ML17348A926
| ML17348A926 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/03/1991 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17348A925 | List: |
| References | |
| NUDOCS 9106070246 | |
| Download: ML17348A926 (41) | |
Text
ATTACHMENT 1 TECHNICAL SPECIFICATION MARKUP AND DESCRIPTION OF THE CHANGES FPL LETTER L-91-152 Pi06070246 9i0603 PDR ADOCK 05000250' PDR
Attachment:
PageI 1 of 3 Change 1 In Section 2.2, Limiting Safety System Settings, page 2-3, was revised as part of amendment 140/135. This change is identical with that requested in the Reactor Protection System Setpoints (RPSS) proposed licensee amendment (PLA) submitted by Florida Power and Light (FPL) letter L-90-417, dated December 19, 1990. This change request should be deleted from the RPSS PLA since the PLA is identical to the current Technical Specifications, (amendment 140/135) .
Change 2 In Table 2.2-1, page 2-4, items 5, 6, 9, and 10 were revised as part of amendment 140/135. These values are identical to those requested by the RPSS PLA except the S value in item 5 was 3.0 instead of the 2.5 requested in the RPSS PLY The 2.5 value was generated by the analysis as the result of a change in instrumentation. New upgraded protection chan-nel pressure transmitters with an increase in instrument span from 800 to 1000 psig were added to the Pressurizer Pressure Control System. The justification for this change is provided on page 7 of,FP&L letter L-91-86, dated April 3, 1991. This FP&L letter was submitted to amend the Turkey Point Technical Specification 3/4.2.5, Power Distribution Limits, DNB Parameters, Limiting Condition for Operation and the Bases Section 3/4.2.5, Power Distribution Limits, DNB Parameters.
Items 5, 6, 9, and 10 have been removed from the RPSS PLA except for the value of 2.5 for S in item 5 and the associ-ated 8 footnote. With the changes requested in the RPSS PLA and amendment 140/135 incorporated into Table 2.2-1, the footnote on page 2-10 is no longer applicable and the g flag associated with Allowable Value was removed from pages 2-4, 2-5 and 2-6.
Change 3 In Table 2.2-1, pages 2-5 and 2-6, items 15.b., 16., 18.,
19., and 20 were revised as part of amendment 140/135.
These values are identical to those requested by the RPSS PLA. The remaining changes on pages 2-4, 2-5, and 2-6 of the RPSS PLA remain valid. The changes were justified in WCAP 12745 Revision 0. With the changes requested in the RPSS PLA and amendment 140/135 incorporated into Table 2.2-1, the g footnote on page 2-10 is no longer applicable and the 0 flag associated with Allowable Value was removed from pages 2-4, 2-5 and 2-6.
The gg footnote on page 2.5 has three values which add up to 7.4 %, while the number footnoted is 7.3 %. This difference was due to the rounding of all four numbers to the nearest tenth after the addition was performed.
Change 4 On page 2-7, Table Notations for Table 2.2-1, the changes requested by the RPSS PLA were all incorporated in amendment
I l
'll h
~
Page 2 of 3 140/135 except for the definitions of w w and x,. These changes were justified in WCAP 12632 and 12745. The terms Eggs are already defined as lead lag compensator terms and do not require individual definitions. The RPSS PLA needs to be revised to eliminate this page from the request.
Change 5 On page 2-8, Table Notations for Table 2.2-1, the changes requested by the RPSS PLA were incorporated in TS amendment 140/135 except for two typos in amendment 140/135. Under Note 1< f~ should be f,. There is no f~ term in the overtem-perature delta-T equation. The f, term is in the overpower delta-T equation under Note 3 and is defined under Note 3.
In addition, the P'erm under Note 1 should be '/ 2235 psig and not just = 2235 psig. Changing f, to f, and P' 2235 psig to P'/ 2235 psig are the only remaining changes needed in the RPSS PLA for page 2-8. The other changes should be removed from the RPSS PLA. These changes were justified in WCAP 12632 and WCAP 12745.
