ML031560699

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Technical Specification Pages for Vogtle Electric Generating Plant, Units 1 & 2
ML031560699
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 06/04/2003
From: Rinaldi F
NRC/NRR/DLPM/LPD2
To: Gasser J
Southern Nuclear Operating Co
Rinaldi F, NRR/DLPM/LPD2-1, 415-1447
References
TAC MB5046, TAC MB5047
Download: ML031560699 (17)
v • d • e


Text

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the SLs specified in Figure 2.1.1-1.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained < 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.4 Within -24 hours, notify the General Manager-Nuclear Plant and Vice President-,Nuclear.

2.2.5 Within 30 days a Licensee Event Report (LER) shall be prepared and submitted to the NRC pursuant to 10 CFR 50.73.

2.2.6 Operation of the unit shall not be resumed until authorized by the NRC.

Vogtle Units 1 and 2 2.0-1 Amendment No. 96 (Unit 1)

Amendment No. 74 (Unit 2)

SLs 2.0 670:

2 660 ~~ 66024 5ps1g

_ ;< __~~a - DO NOTAREA INTHIS OPERATE i650- 22_psig W60 . - -- - -

630 ----------

620- -1920 s - - -

610' ACCEPTABLE 570 - OPERATION - - - - -

560 _{ l. = =

55o4 0 10 20 30 40 50 60 70 80 90 100 110 120 PERCENT OF RATED THERMAL POWER Figure 2.1.1-1 Reactor Core Safety Limits Vogt le Units1 and 2 2.0-2 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY kIAtUre SR 3.3.1.16 ---- I mJ I t ;:

1. Only required when not performed within previous 31 days.
2. Verification of setpoint is not required.

Perform COT. After each MODE 3 entry for unit shutdown and prior to exceeding the P-9 interlock trip setpoint.

Vogtle Units 1 and 2 3.3.1-13 Amendment No. 96 (Unit 1)

Amendment No. 74 -(Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instnmentatlon I APPUCABLE MODES OR NOMINAL OTHER TNMA SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REOUIREMENTS VAWE SETPOINT(n)

1. Manual Reactor 1,2 2 . SR 3.3.1.13 NA NA Trip 3 (a), 4a), 5 (a) 2 C SR 3.3.1.13 NA NA
2. Power Range Neutron Flux
a. High 1,2 4 D SR 3.3.1.1 S 111.3% RTP 109% RTP SR 3.3.12 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15
b. Low 1(b), 2 4 E SR 3.3.1.1 S 27.3% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15
3. PowerRange 1,2 4 E SR 3.3.1.7 5 6.3% RTP 5% RTP Neutron Flux High SR 3.3.1.11 wth time with time PosIfive Rate constat constant k2sec 2 sec.
4. Intermediate 1 (b), 2(0) 2 F,G SR 3.3.1.1 S 41.5% RTP 25% RTP Range Neuton SR 3.3.1.8 Flux SR 3.3.1.11 2(d) 2 H SR 3.3.1.1 5 41.9% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.11 (continued)

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) Below the P-10 (Power Range Neutron Flux) Interocks.

(c) Above the P-S (Interrnediate Range Neuton Flux) nterlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) Interocks.

(n) A channel Is OPERABLE wt an actual Trip Selpoint value outside Its calibration tolerance band provided the Trip Setpolnt value Is conservative with respect to its associated Allowable Value and the channel s readjusted to wIthin the established calibration tolerance band of the Nominal Trip Setpolnt. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.

Vogtle Units 1 and 2 3.3.1-14 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 9)

Reactor Trip System nstunentation APPUCABLE MODES OR OTHER NOMINAL SPECIFIED REOUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDMONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT(n)

5. Source Range 2 (d) 2 IJ SR 3.3.1.1 S .7 E5 1.0 E5 Neutron Flux SR 3.3.1.8 cps cps SR 3.3.1.11 J,K SR3.3.1.1 1.7ES 1.0E5 (a)_4(a), 2 SW ~~SR 3.3.1.7 CPS CPS SR 3.3.1.11 I L SR 3.3.1.1 NA NA 3 (e), 4 (e), 5(e) SR 3.3.1.11
6. OvertemperatureAT 1.2 4 E SR 3.3.1.1 Reter to Note I Refer to Note 1 SR 3.3.1.3 (Page 3.3.1-20) (Page 3.3.1-20)

SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15

7. Overpower ET 1,2 4 E SR 3.3.1.1 Refer to Note 2 Refer to Note 2 SR 3.3.1.7 (Page 3.3.1-21) (Page 3.3.1-21)

SR 3.3.1.10 SR 3.3.1.15 (continued)

(a) With RTBs closed and Rod Control System capable of rod withdrawal.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(ej With the RTBs open. In this condion, source range Function does not provide reactor trip but does provide Input to the High Flux at Shutdown Alarm System (LCO 3.3.8) and Indicatln.

