EQ HELB/Heatup ? (DE&S) EQ Radiological? (DE&S) Reactor physics? (GE and DE&S) Transient analysis? (GEIOPL3 and DE&S) A yes to both questions (1)and (2) requires documented review by the VY department responsible for the safety analysis(es) affected. 4 See Notes on Page 2
,I IL/r/2I2 Cal lation Pr pr Date Comments:
Page 1 of 2
VYC-0706, Rev. 1 CCN.02 VY CALCULATION CHANGE NOTICE (CCN) Page I of_ __ CCN Number- 02 Calculation Number VYC-0706 Rev. No. 1 Calculation
Title:
CON1DENSATE STORAGE TANK LEVEL (RCIC) MONTORING Initiating Document: ER-2000-1575 02 VYDCJMMtrMSpec. NoJ other Safety Evaluation Number. N/A Superseded Document N/A Implementation Required: E Yes 0 No Reason for Change: To increase the asnsed normal area tenperature in the CST valve room enclosure from 55-B5eF to 45-100 0F. Description of Change: Revise aperopriao pages as required to incorporate additional Instrument unmertainty (temperature affect) associated with increasing the ambient temperature range for the CST level transmniner to 45-100F Technical Justification for Change: Thc basis for the temperature range of 45-100°P is contained in ER 2000-1575. The tmperatue affect uncertainty is based on the vendor's specifications associated with the CST level transmitter.
== Conclusions:==
- 1. The increase in instrauent uncertainty due to the incease in ambient tempwature has been incolporated into the uncertaintyanalysis..
- 2. This Calculation or CCN is not an implementing document. Therefore, Whis CCN does not require a safety evaluadon-Prepared By/Date Interdiscipline Review Independent Review Approved By/Date By/Date By/Date 1/
Installation Verification/Final Turnover to DCQ Open Items Associated with CCN 0 Yes El No 0 aosed (Section 2.3.2) Installation Verification (Section 2.3A) it Calculation accurately reflects plant as-built configuration, OR O3 NIA, calculation does not affect plant configuration Resolution of documents identifie9.jn the Desl). Output Documents Section of VYA]F 0017.07 (Section 2.3.6) Print Name (f Signature/ 'Iate Total number of pages In package including all attacfiments Note: VYAPF 0017.07 should be included immediately following this farm. 'VYAFF 0017.08 AP 0017 Rev. 7 Page 1 of 1
'I VY CALCULATION DATABASE INPUT FORM VYC-0706, Rev. 1 CCN-02 a Page 2 of _ _
VYC-0706 CCN-02 1I VY CalculationlCCN Number Revision Number Vendor Calculation Number Revision Number Vendor Name: _ PO Number Originating Department: Critical References Impacted: 13 FSAR 0 DBD 0 Reload. "Check" the appropriate box if any critical document is identified in the tables below. EMPAC Asset/Equipment ID Number(s): EMPAC Asset/System ID Number(s): Keywords: For RcvisionlCCN only: Are deletions to General References, Design Input Documents or Design Output Documents required? 3 Yest El No General References
- Reference # IF DOC # REV # Reference Title (including Date, If applicable) (See App. A, Section 3.2.7 for Guidance)
*** I'll Affected Critical Program Reference (_)
I
+ t t t *1*
VYAPF 0017.07 AP 0017 Rev. 7 Page lof 2
VYC.0706, Rev. 1 CCN-02 Page _.3. of ._ Design Input Documents - The following documents provide design input to this calculation. (Refer to Appendix A, section 4)
- Reference # I DOC # REV # Document Title (including Date, If applicable) ***Affected Critical Program Reference U Design Output Documents- This calculation provides output to the following documents. (Refer to Appendix A, section 5)
- Refcrcncc # ' DOC # REV # Document Title (including Date, if applicable) "* Affected Critical Program Reference U I ________I I_____ I 1______
I____________________________________ I______ 1-I ______________ 4-4- __________ 4. 4- + + 4 4.
- 4. 4-4. 4.
_______________________ .5. I A.
*Reference # - Assigned by preparer to Identify the reference In the body of the calculation. **Doc # - Identifying number on the document, if any (e.g, 5920-0264, G91972, VY6.1286) 0*1 Reference Title - List the specific documentation In this column. See attached list Is not acceptable. Design Input/Output Documents should identify the specific design input document used In the calculation or the speclflc document affected by the calculation and not sitply reference the document (e.g.,
VYDC, MM) that the calculation was written to support
" ' Affected Program - List the affected program or the program that reference is related to or part of. If the reference is FSAR, DUD or Reload aASD or OPL), check Critical Reference column and check FSAR, DBD or Reload, as appropriate, on this fonrn (above). + If "yes," attach a copy of "VY Calculation Data" marked-up to reflect deletion (See Section 3.1.8 for Revision and 5.2.3.18 for CCMs).
VYAPF 0017.07 AP 0017 Rev. 7 Page 2 of 2
C-G., - 0 Z, Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I the manual verification of the calculations performed. MathCad 7 stores numbers with a 15-digit accuracy, all calculation outputs displayed within the calculation are rounded from the values stored in MathCad 7. Rounding errors induced by MathCad 7 are assumed to be negligible. Computer specifications: Gateway 2000 G6-233 - Serial number 0008583505 (1214197) Intel Pentium II,233 MHz wI MMX Technology 96 MB RAM Integral Math Co-Processor Software specifications: Microsoft) Windows 95 Microsoft Word Version 97 SR-1 Mathsoft MathCad 7 Professional 2.3. Assumptions 2.3.1. Calibration of instruments is assumed to be at a temperature within the ranges shown in the following table. The RCIC Room (Vol. 52) and Reactor Building (Vol. 21) reference temperatures are per the EQ Manual section 7.4 [Ref. 6.6]. The Condensate Storage Tank is located outside and the level transmitters are located on rack_315 25-66A inside an insulated and un-heated room attached to
~ instrument room are based on diempsea fi the I Stuen
~ST.
/ m normal ambient air temperature extremes expected are as listed in ;ble 2.
; Coo) 20-{SJ Ct67 Ta~~
Plant Area Minimum Maximum Condensate Storage Tank- -4 (00 Instrument Rack 25-66A RCIC Room - Volume 52 -213' 88 F 112 0 F Reactor Building - Volume 21 -280' 62 *F 106 OF 2.3.2. CST water rminimum temperature is maintained 2 50 0F (as read on TI-107-3) per VY Procedure AP-0150, Auxiliary Operator Round Sheet TB/OUT, page 5 of
- 7. The tank is heated by auxiliary steam heating coils. As a conservative value for minimum temperature, the assumed value of 401F from FSAR section 14.5.2 will be used [Ref. 6.21.