The greater-than-or-equal-to function is provided to aid the technicians. The greater-than-or-equal-to function provides a conservative direction to leave the setpoint if it can not be left on the exact prescribed value.
Change 6 On page 2-9, Table Notations for Table 2.2-1, the changes requested by the RPSS PLA were incorporated in TS amendment 140/135 except the RPSS PLA gave K4 as '/ 1.09 instead of =
1.09 and K, as '/ 0.02 instead of = 0.02. RPSS PLA defined t', as '/ 10 s instead of = 10 s. With the exception of the above three changes, amendment 140/135 incorporated all the changes requested by the RPSS PLA. These changes are justi-fied in WCAP 12745. These three changes will remain in the RPSS PLA. The other changes will be removed from the RPSS PLA. The definitions of t, and c, are not needed and should be deleted.
The greater-than-or-equal-to and the less-than-or-equal-to functions are provided to aid the technicians. The greater-than-or-equal-to and the less-than-or-equal-to functions provide a conservative direction to leave the setpoint can not be left on the exact prescribed value.
if it Change 7 On Page 2-10, Table Notations for Table 2.2-1, all of the changes requested in the RPSS PLA were incorporated in TS amendment 140/135; These changes were justified in WCAPs 12745 and 12632. With the changes requested in the RPSS PLA and amendment 140/135 incorporated into Table 2.2-1, the g footnote on page 2-10 is no longer applicable. With the exception of removing the 5 footnote, no other changes are need on this page.
Change 8 On page B 2-3 and B 2-3a, all the changes requested by the
FPL L-91-152 Attachment Page ) 'of 3 RPSS PLA were incorporated except for some word addition-
/deletion/substituting changes, paragraph structure changes and one removed comma. These changes were justified by WCAPs 12745 and 12632. The differences between the current TS, (amendment 140/135) and the RPSS PLA are insignificant, therefore no changes should be requested in the RPSS PLA.
The request to revise these pages should be removed from the RPSS PLA.
Change 9 For LCO 3.3.2, page 3/4 3-13, all the changes requested by the RPSS PLA were incorporated by amendment 140/135 with the exception of the tense on one word. A review of the wording determined either tense would be correct, therefore the request to revise this page should be removed from the RPSS PLA.
Change 10 For Table 3.3-3, on pages 3/4 3-23, 24, and 25, all the changes requested by the RPSS PLA are still valid. Line items l.a., 1.b., 1.f. steam line flow-high coincident with T,~ Low, 2.a., 3.a.l), 3.a.2), 3.a.3), 3.b.l), 3.b.2),
3.c 1), 3.c.2), 3.c.3), 4.a., 4.b., 4.f. steam line flow--
~
high coincident with t,< --low,5.a., S.b., G.a., G.c., G.d.,
G.e., and 7.a. were revised as part of amendment 140/135 and except for some periods missing from the "N. A."s do not need further revision. These items should be removed from the RPSS PLA. The rest of the changes on these pages remain valid.
Change 11 For Table 3.3-3, items 7.b. and 7.c. were revised as part of amendment 138/133. Additional changes requested by the RPSS PLA were made in amendment 140/135. The changes made as part of amendment 138/133 were not covered by the RPSS PLA.
No additional changes are needed for these two items. These two items should be deleted from the RPSS PLA.
Change 12 For Table 3.3-3, items 8.b., 9.a., 9.b., 9.d., and the Table Notations were revised in amendment 140/135. These changes were included in the RPSS PLA. An additional change is needed to item 8.b. and the Table Notations. RPSS PLA changes to 8.a., 9.c., and 9.e. are still required. The changes to items 8.b., 9.a., 9.b., and 9.d. should be re-moved from the RPSS PLA. These changes are justified in WCAP 12745.