(n) A channel Is OPERABLE with an actual Trip Setpo1nt value outside ts calibration tolerance band provided the Trip Setpoint value is conservative with respect to Its associated Allowable Value and the channel Is readjusted to within the established calibration tolerance band of the Nominal Trip SetpoinL. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary I response to plant conditons.

Vogtle Units 1 and 2 3.3.1-15 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

I RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 d 9)

Reactor Trip System Instrumentaton I APPUCABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDrTIONS REOUIREMENTS VAWE SETPOINT(n)

8. Pressurizer Pressure
a. Low 1() 4 M SR 3.3.1.1 2 1950 pslg 1960(g) psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15
b. Hgh 1,2 4 E SR 3.3.1.1 < 2395 psg 2385 ps1g SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15
9. Pressurizer Water 1(0 3 M SR 3.3.1.1 5 93.9% . 92%

Level - High SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Fow- Low
a. Single Loop 1 (h) 3 per loop N SR 3.3.1.1 2 89.4% 90%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.1 5

b. Two Loops I( 3 per loop M SR 3.3.1.1 89.4% 90%

SR 3.3.1.7 SR 3.3.1.1 0 SR 3.3.1.15 (continued)

(1) Above the P-7 (Low Power Reactor Trips Block) Interlock.

(g) Tine constants utilized In the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and I second for lag.

(h) Above the P-8 (Power Range Neutron Flux) Interlck (1) Above the P-7 (Low Power Reactor Trips Block) Interock and below the P-8 (Power Range Neutron Flux) Interlck.

(n) A channel Is OPERABLE with an actual Trip Setpoint value outside Its calibration tolerance band provided the Trip Setpolnt value Is conservative with respect to Its associated Allowable Value and the channel Is readjusted to vthin the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary In response to plant conditions.

Vogtle Units 1 and 2 3.3.1-16 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

I RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 d 9).

Reactor Trip System Instrunentaton I APPUCABLE MODES OR NOMINAL OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE' FUNCTION CONDMONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT(n)

11. Undervoltage j(fl 2perbus M SR3.3.1.9 'a9481 V 9600V-RCPs SR 3.3.1.10 SR 3.3.1.15
12. Underlrequency 1 (f 2 per bus M SR 3.3.1.9 a 57.1iH 57.3 Hz RCPs SR 3.3.1.10 SR 3.3.1.15
13. Steam Generator 1,2 4 per SG E SR 3.3.1.1 a 35.9% 37.8%

(SG) Water Level - SR 3.3.1.7 Low Low SR 3.3.1.10 SR 3.3.1.15

'(continued)

(I) Above the P-7 (Low Power Reactor Trips Block) interiock.

(n) A channel is OPERABLE with an actual Trp Setpoint value outside ts calibration tolerance band provided the Trip Setpoint value Is conservative with respect to its associated Allowable Value and the channel Is readjusted to ithIn the established calibration tolerance band of the Nominal Trip Setpolnt A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary In response to plant conditions.

Vogtle Units 1 and 2 3.3.1-17 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 9)

Reactor Trip System Instrmentation I APPUCABLE MODES - NOMINAL SPECIFiED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT(n)

14. Turbine Trip
a. Low Fiuld Oil 1j) 3 0 SR 3.3.1.10 500 psig 580 pslg Pressure SR 3.3.1.16
b. Turbine Stop 10) 4 P SR 3.3.1.10 2 90% open 96.7% open Valve Closure SR 3.3.1.14
15. Safety Injection (SI) 1.2 2 trains a SR 3.3.1.13 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)
16. ReactorTrip System Interlocks
a. Intermediate 2 (d) 2 R SR 3.3.1.11 1.2E-5% RTP 2.0E-5% RTP Range SR 3.3.1.12 Neuton Fiux P-S
b. Low Power I 1 per train S SR 3.3.1.5 NA NA Reactor Trips Bxk, P-7
c. Power Range 1

.4 S SR 3.3.1.11 5 50.3% RTP 480hoRTP Neutron. Flux, SR 3.3.1.12 P.8

d. Power Range I 4 S SR 3.3.1.11 s 523% RTP 50% RTP Neuton Flux, SR 3.3.1.12 P.9
e. Power Range 1.2 4 R SR 3.3.1.11 (I.m)

Neutron Flux 0l.m)

SR 3.3.1.12 P-10 and Input to P-7

f. Turbie I 2 S SR 3.3.1.10 S 12.3%S Impulse 10% Impulse Impulse SR 3.3.1.12 Pressure Pressure Pressure, Equivalent Equivalerit P-13 turbine turbine (continued)

(d) Below the P-6 (Intermediate Range Neutron Flux) Interlocks.