CST water maximum temperature is assumed equal to the maximum ambient temperature of 100 IF as identified in FSAR section 2.3.5 and on RCIC Process Diagram 5920-0605 [Ref. 6.25.1]. 2.3.3. The calibration interval for the level transmitters and master trip units is once every operating cycle or 684 days (547.5 days + 25%) per the 'Tech Spec Vermont Yankee Design Engineering Page 9 of 26
Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. 1 Given that Indicator Analyzed Drift (DA) includes trip unit analog output circuit drift, and auxiliary analog circuit Calibration Effect (CE) is included in Indicator CE, and since Seismic Effect of the trip units is 0.0% (2.3.19), the indicator Normal, Testing, and Accident uncertainties will be assumed to include all uncertainties associated with the trip unit auxiliary analog output circuit. 2.3.17. Given that Analyzed Drift (ADR) data is available for each loop component evaluated under this calculation, and given that LI-1 07-12A and LT-107-12A(M) and LT-107-12B(M) are all currently calibrated monthly (trip units may be calibrated quarterly under ITS), these loops will be evaluated for mild environmental conditions for the Reactor Building Vol. 21 and 52 (i.e. normal conditions), and it is assumed that the Analyzed Drift (ADR) term for each includes Temperature Effect (TE), Readability (RD), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), Humidify Effect (HE), and Radiation Effect (RE) for the indicator and trip units [Ref. 6.1 section 3.6.5] under both normal and accident conditions. 2.3.18. Given that Analyzed Drift (ADR) data is available for transmitters LT-1 07-12A.& B, and given that LT-107-12A & B are calibrated each operating cycle, the transmitters will be evaluated for mild environmental conditions (i.e. normal conditions), and it is assumed that the Analyzed Drift (ADR) term includes Temperature Effect (TE), Deadband (DB), M&TE Uncertainty (MTE), Barometric Pressure Effect (PB), Power Supply Voltage Effect (VE), and Humidity Effect (HE) [Ref. 6.1 section 3.6.5] under both normal and accident conditions. adiation Effect (RE) at the CST is assumed to be negligible. eismic Qualification testing of the Rosemount 51 ODU Trip Calibration System is documented in Rosemount Report 376aA Rev. B [Ref. 6.6.1 and Attachment E]. The documented results of testing indicate that the worst case seismic effect on the trip point setting for the twelve (12) channels tested was 0.024% span. 32 of the remaining 35 data results yielded setpoint effects of less than 0.012%. A seismic effect of 0.024% maximum, when compared to repeatability of 0.13%, is insignificant and will be considered negligible for this calculation. 2.3.20. The environmental conditions for the Rosemount 51 ODU specified in Table 5 of Reference 6.15 [Attachment El provide the limiting environments to be used for choosing the appropriate performance specifications. Since the temperature, humidity, and radiation conditions listed for the 'Normal - High environment bound the conditions expected for LT-107-12A(M) & 12B(M) under normal and mild accident conditions (See Table 4), the Trip Point Repeatability and Auxiliary Analog Output specifications of +/- 0.20% will be used (Tables 6 and 7 of Attachment E] for both normal and accident conditions.
- 3. INPUT DATA Data used to calculate loop uncertainties, process corrections, setpoints, and decision points are tabulated in the following sections with the applicable reference or basis noted.
esin Eginerig VerontYanee Pge 4 o 2 Vermont Yankee Design Engineering Page 14 of 26
- V YC 7-6Cd Pau }
VYC-76LS (delta -55 0F). Per the guidance in the Vermont Yankee Setpoint Program Manual, Appendix D, Sections 3.6.6 and 3.6.8, a delta of 30 F is assumed to be included in the drift term. The remaining delta of 25TF will be calculated per the vendor's specifications and addressed separately as Temperature Effect (E).
pd66i; 7 oF Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I 3.2. Environmental Conditions I The following information provides the environmental conditions expected for the components located at the Condensate Storage Tank and in the Reactor Building. Table 4 Environmental Input Data Basis Description Data Ref. 6.2 Table 2.3.2 CST Area Ambient Temperature Extremes R T°F Assumption 2.3.1 CST Rack 25-66A Normal Ambient Temperatur h to 0F Assumption 2.3.6 CST Rack 25-66A Accident Ambient Temp. Ilk to!°F CST Rack 25-66A NormaVAccident Humidity ' Ref. 6.6 & Attach. L RB 280'Elev. (Vol. 21) Normal Temperature 62 to 106 0F Ref. 6.6 & Attach. L RB 280' Elev. (Vol. 21) Accident Temperature 62 to 1060F 2
' RB 280w Elev. (Vol. 21) NormJAccident Humidity 40 to 75%
Ref. 6.6 & Attach. L RB 213'.Efev. (Vol. 52) Normal Temperature 88 to 1121F Ref. 6.6 & Attach. L RB 213' Elev.-(Vol. 52) Accident Temperature 88 to i 20F 2 Ref. 6.6 & Attach. L RB 213' Elev. (Vol. 52) Norm./Accident Humidity 60% average Reactor BIdg. 280' - Vol. 21 (Trip Units) I Ref. 6.6 & Attach L Normal Radiation (40 yr.) 3.50 x 103 Rad y Ref. 6.6 & Attach L Normal Radiation (Quarterly Dose) 2.73 x 10' Rad y Reactor Bldq. 213' - Vol. 52 (Indicator). Ref. 6.6 & Attach L Normal Radiation (40 yr.) 3.50 x 104 Rad y Ref. 6.6 & Attach L Normal Radiation (Quarterly Dose) 2.73 x 102 Rad y 2 Accident temperatures for small break LOCA (mild environment) before two hours. Page 16 of 26 Vermont Yankee Design Engineering Yankee Design Engineering Page 16 of 26
AA16F 8 cs C. C.J 0 Z. Condensate Storage Tank Level (RCIC) Monitoring \WC-706 Rev. I
- 4. CALCULATION'DETAIL The detailed calculation of loop uncertainties, setpoints, testing tolerances, and margins have been performed using MathCad and are documented as Attachment C.
- 5. RESULTS AND CONCLUSIONS 5.1. Total Loop Uncertainty Total Loop Uncertainties (TLU) have been evaluated fdr the RCIC CST Level indication and trip loops and the results are presented in Table 9 below.
Table 9 Total Loop Uncertainty
.. TLU TLU TLU TLU Normal Normal Accident Accident Output Instrument Calibration i % CS : Cal Units +/- % CS +/- Cal Units LT-1 07-12A(M) & B(M) Monthly */ 0 / 1241 C D.O.mA mrnAdcc
____ (CTS) tz lO. IVD I I .2.SaZ5 LI-107-12A Monthly / &"-W % Z3 a-aw/o / (CTS) ( 32$31 3.?-Z3 _.35 5_395 LT-107-12A(M) & B(M) Quarterly 1.48 Oa.49 mAdc, - 0-24 mAdc.