Change 13 For the Bases 3/4.3.1 and 3/4.3.2, pages B 3/4 3-1 and B 3/4 3.1a, all changes requested in the RPSS PLA were incorporat-ed in amendment 140/135 except for one deletion (two sen-tences) and some minor wordsmithing. Because there was no justification for the deletion of the two sentences in WCAP 12745, and because the remaining unincorporated changes were insignificant, the request for changes to the bases for 3/4.3.1 and 3/4.3.2 should be deleted from the RPSS PLA.
SAFETY LIMITS AND LIMI G SAFETY SYSTEM SETTINGS
- 2. 2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY: As shown for each channel in Table 3.3-1.
'CTION:
a.'ith less 5'Reactor Trip System Instrumentation or Interlock Setpoint ':=.~: '<:.;..
conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the setpoint consistent with the Trip setpoint value within permissible calibration tolerance.
- b. With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table.2.2-1, either:
- l. Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or
- 2. Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
EQUATION 2. 2-1 Z+R+SgTA where:
Z = The value for column Z of Table 2.2-1 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value of Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowance in X of span) of Table 2.2-1 for the affected channel.
TURKEY POINT - UNITS 3 4 4 2-3 AMENDMENT NOS. 14QAND 135
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS;
~
r FUNCTIONAL UNIT ALLOMANCE TA Z S TRIP SETPOINT ALLIABLE VALUE I. Manual Reactor Trip N.A. N.A. N.A- N.A.
- 2. Power Range, Neutron Flux 7.5 Qsg Aa ll<~~o
d.o ag,ng p,s'4
<~
3.
- b. Low Setpoint Intermediate Range, Neutron Flux J 3'i5 ppj
-kW ~
,>I go vu
<25K
<25X of l
of RTP*"
RTP""
31%
<~l of RTP*"
of RTP
- 4. Source Range, Neutron Flux 54
<10s cps <~x 10s cps Q,
- 5. Overtemperature dT 7.2 4.8 See Note 1 See Note 2
- 6. Overpower dT 5.3 3.1 2.0 See Note 3 See Note 4 y.K l $ 'l P
- 7. Pressurizer Pressure-Low >1835 psig >~ psig
"'. Pressurizer Pressure-High <2385 psig z Qc99'~
psig
- 9. Pressurizer Mater Level-High 8.0 6.8 4. 0 <92X of instrument <92.2X of ins en(
span span
- 10. Reactor Coolant Flow-Low 4.6 2.7 0.8 >90X of loop >88.7X of loop design flow" design flow" g,33 /, 'I jfi~a
- 11. Steam Generator Mater >15X of narrow >~X of narrow Level Low-Low range instrument range instrument span span
- p. g g g~ P~yymw1+<> Pi>sx< ~>
g I (A'T>iJ >~
- Loop design flow = 89,500 gpm
""RTP = RATED THERMAL POMER
TABLE 2.2-1 (Continued)
PC REACTOR TRIP SYSTEH INSTRUHENTATION TRIP SETPOINTS m
C)
M FUNCTIONAL UNIT ALLOWANCE TA Z S TRIP SETPOINT ALLOWABLE VALUE I
C:
- 12. Steam/Feedwater Hismatch Flow tP Qp.
3- Feed Flow "~~> Feed Flow+ >3 ~+
Coincident Mith below steam flow below steam flow l/l gi 2.
Steam Generator Mater >15K of narrow >~X of narr~
Level-Low range instrument range instrum~
span span
+Pe 0 g,l2. N,O pop bats v~h~p g,gS lm v~/<g<
- 13. Undervoltage - 4.16 kV Busses A and B mach-~
~.9
- 14. Underfrequency - Trip of Reactor
. Coolant Pump Breaker(s) Open
>56.1 Hz >~ Hz
- 15. Turbine Trip pD
/,p y3
- a. Auto Stop Oil Pressure >45 psig >~peag
- b. Turbine Stop Valve N.A. N.A, N.A ~ Fully Closed *"" Fully Closed "*"
Closure
- 16. Safety Injection Input N.A e N.A, N.Ae N. A. N.A.
from ESF m Reactor Trip System 7.