(D Above the P-9 (Power Range Neutron Flux) Interlock (i For the P-10 input to P-7, the Allowable Value Is S 12.3% RTP and the Nominal Trip Setpolnt Is 100/e RTP.

(m) For the Power Range Neutron Flux. P-10. the Allowable Value Is a 7.7% RTP and the Nominal Trip Setpoit Is 1O% RTP.

(n) A channel Is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpolnt value Is conservative with respect to ts associated Allowable Value and the channel Is readjusted to within the estabrished calibrton tolerance band of the Nominal Trip Setpoint. A Trip Setpolnt may be set more conservative than the Nominal Trip Setpoint as necessary In response to plant conditfions.

Vogtle Units 1 and 2 3.3.1-18 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

I RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 6 of 9)

Reactor Trip Systern Instnrnentation I APPUCABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDMONS REQUIREMENTS VAWE SETPOINT(n)

17. Reactor Trip 1,2 2 trains T,V SR 3.3.1.4 NA NA Breakers(k) 2 trains C SR 3.3.1.4 NA NA 3 (a), 4 (a), 5 (a)
18. Reactor Trip 1.2 1 each per U,V SR 3.3.1.4 NA NA Breaker RTB Undervoltage and Shunt Trip 3(a), 4(a), 5(a) 1 each per C SR 3.3.1 A NA NA Mechanisms RTB
  • 19. Automatic Trip 1,2 2 trains Q,V SR 3.3.1.5 NA NA Logic 3 (a), 4 (a), 5(a) 2 trains C SR 3.3.1.5 NA. NA (a) Wfith RTBs closed and Rod Control Systern capable of rod wfthdrawal.

(k) Including ary reactor trip bypass breakers that are racked hI and closed for bypassing an RTB.

(n) A channel Is OPERABLE with an actual Trip Setpoint value outside Its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Alowable Value and the channel Is readjusted to within the established calibration tolerance band of the Nominal Trip Setpolnt A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary In response to plant conditions.

Vogtle Units 1 and 2 3.3.1-19 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

4I RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 9)

Reactor Trip System Instrumentation I Note 1: Overtem'eratureDelta-T The Allowable Value of each Input to the Overtemperature Delta-T function as defined by the equation below shall not exceed Its as-left value by more than the following:

(1) 0.5% AT span for the AT channel (2) 0.5% AT span for the T,, channel (3) 0.5% AT span for the pressurizer pressure channel (4) 0.5% AT span for the 11(AFD) channel I AT {l+tS) 1 F {l+r 4 s)r 1 1 (o) 1 100- S 1-K2 T -' -K3 {P'-P}-fl(AFD)I ATO {I + 525) {l+s)J { + 'Is)sj {I+¶6) . J Where: AT measured loop specific RCS dffferential temperature, degrees F ATo Indicated loop specific RCS differential at RTP, degrees F lead-lag compensator on measured differential temperature I +T2S

1¶2 time constants utilized In lead-lag compensator for differential temperature: s, =0 seconds, 2 0 seconds .1.

I +T3S lag compensator on measured differential temperature

-A3 time constant utilized In lag compensator for differential temperature, S 6 seconds I Ki fundamental setpolnt, S 114.9% RTP I

K2 modifier for temperature, 2.24% RiTP per degree F 1+S5S lead-lag compensator on dynamic temperature compensation S4, S5 time constants utilized In lead-lag compensator for temperature compensation: T4 2 28 seconds, 5 4 seconds T measured loop specific RCS average temperature, degrees F 1+¶6s lag compensator on measured average temperature s6 time constant utilized In lag compensator for average temperature, S 6 seconds r

1K3 Indicated loop specific RCS average temperature at RTP, S 588.4 degrees F modifier for pressure, = 0.177% RTP per psig

1. I p measured RCS pressurizer pressure, psig I reference pressure, 2 2235 psig s Laplace transform variable, Inverse seconds Vogtle Units 1 and 2 3.3.1-20 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 8 of 9)

Reactor Trip System Instrumentation Note 1: Overtemoerature Dela-T (continued) f(AFD) modifier for Axial Flux Difference (AFD):

1. for AFD between -23% and +10%, = 0/0 RTP
2. for each % AFD Isbelow -23%, the trip setpolnt shall be reduced by 3.3% RTP
3. for each % AFD is above +10/, the trip setpoint shall be reduced by 1.95% RTP 1+ ¶4 S)r11 (o) The compensated temperature difference - T - I shall be no more negative than 3 degrees F.