. (TS) -. I.6 D. 205 1.W21Z c.2*it l LI-107-12A Quarterly /ah AAP/
44o / a (ITS) ! .oI
&t~tt1q,221 __ _ _ _
5.2. Setpoint Evaluation 5.2.1. Current Low Level Suction Transfer setpoint As evaluated in Attachment C, section 5.1, the existing Low Level suction transfer setpoint of 4.64 mAdc (decreasing) cannot be supported based on the new requirements for critical height Of submergence of the RCIC suction. The revised Process Limit of 2 26.5' from CST bottom [Ref. 6.14 and Attachment B] includes consideration for the TS requirement that the setpoint be 2 3% and that there be 10,000 gallons reserve at the suction transfer point. See Table 10 below.
- 5.2.2. Revised Low Level Suction Transfer setpoint A revised setpoint is evaluated in Attachment C, section 5.3; the proposed setpoint of 4.87 mAdc (decreasing) supports the requirements for critical height of submergence of the RCIC suction + 10,000 gallon reserve and has adequate margin from LSP to SP. See Table 10 below.
Ven YaeDsg nieeigPg 0o2 Vermont Yankee Design Engineering Page 20 of 26
cSCM - 0 2. Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Table 10 Setpoint Results Existing Setpoint New Setpoint (CTS) New Setpoint (ITS) (4.64 mA) (4.87 rnA) (4.87 mA) Inches 6 Inches 7 Inches6 Inches 7 Inches 6 Cal Units 7 Process Umit (PL) 2Ž26.5 Ž18.5 Ž26.5 18.5 26.5 Ž18.5 Accident Uncertainty I" &895 J 6.S8 N/AN (Monthly Cal - Ua12m) 0- ?- 6. Icm 4V. 4ARS Accident Uncertain N/A N/A N/A N/A .5989 (Quarterly Cal -U.a 20) , . . . 2jo 4.2c , Limiting Setpoint 85fr 2 4385' . 2j38 24 / (LSP) r 3?<. v92, Z4.-q 2.^z 32.sq 36-qqo ot.q Setpoint (SP) i7 27.6 19.6 , 33.2 / 25.2 33.2 / 25.2 Mdtgin (MI) -A 7 -A -7 05146tS1
.- -5S.o9p2- £'.5086 &SOS 0.14L1 0.410 5.3. Calibration a In order to support and implement the results of this calculation, the loop instruments are to be calibrated at nine points based on the following ranges:
Table 11 Module Calibration Ranges Description Value Units Transmitter input range 4 to 394 Inches H2 0 Transmitter output range 4.0 to 20.0 mAdc m/ Indicator input range (Cal current adjust) 4.0 to 20.0 rmAdc Indicator output range O to_100 __ % Trip Unit input range 4.0 to 20.0 / mAdc Trip Unit Lo Setpoint - Auto Suction Xfer 4.87 decr mAdc Test as-found tolerances (FT) and as-left tolerances (CT) are shown below. 6 Referenced to tank botom. 7 As sensed by transmitter, level above transmitter tap (Os) including 4' static head. anke DeignEngneeing Vermnt age21 f 2 Vermont Yankee Design Engineering Page 21 of 26
ccvs - 0 ZR Condensate Storage Tank Level (RCIC) Monitoring VYC-706 Rev. I Table 12 Module Calibration Tolerances AsT) Left (CT) Tag Number Calibration +/-% CS) Cal Units t% CS +/- Cal Units LT-107-12A & B Operating Cycle cCo/9 0.25 0.04 mAdc LT-107-12A(M) & Monthly (CTS) 0.250 0.04 mAdc v 0.19 0.03 mAdc B(M) __ LI-107-12A 8 Monthly (CTS) 2.0 2.0 % 2.0 2.0 % LT-107-12A(M) & Quarterly (ITS) 0.375 0.06 mAdcv 0.19 0.03 mAdc, B(M) I I , LI-107-12A8 Quarterly (ITS) 3.0 3.0 % $ 2.0 2.0 % 5.4. Conclusions and Summary of Recommendations V 5.4.1. Revise setpoint to 4.87 mAdc decreasing. The setpoint is no longer based on simply being greater than or equal to 3% level as per TS Table 3.2.9. Based on tank vortexing effects evaluated under VYC-1844 Rev. 0, the limiting consideration is now based on maintaining a minimum level above the RCIC suction to prevent air entrainment due to vortexing, with the 10,000 ganon reserve requirement added. As such, the references in OP-4355 Rev. 14 to OTech Spec Setting of > 3%6 and VY Trip Setting of *4%" should be revised to reflect the new bases. 5.4.2. For transmitter calibrations, only the Heise 901B (0-400w) is acceptable as the pressure source. Both the HP 3466A and HP 34401A DMMs are acceptable for transmitter calibration. OP-4355 should be revised to incorporate the change in test equipment requirements. All calibrations should be revised to nine-point calibrations. 5.4.3. Applicability list for VYEM-0055 shows model number for LT-107-12A & B as 1153G85 instead of 1153GB5. Revise accordingly. 5.4.4. MPAC for LT-107-12A says Model Number is 1153G85 instead of 11 53GB5. Revise accordingly. 5.4.5. Since there is no Analytical Limit (AL) associated with the RCIC CST Level Indication or suction transfer functions, evaluation of Allowable Value (AV) is not performed for this calculation. VYC-1844 Rev. 0 [Ref. 6.14] determines the process limit for the low level suction transfer point based on system operability requirements. The process limit used for this calculation concurrently satisfies the existing Technical Specification requirement of > 3%. e Indicator tolerances rounded for readabilty. Page 22 of 26 Vermont Yankee Design Engineering Engineering Page 22 of 26
I'IAC6 It or
* *706V-R2 Condensate Storage Tank Level (RCIC) Monitoring WVYC-706 Rev. I 6.26.4. Drawing B-191265, Sheet 4 of 6, Reactor Building Instrument Arrangement, Rev. 20.