Interlocks C)
CA 4m~i'10-
- a. Intermediate Range 'I g amp Neutron Flux, P-6 C) g,ex~4'mp'imit switch is set when Turbine Stop Valves are fully closed. l~e ',;
~ ),7@5 ~el 5ii 56a~ lJ<e 8/~gy g,1%% 5pnySiWJ~vi~Flowa>Jg >S 5l'<~ ie~ yP~
p"e~gc~a:,
1%
r>
I ~
Y
'e
- ~1 TABLE 2.2-1 Continued 4
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT ALLOWANCE TA Z S TRIP SETPOINT ALLOWABLE VALUE
- b. Low Power Reactor Trips Block, P-7 K8, N.+. )P,4 8
- 1) P-10 input OX of RTP*" <~Md RTP"*
Wge "MiWe Jg,d'@
- 2) Turbine First Stage OX Turbine Power <~RbTurbio+wer Pressure fg.DPg
- c. Power Range Neutron 45X of RTP~" <~SPA RTP"*
Flux, P"S
+, Qo Q,Og
- d. Power Range Neutron Flux, P"10 g RX of RTP** ~~% RTP""
- 18. Reactor Coolant Pump N.A N.A N.A N.A. N.A.
Breaker Position Trip
- 19. Reactor Trip Breakers N.A N.A N.A N.A. N.A.
- 20. Automatic Trip and Inter lock N.A N;A N.A N.A. N.A.
logic
""RTP = RATEO THERMAL POWER
t~ S 0
Vy H
g4
TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 1: OVERTEMPERATURE hT ST ~1
~ ts (1 )<ST (K -K (~l ~ tS)[T(1 )
1+ teS 1+ teS e e (1+ teS) 1+ teS Where: AT Measured AT by RTD Instrumentation
~1+t S Lead/Lag compensator on measured hT; x>=8s, x2 =3s 1 + x2S Lag compensator on Neasured hT; xs = Os 1+ ts hT Indicated hT at RATED THERMAL POWER Kg 1. 095; K2 0.0107/4F;
~1+ t S The function generated by the lead-lag compensator for T
+ ls avg dynamic compensation; Time constants utilized in the lead-lag compensator for T
, xq = 25s, 3 s; Average temperature, 4F; Lag compensator on measured Tavg 76 Os 574.2 F (Nominal T at RATED THERMAL POWER);
0.000453/psig; Pressurizer pressure, psig;
TABLE 2.2-1 Continued TABLE NOTATIONS Continued NOTE 1: (Continued) pl 2235 psig (Nominal RCS operating pressure);
Laplace transform operator, s-;
and (AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(1) For q
- q between - 14K and + 10X, f> (hI) = 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that the magnitude of qt - qb exceeds - 14', the hT Trip Setpoint shall be automatically reduced by 1.5X of its value at RATED THERMAL POWER; and (3) For each percent that the magnitude of qt - qb exceeds + 10K, the dT Trip Setpoint .shall be automatically reduced by 1.5X of its value at RATED THERMAL POWER.
NOTE 2: The channels maximum trip setpoint shall not exceed its computed setpoint by more than 1.5X of instrument span.
TABLE 2.2-1 Continued TABLE NOTATIONS Continued rn D
M NOTE 3: (Continued)
I 0.00068/ F for T > T" and Ke = 0 for T < T",
C:
As defined in Note 1, CIl Col Indicated T at RATED THERHAL POWER (Calibration temperature for hT Qo instrumentation, < 574.24F),
a As defined in Note I, and 0 for all hI NOTE. 4: The channel's maximum trip setpoint shall not exceed its computed trip setpoint by more I than 1.4X of instrument span.