(1 + SS) L 1+ 16s)

Note 2: Overpower Delta-T The Allowable Value of each Input to the Overpower Deta-T Function as defined by the equation below shall not exceed Its as-eft value by more than the following:

(1) 0.5%T span for the AT channel (2) 0.5% AT span for the T&,, channel EATo

[ AT {1 + 2rls) 1 l+ r2s) 1 L K4-7 1-K) 11+Kr7s4L l+rs) ] L1 .)J

- f1r2(AFD)]

J Where: AT measured loop specifoc RCS differential temperature, degrees F ATo Indicated loop specific RCS dfferential at RTP, degrees F 1+tMs lead-lag compensator on measured differential temperature 1+12S T1 12 time constants utilized In lead-lag compensator for differential temperature: , = seconds, T2 = 0 seconds 11+3s lag compensator on measured differential temperature time constant utilized In lag compensator for differential temperature, S 6 seconds K., fundamental setpolnt,:s 110% RTP modifier for temperature change: 22% RTP per degree F for Increasing temperature, 2 0°%PTP per degree F for decreasing temperature

'Ps 11+r, rate-lag compensator on dynamic temperature compensation T7 time constant utitized In rate-lag compensator for temperature compensation, 2 10 seconds T measured loop specific RCS average temperature, degrees F

~1 1+us lag compensator on measured average temperature Vogtle Units 1 and 2 3.3.1-21 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 9 of 9) I Reactor Trip System Instrumentation Note 2: Overtemoerature Delta-T (continued) I TS time constant utilized In lag compensator for average temperature, S 6 seconds I Ks modiier for temperature: 0.244% RTP per degree F for T > T, = 0/o RTP for T S r r indicated loop specific RCS average temperature at RTP, s 588.4 degrees F s Laplace transform variable, Inverse seconds f2(AFD) modfler for Axial FIux Difference (AFD), = 0/6 RTP for all AFD Vogtle Units 1 and 2 3.3.1-22 Amendment No. 128 (Unit 1)

Amendment No. 106 (Unit 2)

Ig a  %

Reactor Core SLs B 2.1.1 E

I-U, go 0 20 40 60 80 100 120 Percent of Rated Thermal Power (%)

Figure B 2.1.1-1 (page 1 of 1)

REACTOR CORE SAFETY LIMITS VS. BOUNDARY OF PROTECTION Vogtle Units 1 and 2 B 2.1.1-7 Revi sion No.

RTS Instrumentation B 3.3.1 BASES APPLICABLE 6. OvertemeratureAT (continued)

SAFETY ANALYSES, LCO, and as close as possible to 588.4 °F. The instrument uncertainty APPLICABLITY calculations and safety analyses, in combination, have accounted for loop variation in loop specific, full power, indicated AT and Tayg. With respect to Ta,g, a value for T' common to all four loops is permissible within the limits identified in the uncertainty calculations. Outside of those limits, the value of T' will be set appropriately to reflect indicated, loop specific, full power values. In the case of decreasing temperature, the compensated temperature difference shall be no more negative than 3 F to limit the increase in the setpoint during cooldown transients. The engineering scaling calculations use each of the referenced parameters as an exact gain or reference value. Tolerances are not applied to the individual gain or reference parameters.

Tolerances are applied to each calibration module and the overall string calibration. In order to ensure that the Overtemperature AT instrument channel is performing In a manner consistent with the assumptions of the safety 1.

analyses, it is necessary to verify during the CHANNEL OPERATIONAL TEST that the magnitude of instrument drift from the as-left condition is within limits, and that the input parameters to the trip function are within the appropriate calibration tolerances for the defined calibration conditions (Ref. 9).

The LCO requires all four channels of the Overtemperature AT trip Function to be OPERABLE. Note that the Overtemperature AT Function receives input from channels shared with other RTS Functions. Failures that affect multiple Functions require entry into the Conditions applicable to all affected Functions.

In MODE 1 or 2, the Overtemperature AT trip must be OPERABLE to prevent DNB. In MODE 3,4, 5, or 6, this trip Function does not have to be OPERABLE because the reactor is not operating and there is insufficient heat production to be concerned about DNB.