6.26.5. Drawing B-1 91259; *Misc. Instrument Arrangement, Rev. 0. 6.27. "ASME Steam Tables,* Thermodynamic and Transport Properties of Steam, Sixth Edition, 1993. (Excerpts -Attachment L) 6.28. AP-01 50, "Conduct Of Operations And Operator Roundse, Rev. 31, 715196, through Dl R Z-eoo - 15 7* 5ss U A rrAPrlr-h0 t-A64 Oe-
,tlePkL- o04 /,Sgr A-6dLMfId~d$ >K (? 0 a F/Sitc/sS I VY-7'1 Vh4WIS
_o _DIII-~ t _-- , - O r.1 l1'1 %1 I Page 26 of 26 V/ermont Yankee Design Engineering
pM-& I- O CC-A) -c > /YC-708 Rev. 1 ATTACHMENT C Calculation Detail GIST Level (RCIC) Monitoring Page 6 of 31 3.2.1.5 Analyzed Drift(DA3 DA 1% 1.0407 % DA 1% = 1.041 A% Transmitter drift in % (Assumption 2.3.12) DA 1 : DA 1 %.CS DA j =4.059oInWC //. Q Transmitter drift In InWC 3.2.1.6 Temperature Effect too ;° g' d°
- .°°;O5 -su Temperature effect during normal and accident E - + !;T P.
conditions are the same and Included In the Analyzed Drift term (Assumption 2.3.18) E 1~:=AO'inWC TE 1 =-el oinWC 3.2.1. r c ress ro Effect (1PB) 8T Barometric pressure effect Is either the effect on the vented side of gage pressure The 1153GB5 is a gage pressure transmitter Transmitters, or the error associated with calibration of an absolute pressure transmitter monitoring a tank vented to atmosphere, therefore .ising gauge pressure test Instruments.. this effect Is negligible per Ref. 6.1 section 3.6.8. PB I := OInWC 3.2.1.8 Humidity Effect (HE) HE 1 := o-inWC Humidity effect during normal and accident conditions are the same and Included In the associated Analyzed Drift term (Assumption 3.2.1.9 Radiation Effect (RE) 2.3.18) REai = REn 1 = 0.0 inWC Radiation exposure at the CST Is negligible and assumed Included In the Analyzed D'nft RE := 0.0*InWC RE .1= 0.000 °lnWC term (Assumptlon 2.3.18) 3.2.1.10 Seismic Effect (SE) SE I := 0.5 % URL SE 1 = 3.750 oInWC / Seismic effect from Table 5 & Attachment D 3.2.1.11 Process Pressure Effects (SP) Since the maximum pressure felt by the transmitter Is 394 inWC+ ambient pressure, SP 1
- 0.000 *InWC static pressure and over-pressure effects and SP I := o.o lnwc corrections for this application are not applicable
PbAt(i/ 3 f6 CiA -0 Zd VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 7 of 31
-4.
3.2.1.12 Power Supply Vottage Effect (VE)
- Power Supply Voltage Effect during normal and accident conditions'are the same and Included in VE t := 0.0 inWC VE 1 =0.000
°inWC the Analyzed Drift term (Assumption 2.3.18) 3.2.2 Transmitter Total Module Uncertainty 3.2.2.1 Normal Conditions MTE ', HE, RE and VE are included in CE I = 0.975 InWC DB I = ° 000 *inWC DA 1 = 4,059 'InWC Anal rift term (Assump. 2.3.18), SP = 0.
= (.,act
/ AQ e nIR=
e n1R =$i'!C Normal transmitter module uncertainty (eniR) for calibration every 684 days 3.2.2.2 Testing Conditions MTE, PB Analyzed ( E, RE and VE are included In term (Assump. 2.3.18), and SP = 0. e tlR:= 2 2I (s]'*(e¢+9,~~o nS5
.8Y Testing transmitter module uncertainty (etIR) e tIR n C1 /
for calibration every 684 days 3.2.2.3 Accident - LOCA (small break) with Seismic & without Radiatioik . C =0. .nWC DB I = 0.°°InWC -DA I - 4.059 .InWC SE 1 = 3.750 alnWC 'T~ re ~qq MTE, P , RE and VE are Included In the Ana 9drift term (Assump. 2.3.18), SP
= 0, and mild environments.
e 7 Accident transmitter module uncertainty (ealR) for calibration every operating cycle (684 days) 3.3 Master Trip Unit LT-107-12A(M) & B(M) (Module 2 - e2) CT 2mA:= 0.06*MA CT 2mA = 0.08 *mA Existing Calibration Tolerance In mAdc per OP-4355 [Ref. 6.7] and Table 6. CT 2 = CT2mA Calibration Tolerance in % span 1a6mA CT 2 % = 0.375 °% Z
#I PA6AS i1#-0 CC.A)- 0o2 VYC-706 Rev. 1 ATTACHMENT C Calculation Detail ;
CST Level (RCIC) Monitoring Page 17 of 31
-A 3.4.2.3 Accident - LOCA (small break) with Seismic & without Radiation i
3.4.2.3.1 Monthly Calibrations CE 3 = 7.800 *InWC DA 3M 2 5.592 .inWC SE 3 = 0.000 *InWC MTE, RD, TE, HE, RE and VE are included in Indicator Analyzed Drift term (Assump. 2.3.17). e a3RM:: JCE 3 2
+ DA 3 M2 + SE 32 e a3RM = 9.597 *InWC L/
Accident Indicator unit module uncertainty (8a3RM) for monthly calibrations (38 days) 3.4.2.3.2 Quarterly Calibrations CE 3 = 7.800 *inWC DA 3Q = 10.723.inWC SE 3 = 0.000 .InWC MTE, RD, TE, HE, RE and VE are Included In 2 Indicator Analyzed Drift term (Assump. 2.3.17). e a3RQ: :J VCE 32+ DA 3 Q2 +SE 3 a a3RQ 13.260 ainWC 1 / Accident Indicator module uncertainty (ea3Ro) for quarterly calibrations (114 days) 4.0 Total Loop Uncertainty 4.1 Master Trip Unit Auto Suction Transfer TLU ( LT-107-12A & B, LT-107-12A(M) & B(M) - Monthly Calibrations (CTS) 4.1.1 Normal Conditions 4.1.1.1 Random 8 n1 nI C Transmitter normal uncertainty from section 3.2.2.1 a n2RM " 0.975 *inWC 7 Trip Unit normal uncertainty from section 3.3.2.1.1 U nR12M :24en1R+en 2 UnR12 W / e X-lormal Random Uncertainty for trip unit loop with (2 monthly calibration.