O C/l O
f shall If no al able val and no allowance, so be the allo le value Z, or S is s ified as in ed by [ ], t t C7 CAl Ol
TABLE 2.2-1 Continued TABLE NOTATIONS Continued NOTE 3: OVERPOWER AT 1+t 1+
hT TeS S
1+
1 SsS
<AT (K o s
- K s
~ [T,.
(~s 1+ tqS
)
(1+ tsS)
T- K (1
(1+ xeS)
- T") - fe (ni)}
Where: 4T As defined in Note 1, As defined in Note 1, 1 + TIES As defined in Note 1, 1 + v3S Xg As defined in Note 1, As defined in Note 1,
- 1. 09,
~~ 0.02/4F for increasing average temperature and 0 for decreasing average temperature,
~tS + The function generated by the rate-lag coipensator for T dynaiic 1 xqS compensation, Time constants utilized in the rate-lag compensator for Tav T 0 s 1 + xeS As defined in Note 1, As defined in Note 1,
I 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES
~ ~
2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor trips are set for each functional unit. The Trip Setpoints have been selected to ensure that the core and Reactor Coolant System are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engi-neered Safety Features Actuation System in mitigating the consequences of accidents. "The setpoint for a reactor trip system or interlock function is
,;. considered to be adjusted consistent with the nominal value when the "as measured" setpoint is within the. band allowed for. calibration accuracy.
To accommodate the instrument drift that may occur between operational tests and the accuracy to which setpoints can be measured and calibrated, Allow-able Values for the Reactor Trip Setpoints have been specified in Table 2.2-1.
Operation with setpoints less conservative than the Trip Setpoint but within the specified Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. If no value is listed in the Allowable column; the setpoint value is the limiting setting.-
For some functions, an optional provision has been included for determining the OPERABILITY of a channel when its trip setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical'ombination of the other uncer-tainties in calibrating the instrumentation. In Equation 2.2-1, Z + R + S (
TA, the interactive effects of the errors in the rack and the sensor, and tlie "as measured" values of the errors are considered. 1, as specified in Table
,2.2-1, in percent span,, is, the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of their measurement. TA or Total Allowance is the difference, in percent span, between. the trip setpoint and the value used .in the analysis for reactor trip. R or Rack Error is the "as measured" deviation, in percent span, for the affected channel from the specified trip setpoint. S or Sensor Drift is either the "as measured" deviation of the sensor frea its calibration point or the value specified in Table 2.2-1, in percent span, from the analysis assumptions. Use of Equation 2.2-1 allows for a sensor drift factor, an increased rack drift factor, and provides a threshold value for REPORTABLE EVENTS.
The methodology to derive the Trip Setpoints includes an allowance for instrument uncertainties. Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and other instrumen-tation utilized in these channels are expected to be capable of operating within the al.lowances of these uncertainty magnitudes.
Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance. Being that there is a small. statistical chance TURKEY POINT - UNITS 3 4 4 B 2-3 AMENDMENT NOS. 14QAND 135
- 2 2 LIMITING SAFETY EM SETTINGS BASES that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level. In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity. The functional z,;;~... capability: at-.:the specified trip'etting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. This prevents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System. J Manual Reactor Tri The Reactor Trip System includes manual Reactor trip capability.
TURKEY POINT UNITS 3 8r. 4 B 2-3a , AMENDMENT NOS. 14QAND 135
INSTRUMENTATION 3/4.3.2 l
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-2 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3,3-3.
APPLICABILITY: As shown in Table 3.3-2.
ACTION:
With an ESFAS Instrumentation or Interlock Trip Setpoint trip less conservative than the value shown in the Trip Setpoint""column but . '-".;. I'.
conservative than the value shown in the Allowable Value column 'ore of Table 3.3-3, adjust the Setpoint consistent with the Trip Setpoint value within permissible calibration tolerance.
- b. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-3, either:
- 1. Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-3 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. that Equation 2.2-. 1 was satisfied for the affected channel, or
- 2. Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3-2 until the channel is restored to OPERABLE status with its setpoint ad)usted consistent with the, Trip Setpoint value.