(continued)

Vogtle Units I and 2 B 3.3.1-19 Revision No. 3

RTS Instrumentation B 3.3.1 BASES APPLICABLE 7. Overpower AT (continued)

SAFETY ANALYSES, LCO, and Delta-T 0 , as used in the overtemperature and overpower APPLICABILITY AT trips, represents the 100% RTP value as measured for each loop. This normalizes each loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power conditions as assumed in the accident analyses. These differences in RCS loop AT can be due to several factors, e.g., difference in RCS loop flows and slightly asymmetric power distributions between quadrants. While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific AT values.

Therefore, loop specific ATo values are measured as needed to ensure they represent actual core conditions.

The value forT is a key reference parameter corresponding directly to plant safety analyses initial conditions assumptions for the Overpower AT function. For the purposes of performing a CHANNEL CALIBRATION, the values for K4, 15, Ka, and r are utilized in the safety analyses without explicit tolerances, but should be considered as nominal values for instrument settings.

That is, while an exact setting is not expected, a setting as close as reasonably possible is desired. Note that for r, the value for the hottest RCS loop will be set as close as possible to 588.4 F. The instrument uncertainty calculations and safety analyses, in combination, have accounted for loop variation in loop specific, full power, indicated AT and Tavg*. With respect to Tayg, a value for T" common to all four loops Is permissible within the limits identified in the uncertainty calculations.

Outside of those limits, the value of T" will be set appropriatelylo reflect indicated, loop specific, full power values. The engineering scaling calculations use each of the referenced parameters as an exact gain or reference value.

Tolerances are not applied to the individual gain or,reference parameters. Tolerances are applied to each calibration module and the overall string calibration. In order to ensure that the Overpower AT instrument channel is performing in a manner consistent with the assumptions of the safety I analyses, it is necessary to verify during the CHANNEL OPERATIONAL TEST that the magnitude of instrument drift from the as-left condition is within limits, and that the input parameters to the trip function are within the appropriate calibration tolerances for defined calibration conditions (Ref. 9). Note that for the parameter K 5 ,

(continued)

Vogue Units 1 and 2 B 3.3.1-21 Revision No. 2

C. -

RTS Instrumentation B 3.3.1 BASES REFERENCES 2. FSAR, Chapter 6.

(continued)

3. FSAR, Chapter 15.
4. IEEE-279-1971.
5. 10 CFR 50.49.
6. WCAP-11269, Westinghouse Setpoint Methodology for Protection Systems; as supplemented by:

Amendments 48 and 49 (Unit 1) and Amendments 27 and 28 (Unit 2), deletion of RTS Power Range Neutron Flux High Negative Rate Trip.

  • Amendments 60 (Unit 1) and 39 (Unit 2), RTS Overtemperature AT setpoint revision.

Amendments 57 (Unit 1) and 36 (Unit 2), RTS Overtemperature and Overpower AT time constants and Overtemperature AT setpoint.

Amendments 43 and 44 (Unit 1) and 23 and 24 (Unit 2),

revised Overtemperature and Overpower AT trip setpoints and allowable values.

. Amendments 104 (Unit 1) and 82 (Unit 2), revised RTS Intermediate Range Neutron Flux, Source Range Neutron Flux, and P-6 trip setpoints and allowable values.

. Amendments __ (Unit 1) and __ (Unit 2), revised Overtemperature AT trip setpoint to limit value of the compensated temperature difference and revised the modifier for axial flux difference.

Amendments __ (Unit 1) and - (Unit 2), revised Overtemperature AT and Overpower AT trip setpoints to increase the fundamental setpoints K, and K4 ,and to modify coefficients and dynamic compensation terms.

7. WCAP-10271-P-A, Supplement 1, May 1986.
8. FSAR, Chapter 16.
9. Westinghouse Letter GP-1 6696, November 5, 1997.

(continued)

Vogtle Units 1 and 2 B 3.3.1-65 Revi si on No . 5

-a  ?%-

. ; RTS Instrumentation B 3.3.1 BASES REFERENCES 10. WCAP-1 3632-P-A Revision 2, uElimination of Periodic (continued) Sensor Response Time Testing Requirements," January 1996.

11. WCAP-14036-P-A Revision 1, HElimination of Periodic Protection Channel Response Time Tests," October 1998.

.12. WCAP-14333-P-A, Rev. 1,-October 1998.

13. WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.

Vogtle Units I and 2 B 3.3.1-66 Revision No. 1 l

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