I1q' '9 Cz/j - O ?, VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring . Page 18 of 31 4..1.2 Sias %Levein PM negn Ln PM Posn From section 2.0. magnitude of bias depends on point of interest InWC InWC inWC 0 -0.020 V/ 0.007 %/ 25.0 -0.506 / 191 .5 / 0.190 ..- 50.0 -0.992 ./ 199.0 k 0.372 Ve PM bias := 0.190inWC For trip unit actuation on decreasing level,
-1.478 -/ 296,5k/ 0.554 "I 75.0 ., positive bias is limiting (sensed level higher than 100.0 -1Q9641 394.0 / 0.736 0le actual). The process temperature bias is U nB2_pos : PM bias . conservatively chosen at the 25% span point with the setpoint expected to be less than 10%
U nB12 pos = 0.190 .inWC / (25 inWC setpoint/390 inWC span). 4.1.1.3 Normal Total Loop Uncertainty (TLU) U n12M j R2 B2ps U n12M .44 a/w Normal TLU In InWC for monthly calibration 4.1.2 Loop UoW These channels are not tested as a loop 4.1.3 Accident - Small Break LOCA with Seismic 4.1.3.1 Random e alRC Transmitter accident uncertainty from section 3.2.2.3 e a2RM = 0.975 .rnWC Trip Unit accident uncertainty from section
/ 3.3.2.3 U aR12M U aRi2 /66 WC t OAccident Random Uncertainty for trip unit loop I-"' with monthly calibration.
PC&F )6 OF coCqQ- CZ. VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 19 of 31 ,, 4.1.3.2 Bias %Leveln PM negn Ln PM posn From section 2.0. magnitude of bias depends on point of Interest InWC InWC InWC 0 -0.020 / 4.0 / 0.007 .0' PM bias : 0.1 90 InWC For trip unit actuation on decreasing level, 25.0 -0.506 / 101.5 / 0.190 '0, positive bias Is limiting (sensed level higher than 50.0 -0.992 / 199.0 / 0.372 ' U a82-pos :- PM bias actual). The process temperature bias Is 75.0 -1.478 I/ 296.5 / 0.554 v ,1 conservatively chosen at the 25% span point 100.0 -1.964 / 394.0 / 0.736 v -I U aB12_pos 2 0.190 *InWC / I with the setpolnt expected to be less than 10% (25 inWC setpointl390 InWC span). 4.1.3.3 Accident Total Loop Uncertainty (TLU) U a1 2 p o s U 2 .Sv51WCl/. vll AccidentTLU In InWC 4.2 M Ion Transfer TLU ( LT-107-12A & B, LT-1M) & B(M) - Quarterly Calibrations (ITS) 4.2.1 Normal Conditions 4.2.1.1 Random I C e OR R C Transmitter normal uncertainty from section 3.2.2.1 e n2RQ = 1.462 clnWC V/1 Trip Unit normal uncertainty for quarterly calihrtlfnns frnm secInn 3 921 .9 U nRI2QA U nR12 .40 WC V/ /Normal Random Uncertainty for trip unit loop. with L Bi quarterly calibration. .
J'AI;6- /7 rF 6 C.N- 0".7 VYC-706 Rev. 1 ATTACHMENT C Calculation Detail ii CST Level (RCIC) Monitoring Page 20 of 31 4.2.1.2 Bias %Leveln PM negn PM posn
- From section 2.0. magnitude of bias depends on point of interest InWC inWC inWC 0 -0.0201 V. 4.0 0.007 v 25.0 -0.506 A/ 101.5 V 0.190 0 50.0 7-0992 V 199.0 0.372 a For trip unit actuation on decreasing level, PM bias := 0.190*inWC 75.0 -1.478 296.5 0.554 w / positive bias is limiting (sensed level higher than
-1.64 394.0 I/ 0.736 'v U nB12_pos PM bras actual). The process temperature bias is conservatively chosen at the 25% span point
/
Z with the setpoint expected to be less than 10% (25 InWC setpointV390 InWC span). U nB12 pos 0.190 nWCI 4.2.1.3 Normal Total Loop Uncertainty (TLU) / ,t'r 1" Un s O~p UUn12Q41I0WC Normal TLU in InWC for quarterly calibration Ic§O1/ 4.2.2 Loop These channels are not tested as a loop 4.2.3 Accident - Small Break LOCA with Seismic 4.2.3.1 Random 7-=) ea1 RaCal Transmitter accident uncertainty from section 3.2.2.3 e a2RQ - 1.462 'inWC v' . Trip Unit accident uncertainty for quarterly calibration from section
/. 3.3.2.3.2 U aRl2Q:4 U aRi2 Q/C V V Accident Random Uncertainty for trip unit loop 4400a with quarterly calibration.
WYC-706 Rev. 1 ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 21 of 31 4.2.3.2 Bias %Leveln PM neg. Ln PM pos, From section 2;0. magnitude of bias depends on point of Interest inWC InWC InWC
-0.020 / 4.0 / 0.007 &/
For trip unit actuation on decreasing level,
-0.506 / 101.5 /
01 PM bias:= 0.1901InWC 25.0 0.190 I/ positive bias Is limiting (sensed level higher 01 50.0 -0.992 / 199.0 / 0.372 ^/ than actual). The process temperature bias is 01 U aB12_pos PM bias conservatively chosen it the 25% span point 75.0 -1.478 k/ 0.554 s. 1100.0 -1.964/ 0.736 6/ with the setpoint expected to be less than U aB12I pos = 0.190 inWC / 10% (25 inWC setpolnt/390 inWC span). 4.2.3.3 Accident Total Loop Uncertainty (TLU) U a1 2Q := U _pos U a12 Z / Accident TLU for quarterly calibration in inWC 4k;ol f . ,qo 4.3 CST Level ntltT TLU ((LT-107-12A, LT-107-12A(M) LI 1-C onthly Calibrations (CTS) 4.3.1 Normal Conditions ; 4.3.1.1 Random e n1RR *Transmitter normal uncertainty from section 3.2.2.1 e n3RM =nW7.nWC Indicator normal uncertainty for monthly calibration from section 3.4.2.1.1 U nR13M C, Normal Random Uncertainty for indicator loop with monthly calibration. %LeVeln PM negn Ln PM POsn From section 2.0. magnitude of bias depends on point of interest 0 25.0 InWC
-0.020 /
-0.506 /
InWC 4.0 101.5 / inWC 0.007 z 0.190 V 4 U nB13.negn:= PM negn For the indication function, both positive and negative bias at all points are considered. 50.0 -0.992 / 199.0 / 0.372 4/ 75.0 -1.478./ 296.5 / 0.554 / U nB13_posn PM pOSn 100.0 -1.964 394.0 s/ 0.73E /
AAk6S I 9 IF CZ J - No-VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Pago 22 of 31 4.3.1.3 Normal Total Loop Uncertainty U nR13 :=U nR13M U nR13M $W C Nor mal Random uncertainty term for monthly n fio43E/ call bration U nl3_pos :=U nR13 U nB13 pos Nor 'mal positive TLU with bias (Monthly Cal) U nI3_negn: (UnR3n)'(-1) +UnnB13_negn 'Mal negative TLU with bias (Monthly Cal)
%Level,In U nR1'3n U nB13_negn U nB13._pos, U n1 3negn U n13.pos, n lnWC P -0.020 /
I 25.0 0.506 1 50.0 10.46M 75.0 S ,-1.478 V 10 ." 4 100.0O -1.964 &/ U n13M ,,In C inding normal TLU (Monthly Cal) of bWC conservatively chosen for all points. 4.3.2 Loop Testing Conmdittions Ehannels are not tested as a loop 4.3.3 Accident - Small Break LOCA with Seismic 4.3.3.1 Random e Transmitter accident uncertainty from section 3.2.2.3 e a3RM - 9.697 *InWC Indicator accident uncertainty from section 3.4.2.3.1 U aR13M U aR13 CC / Accident Random Uncertainty for Indicator loop. with monthly calibration. 11.2:-71
rcwr- *- u C-CA) - O'Z.- VYC-708 Rev. 1 ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 23 of 31
-4.