EQUATION 2. 2-1 Z+R+SgTA where:
Z. = The value for column Z of Table 3.3-3 for the affected channel, R = The "as measured" va1ue (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value of Column S (Sensor Error) of Table 3.3-3 for the affected channel, and TA = The value from Column TA (Total Allowance in X of span) of Table 3.3-3 for the affected channel.
C, With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-2.
SURVEII LANCE RE UIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
TURKEY POINT - UNITS 3 CL 4 3/4 3"13 AMENDMENT NOS.140AND 135
TABLE 3.3"3 m ENGINEERED SAFETY FEATURES ACTUATION SYSTEH N A N CD TRIP
~ FUNCTIONAL UNIT ALLOMANCE TA Z S SETPOINT ALLOMABLE VALljEg I
c= 1. Safety Injection (Reactor Trip, Turbine Trip, Feedwater Isolation, Control Room Ventilation Isolation, ~p Eidddd ~jdddd d)ef) n'4 Start Diesel Generators, Contain- ~, W)),ws, a,
~~ ment Phase A Isolation (except Hanual SI), Containment Cooling Fans, g~ls) ggppillJliV) $ifp Containment Filter Fans, Start yg,g g 5&<~h~ 8'f'-~~)
Sequencer, Component Cooling Mater, +g0$ lnz~ ~
Start Auxiliary Feedwater and Intake
-Cooling Mater)
+ 6g
+era
]'ldddand'p,P~ pqi~r-
~baht 0 dyaJ co~>~~(~ ~g j) I l~~
- a. Manual Initiation N.A, N.A. N.A N.A. N.A.
Cay I b. Automatic Actuation Logic N.A N.A. N.A. N.A. N.A.
High u,2 po C. Containment Pressure <Ij psig psig Low I+CO ) 730 >>lX de Pressurizer Pressure
),$ '7 pgn+
>kBS, psig gOP
>~
//+
psig
- e. High Differential Pressure Between the Steam Line..
<~ psi <~ psi Header and any Steam Line.
m
/go 7 z,S4 C7 Stean Line Flow-High A f di d fd d as follows: A hp corresponding to CD rdn s de, ~dd at OX load increaS-CA
~pPf 2 0
)P~zra ic ing linearly ao-a-CD corres onding to C7 d
>>Fp 5~~+ +l at full load.
ad 2,s 8 ~pan '6r mA sa'd'or
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IN UMEN A ION TRI S TPO N S C)
TRIP .
~ FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUE
- 5. f g) 57 Q -
Coincident with: p.p 9 psig Steam Generator iA, CA Pressure Low or T "-.Low 4.0 2.0 1.0 >543'F >542.5 F avg
- a. Automatic Actuation Logic N.A . N.A5 N.A4 N.A. N.A.
and Actuation Relays gd gl
- b. Containment Pressure High- <$ 48-psig +'~~psig High Coincident with:
Containment Pressure High psig <~psig gd
- 3. Containment Isolation
- a. Phase "A" Isolation
- 1) Manual Initiation N.A> N.A. N.A. N.A. N.A.
- 2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays CD
- 3) Safety Injection see item 1 See Item 1 above for all Safety m Injection Trip Setpoints and Allowable Values.
- b. Phase "B" Isolation
- 1) Manual Initiation N.A. N.A. N,A. N.A. '. N.A.
Cl CJl
I, Hl
~'
4
5~
(
~ I ~
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM N UMNA 0 S 0 C)
TRIP.
w FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUE¹ I
Q 3. Containment Isolation (Continued)
- 2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays Qo gp,O l,4 ZI'P 24'~
- 3) Containment Pressure High-High psig <~ psig Coincident with:
Containment Pressure-"High psig <~ psig Ventilation Isolation
~~
C. Containment
- 1) Containment Isolation N.A. N.A. N.A. N.A. N.A.
Manual Phase A or Manual Phase B
- 2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays
- 3) Safety Injection see item 1 See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
m
- 4) Containment Radio-activity-High (1)
Parti cul ate (R-11)
<6.1 x lgs CPH t'aseous (R-12)
See (2) f P.
~ '
Zmf<<y-id g>~~~a'PA
~-)Z) 5 Steam Line Isolation Xi~C~)
- a. Manual Initiation N.A. N.A. N.A. N.A. N.A I
7
J" 'I ~
~ ~
(
4 p +u+ln~ 4L'Pl<>~ ~>~-
~//~$ i ~ dp cn>>~ lp
.']
J (~go gas'l>g
'~~~,
I TABLE 3.3-3 (Continued)
~~a"" ~
ops i~~
ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INST UNENTA ON TRI SE P IN Pg,'~ ~la gll l~~J Zl TRIP.
~ FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUE¹ I e g 4. Steam Line Isolation (Continued)
- b. Automatic Actuation Logic N.A. N.A. H.A.
~
Actuation Relays and gg,5 J, 4 d.> gn g(r 'f
- c. 'ontainment Pressure High" v 's j. g psig, High Coincident with: gaP ~, P f,O..:.
Contailnt Pressure High t: 3 psig psig
- f. Steam Line Flow High )Ca7
<A as function defined follows: A hp
~
corresponding to
~ese, r/ at OX load increaS-n linearly le=.a
~Pod ao rres onding to a
~ r Fjm I at full load.
Coincident with:
Steam Line Pressure-Low
(, Q ~,9
~
pig fs >K-~paig 9'tF ~
or av 4.0 2.0 1.0 >5434F. $542.5 F R5. Feedwater Isolation ID a. Automatic Actuation Logic N.A. N.A, N.A. N.A. '- N.A.
and Actuation Relays 8 Safety Injection
- b. see item 1 See Item 1. above for all Safety.
CV Injection Trip Setpoints and Allowable Values.
TABLE 3.3-3 (Continued)
ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH I
IN T UHENTA N TRI S TPO N C)
-I FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUES
~
I
- 6. Auxiliary Feedwater (3) 9'RIP g ~
c a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays
].
- b. Steam Generator Water Level Low-Low
>15% of narrow >~X of narrow range instrument range instrument span. span.
- c. Safety Injection see item 1 See Item l. above for all Safety Injection Trip Setpoints and Allowable Values.
- d. Bus Stripping see item 7 See Item 7. below for all Bus Stripping Setpoints and Allowable Values.
- e. Trip of All Hain Feedwater N.A. N.A~ N.A. N.A. N.A.
Pump Breakers.
- 7. Loss of Power a.- 4.16 kV Busses A and 8 N.A N.A, N.A N.A. N.A.
ITl CD
~
(Loss of Voltage) fTl ED lA 8
C7
k TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUHENTAT ON TRIP SETPO N S ED TRIP
~ FUNCTIONAL UNIT ALLO@ANCE TA Z S SETPOINT ALLOWABLE VALUES I
Q 7. ,-= Loss of Power (Continued) c/l b 480V Load Centers (Instantaneous Relays)
Qe Degraded Voltage Load Center
[ ] 3 [ 3 418Vi5V (10 sec 4 1 sec delay)f 3B [ 3 3 f 3 423VXSV (10 sec t 1 sec delay)f I
3C [ 3 f I f ] 429V15V (10 sec a 1 sec delay)f ]
CQ 3D [ 3 [ 3 [ 3 429VKV (10 sec a 1 sec delay) f ]
[ 3 [ 3 [ 407VXSV (10 sec t 1 sec delay)[ 3 3 f 3 [ 3 423V15V (10 sec a 1 sec delay) f ]
3 [ 3 f 3 419Va5V (10 sec k 1 sec delay)[
4D f 3 [ 3 [ 3 404Vi5V (10 sec i 1 sec delay)[
CV m Coincident with:
Safety Injection and see item 1 See Item 1. above for all Safety Injection Trip Setpoints and C) Allowable Values.