4.3.3.2 Bias 4 %Levein PM negn n Ln PM pos A From section 2.0. magnitude of bias depends on point of Interest InWC InWC inWC 0 4.0 0.007 / 25.0 -0.508 / 101.5 0.190 / U aBl3 negn :- PM nag, For the Indication function, both positive and 50,0 -0.992 / 199.0 0.372 *, negative bias at all points are considered.
/
75.0 -1,478 V 296.5 0.554 t/ U aB13_posn : PM Posn
/
100.0 -1,964 / 394.0 0.736 / 4.3.3.3 Accident Total Loop Uncertainty U aR13M WCV' U aR13 := U aR13M 1.1- I Accident Random uncertainty term (monthly cal) U a13.posn = U aR13n + U aB13_posn Accident positive TLU with bias (monthly cal) U a13 neg_ := (U aR13n)'+1) + U aBi3negn Accident negative TLU with bias (monthly cal)
%Leveln U aRI3n U aBl3_negn n % hz InWC, 0 0 11. 4.t7i WC/
1 25.0 11. !-7~ 2,71 0.506 2 50.0 11. .U7* -0.992 3 75.0 1 . ,17 1.7 8 / 4 100.0 11.14 *.7) -1.964 L
. W Ua13M i IW C Ua13M wC Thp-beuqding accident TLU (monthly calibration) l3.2 A.\ oN1-e1itrw is conservatfvely chosen for all Zints. (-*.zl1I
84-'£- 71 °F- 4) VYC-706 Rev. I ATTACHMENT C Calculation Detall CST Level (RCIC) Monitoring Pago 24 of 31 4.4 CST Indication Loop FLU ( LT-107-12A, LT-107-12A(M), Ll-107-12A) - Quarterly Calibrations (ITS) 4.4.1 Normal Conditions 4 4.4.1.1 Random e n1RC Transmitter normal uncertainty from section 3.2.2.1 e n3RQ 6iW Indicator normal uncertainty for quarterly calibration from sectIon 3.4.2.1.2 U nRi3Q : U nR13Q +/-2irO4 C Normal Random Uncertainty for Indicator ( .o03 loop with quarterly calibration. 4.4.1.2 Bias %Level~ PM neg. L PM posn From section 2.0. magnitude of bias depends on point of Interest inWc inWC , inWC 0 -0.020 / 4.0 0.007 . 25.0 -0.506 /. 101.5 I/ 0.190 v,
/O U nB13_negn := PM negn For the indication function, both positive and negative blas at all points are considered.
50.0 -0.992 / 199.0 0.372 d 75.0 -1.478 / 296.5 0.554 t UnB13_posn:=P Posn 100.0 -1.964 / I 394.0 ,0.736 J 4.4.1.3 Normal Total Loop Uncertainty U nR13 : U nR13Q n U nR13Q t ic /" Normal Random uncertainty term for quarterly
- calibration l4.,o3 U n13_pos := U nR13n U nB1 3pos Normal positive TLU with bias (Quarterly Cal)
U n13_negn := (U nR13n)'( 1) + U nB13-negn Normal negative TLU with bias (Quarterly Cal)
f/,&&rZ7. ' a ctj - 0 Z VYC-705 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 25 of 31
%Level, U nRI3 " U nBis neg, U nBl3_pos U n13_negn U nl3_pos, n InWC 01 0 0.007 I/ .I 25.0 0.190 / -2 00.0 0.372 "/
3 75.0 0.554 / 4 _O1 0.736 / ing normal TLU (Quarterly Calib) of IC conservatively chosen for all points 4.4.2 Loop Testing Conditions nnels are not tested as a loop 4.4.3 Accident - Small Break LOCA with Seismic 4.4.3.1 Random al S Transmitter accident uncertainty from section 3.2.2.3 e a3RQ = 13.260 inWC Indicator accident uncertainty (quarterly cal) from section 3.4.2.3.2 U aR13Q; U aRi3Q CWC Accident Random Uncertainty for indicator loop with quarterly calibration. 14.62Z 4.4.3.2 Bias %Leveli PM negn Ln PM posn 'From section 2.0. magnitude of bias depends on
% point of interest InWC InWC InWC 0 -0.020 , 4.0 0.007 I/
25.0 -0.506 O/o I/ Vat 0.190 -, UaB13_neg :: PMneg. For the Indication functi'on, both positive and 50.0 -0.992 &,ea 0.372 --' negative bias at all points are considered. 296. a, 75.0 -1.478 1d 0.554 .- U aB13_pos ;- PM pos 100.0 - 1.964 . It 0.736 y
A/jr-6 2-3 oF ccMt - daz VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 26 of 31 4.4.3.3 Accident Total Loop Cnncertainty U aRI3n := U aR13Q U aR3 1 nC Accident Random uncertainty term (quarterly cal) U a13posn := U aR13n + U aB133pos, Accident positive TLU with bras (quarterly cal) U al3_neg, : (U aRl3 ){('1) + U aB13.3_negn Accident negative TLU with bias (quarterly cal)
%Leveln U aR13 UaBl3-neg, U aB 13-posn U a13_negn U a I -Posn n InWC 0~ 0.007 /
0.190 / ( 0.372 / 1 0.554 '/- 0.73B &' U a13Q: I to, iC The bounding TLU (quarterly calibration) ofti 6iinV£Ls conservatively chosen for all 4.5 Summary of Results 4.5.1 Module As-Left Callbratlon Tolerances (CT) CT (InWC1 CT (Calibration Units] Transmitter LT4107-12A & B CT 1 - 0.975 einWC CT 16mA 0.040emA Cs 7/ CT 2 Master Trip Unit CT 2 - 0.731 *lnWC CT '16 mA= 0.03 emA LT-107-12A(M) & B(M) Cs Indicator Li- 107-12A CT 3 = 7.800 inWC CS
- 2.000 '%
7-1
pkOw Z- oe VYC-706 Rev. I ATTACHMENT C Calculation Detail el CST Level (RCIC) Monitoring Page 27 of 31 4.5.2 Module As-Found Calibratlon Tolerances (FT) Monthly Callbratlon (CTS) Quarterly Calibration (CTS) Module FT (InWC)- FT (Calibration Units) FT (InWC) FT (Callbration Units r 4 5b Transmitter LT-107-12A & B e t1V C
- 16*m = D47yor 7, ettiWc 11e 1'*16 1R16. ml==O" Zqt AA */
CS Master Trip Unit e t2RM " 0.975 TnWC es2RM 16-mA = 0.04 *mACI/L/ e t2RQ = 1.462 *lnWC t2.Q,16*mA 0.06 omA /1.- 0 LT-107-12A(M) & B(M) CS Cs et3RQ = 3.400 .% ; Indicator e t3RM = 9.597 'InWC t3RM = 2.461 0% / e t3RQ = 13.260ailnWC Cs cs LI-1 07-12A 4.5.3 Monthly (CTS) Normal/Accident Total Loop Uncertainty (TLU) Loop Normal (InWC Normal (Callb. UnitsI Accident (inWC) Accident (Callb. Units)
. 0 Ua12M Master Trip Unit U n12 inC U nlM .16 0 o=a V, Ua 1 2 nC C.S 16.nA LT-107-12A(M) & B(M) CS A Cs CS a3 5z'I Ua3 .3 Indicator U n13 4 C 139 aIC 33~
LI-1 07-1 2A 4.5.4 Quarterly (ITS) NormallAccident Total Loop Uncertainty (TLU) Normal (Calib. Units) Accident linWC) Accident (Calib. Units) Master Trip Unit CS% U a 12 a LT-107-12A(M) & B(M) CS Cs n12Qi 1BA9> UC 1S3 Indicator U a13 = Cs LU-1 07-1 2A
VYC-706 Rev. 1 ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 29 of 31 (SP mA - 4.mA) SP:= *-390-ini L2 SP 27.600 'in i/
- Current setpoint referenced to tank 16 mA bottom.
It should be noted that the previously calculated setpoint did not consider the requirement for minimum height of submergence due to the effects of potential vortexing within the CST; Inaddition, the calculated TLU used in the setpoint determination was +1-6.82". 5.2 Evaluation of Current Setpoint (4.64 mA = 27.6 InWC above tank bottom) 5.2.1 Current Tech Specs (CTS) - Monthly Testing LSP = Process limit + TLU (accident) = Ls + Ua. 2M Ml SP - LSP SP 27.600 sin U a 12 lCC U al2M LP LSP: L5 i- WC 'IIn LS 2ae *in M 1 :SP - LSP M -- 8eIn V 7 5.2.2
Conclusion:
The current setpont o .64 mA Is not acceptable because It does not satisfy the minimum level requirement of > 26.5" above tank bottom [Ref. 6.14 &Attachment BJ plus Trip Unit TLU. Since the minimum level requirement cannot be met, a new setpoint must be derived which will meet the minimum level requirement for both CTS & ITS. Since the ITS-related uncertainties are more limiting, the quarterly TLU for accident conditions will be used to determine the proposed new setpoint Requirement Ruid LSP Current Setpoint -Margin to LSP Process Limit > 26.6 above bottom (Lo) SP = 27.600 lin M Car
- PAC. Z6 or COJ -o'2; VYC-706 Rev. I ATTACHMENT C Calculation Detail CST Level (RCIC) Monitoring Page 30 of 31 5.3 Evaluation of Revlsed ,etpolnt 5.3.1 Improved Tech Specs (ITS) - Quarterly Testing An arbitrary value of 33.2" Is chosen as a proposed. new setpolnt such that it Is larger than the minimum level requirement of 26.5" plus accident uncertainties for quarterly testing.
LSP = Process limit + TLU (accIdent) = L5 + U8 120 M1= SP - LSP L 5 = 26.500 -in U a12 11 / .;I-- SP:= 33.2 In SP = 33.200 'in Proposed new setpoint referenced to tank bottom L 5 a26.5 > Process Limit referenced to bottom of Ls=6.9DI~r~~>tank U ae Accident Trip Unit TLU from section 4.2.3.3 LSP:= L 5 UaI2QIn L/ L3 - I A 10 M 1 := SP - LSP M 0 Setpoint Margin for proposed setpoint 5.3.1.1 Determination of calibration setpolnt value S ISP - L 2 ) + head . SP cal = 25.200 -inWC ./ New calibration setpoint InInWC as SP cal
'4 in. lnWC '/
sensed by the transmitter r tqP- L 1 , SP mA :=I 4*mA
.i16-mA V SP mA = 4.870 -mA / New calibration setpolnt In mA as SM 390in . measured at trIp/calibratlon unit readout assembl 5.3.1.2
Conclusion:
The revised setpoint of 4.87 mA is acceptable because it is higher than the Limiting Setpoint by a Margi 44".
OA6e: Z,.7 o J- .. I COA) - O Z., VYC-706 Rev. I ATTACHMENT C Calculation Detail a CST Level (RCIC) Monitoring Page 31 of 31
-4; Requirement Required Level New Setolint Margin to LSP LSP38' Process Limit > 26.5" above bottom (L5) LSP 2 '3^.48 n -)/
- SP - 33.200 sn / M Q! 3Z 7 o1 5.3.2 Custom Tech Specs (CTS) - Monthly Testing LSP = Process limit + TLU (accident) = L5 + UaI 2M Ml = SP - LSP Proposed new setpoint SP = 33.200sln referenced to tank bottom L5 n 26.500 in Process Limit referenced to bottom of tank 11 . - J ./Z Accident Trip Unit TLU from section a12 = S-'"' " 4.1.3.3 (Monthly Cal)
LSP:= L 5 ia12M in /LS 3=930n I inWC M1 :-SP - LSP M1 / t. Setpoint Margin for pro ed setpoint 5.3.2.1
Conclusion:
The revised setpolnt of 4.87 mA Is acceptable because It Is higher than-the Limiting Setpoint by a Margin in&. Requirement Required Level LS New Setpoint Marol SP Process Limit > 26.5" above bottom (Lo) LSP 3s31n in SP- 33.200 -n/ M = n
/32.. CSo
02/04/199 THU 0oo FA,: 18022585771 1J~? V- I - --
^ ~~~-1-v...,. Nuclear ce Power VERMONT YANKEE SEOINT CONROL PROGRAM E EIPDU"EEa INTERDEPAR.ThNTAL REVIEW OF CALCULATION: 1 WC- -7o4 REVISIONOa VYC- 706 -Revision I AIT:CDENAGEIo_
VY'C706 Rcvision 1, has been prepared and independently reviewed. The Departnents Impacted by this calaclation arc requested to reYiew the results of this calculation, concurwith the results and/or reconunerdations, aad docunent the departmentes acccptanmc prior to the calculation beingapprovcd.
- 1. Summaryn 'his calculation cYalates fth uncertaintyfor tbe ReactorC Isolation Cooling (RCIc) System Aute Suction Transfer on Low CST Level as well a the RCC altemate shutdown CS1 Level1 Indication LooD fornornal andPost Accidentconditions. hteloop components cyaluated 2re as follows:
LT-107-12A & B. LT-107-12A(M) & B(M), and L[-107-)2A
- 2. Calculatlon Ooen Items: AP.0028 to be Assigned None ' '
- 3. Department Review - contact the SelpolntProgramManagr(G.rHenperler if not in agreernent with the concluslonmstatemmets.
3.1 .,Vpmont Yankee S&C 3.la. The Calibration Scctions of O-4355 for LT-1 07-12A & RBL-1 07-12A(M) & BN). and LT-1 07-1 2A will roquire the following clhanges bised on CIS and montlly calibrations for the indicator and trip units
- l. Add to procedure OP-43S5 as follows: A 9'j
- a. Limiting Setpoint (LSP):
CT1S LT-107-12A(" & BOA() -32inches' (4 c)dc0 ) Referenced to bank Bottom (equivaleto 435. otransit) aapplied
- b. LT-107-12A &1BTransmitterl4odule Calibration As-Found LT-107-12A&B /+/-O.I\
- c. LT-107-12A(M)&B" riTpUnk As-Found
&Found :t,0 Auto Suction Transfer (Monthly Cal) AMS-Adc 00
- d. U-107-12A ldicatorModucl Calibratlon As-Found:
As-Found U--107-12A (Mondliy Cal)
- 2.0 1/a
- c. Revise Read to reflec NA
- f. ltevise the M&TErequirements of OP-4355 to remoe the fise 130A.03.
'he following test equiptent (or equivalent) is recommended for use:
Gauge Hlclse 901B (0-400 inwe) DMM HP34401Aor3466A
I,. 4 Page___ of ___ VY CALCULATION REVIEW FORM Calculation Number. VYC-0706 Revision Number: 1 CCN Number. 02
Title:
CONDENSATE STORAGE TANK LEVEL (RCIC) MONITORING Reviewer Assigned: igneRequired Date:_ 3 Interdiscipline Review 0-Ddependent Review VYC-0706, Rev. 1 CCN-02 Comments* Resolution Page .Z7 of l AeQ YU KONco -barde 6 _ __ ___ _ o4 rp VY4P7:vA17Z,7 eLs C42stq ! Zf7yot 4 kcoweJ 4 '/4 tj IL e 1 2JŽ Reviewer Signature tDate esolved) ( kll cfa CaIulansn Preparer (CRevi
- / qljo Dat 61 Jethod of Review:
Sig at culation/Analysis Review C u .R l O Alternative Calculation ___/_1_3___lot o Qualification Testing Reviewer Signature (Comments Resolved) Date
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
VYAPF 0017.04 AP 0017 Rev. 7 Page lofI
TABLE I TE Number 2001-048 CST Level and Volume _ Vol. From Vol. From CST CST CST HPCI Elevation Admin.Limit Standpipe Volume Inst. Level Level ft In Down Down (gallons) (inches) % 286 6 . 491,632 394 100.00% Level Instrument Range [Design Input 1, Attachment 2] Admin. Limit 0 157,480 121 30.00% VYOPF0150.10, pg. 9, Rev. 34 [Gen. Ref. 6] Standplpe 259 3 66,096 0 91,384 67 16.15% G-191176 Sh. 1 (Design Input 71 I 0j1b HPCI Max. Setpolnt HPCI Process Limit 256 255 2.51 4.54 110,772. 122,963 44,676 56 867 l 34,517 30.5 20.54 6.79% 4.24% HPCI Setpoint + Uncertainty [DI 2, CCN-03, p. 10] 28.2" above CST bottom [Design Input II 254 11.7 128,887 62.791 28,593 15.7 3.00% Current TS limit [General Reference 8] HPCI Critical Height 254 8.34 133,000 66,904 24,480 12.34 2.14% 20.0" above CST bottom [Design Input 1] HPCI Suction Centerline 254 6 135,864 69,768 21,616 10 5920-3594 Rev. 2 [Design Input 4] CST Level Instrument Tap 254 0 143,208 77,112 14,272 4 0.00% Level Instrument Range [Design Input 1, Attachment 2] CST Bottom 253 0.34 157,480 91,384 0 -7.66 CST floor thickness=0.34" [Design Input 11 CST Pad 253 0 . CST Pad Elevation [Design Input 8l Vol. From Vol. From CST CST CST RCIC Elevation Admin.Llmit Standpipe Volume Inst. Level Level ft in Down
- Dovn (gallons) (Inches) %
286 6 491,632 394 100.00% Level Instrument Range[Design Input 1. Attachment 2] Admin. Limit 0 157,480 121 30.00% VYOPF0150.10. pg. 9, Rev. 34 (Gen. Ref. 6] Standpipe 259 3 66,096 0 91,384 67 16.15% G-1 91176 Sh. 1 [Design Input 7] RCIC Max. Setpolnt 256 3.2 109,915 43,819 47,565 31.2 6.97% RCIC Setpoint + Uncertalnty [Dl 3, p.21] RCIC Process Limit 255 2.84 125,044 58,948 32,436 18.84 3.81% 26.5" above CST bottom [Design Input 1] RCIC Critical Height 255 1.04 127,247 61,151 30,233 17.04 3.34% 24.7" above CST bottom [Design Input 1] 254 11.7 128,887 62,791 28,593 15.7 3.00% Current TS limit [General Reference 8] RCIC Suction Centerline 254 6 135,864 69,768 21,616. 10 5920-3594 Rev. 2 [Design Input 4] CST Level Instrument Tap 254 0 143,208 77,112 . 14,272 4 0.00% Level Instrument Range[Design Input 1, Attachment 2] CST Bottom 253 0:34 157,480 91,384 0 -7.66 CST floor thickness-0.34* [Design Input 1] CST Pad 253 . 0 I I_ . CST Pad Elevation [Design Input 8] V- &,U X - meP ig,144 AII ~oIahe j5iti or tLawoVi/'hAt5.}}