Cil CD Diesel Generator N.A." N.A.
Breaker Open C7
~
(
l h
9
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM NSTRUHEN AT ON RIP SET OINTS C)
TRIP w FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUE I
c= 7. Loss of Power (Continued)
- c. 480V Load Centers (Inverse Time Relays)
Qo Degraded Voltage Load Center 3A 3[ 3 416VRSV(60 sec l:30 [
sec delay) 3B f 1f 3 426V15V(60 sec f30 [ 1 sec delay) 3C [ 3[ 3 436VKSV(60 sec i30 [
sec delay) 3D [ 1[ 1 437VXSV(60 sec %30 [
sec delay) 4A 1f 3 424ViSV(60 sec t30 [ 3 sec delay) 4B [ 1[ 1 422VLSV(60 sec 130 [ 1 sec delay) 4C [ 3f 1 433VLSV(60 sec 230 [ 1 m sec delay)
C3
[1[ 3 432VaSV(60 sec sec delay) f30 f 1 l/l Coincident with:
8 Diesel Generator Breaker Open N.A. N.A. N.A N.A. N.A.
I a
~ ~
TABLE 3.3-3 (Continued) D ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUM NTATION TRIP SE OINTS TRIP
~ FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLOWABLE VALUES I
g 8. Engineering Safety Features Actuation System Interlocks 44 ply" gott c~
C/l a."-- Pressurizer Pressure psig Qo b;-'- T avg Low $ .0 2.0 1.0 2000 f543 F peig 542 5 oF
~
- 9. Control Room Ventilation Isolation
- a. Automatic Actuation Logic and Actuation Relays N.A. N.A. N.A. N.A. N.A.
- b. Safety Injection see item 1 Item 1. above for all Safety d,A'eeAllowable Values.
Injection Trip Setpoints and
- c. Containment
'igh (1)
Radioactivity p'8. p',k Particulate (R-ll)
.1 x 10s CPM Caseous (R-12)
~~
~ g,g>IP
~> Jj)
See (2) @~~a p u,S CA'->+
gg8 m d. Containment Isolation N.A o N.Aa N.A. N.A. N.A.
Manual Phase A or Hanual Phase B pt Wk
~
- e. Air Intake Radiation Level < 2 mR/hr 2.83 mR/hr TABLE NOTATIONS (1) Either the particulate or gaseous channel in the OPERABLE status will satisfy this LCO.
J 0 K P
't
~ ~
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INS RUHEN A ON R P SE IN Cl
~ TABLE NOTATIONS continued I
~ (2) Containment Gaseous Honitor Setpoint = 3 2 x 10~
CPH,
( F )
Actual Pur e Flow Mhere F Design Purge Flow (35,000 CFH)
Setpoint may vary according to current plant conditions provided that the release rate does not exceed allowable limits provided in Specification 3.11.2.1.
(3) Auxiliary feedwater manual initiation is included in Specification 3.7.1.2.
kIf no allowable value, ALLOWANCE (TA), Z or S is specified so indicated by f ], the trip setpoint shall also be the allowable value.
m C7 m
CI CA C7
r 4
'4h '
3/4. 3 INSTRUMENTATION BASES
~ 5 i
3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEH and ENGINEEREp SAFETY FEATURES A UA I N SYS NS RUMENTA N The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that: (I) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint (2) the specified coincidence logic is maintained, (3) sufficient redundancy is main-tained to permit a channel to be out-of-service for testing or maintenance (due to plant specific design, pulling fuses and using jumpers may be used to place channels in trip), and (4) sufficient system functional capability is
". "" -". available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses. The Surveillance Requirements speci-fied for these systems ensure that the overall system functional capability is maintained, comparable,.to the original design standards. The, periodic surveil-lance tests performed at the minimum frequencies are sufficient to'emonstrate this capability.
Under some pressure and temperature conditions, certain surveillances for Safety Injection cannot be performed because of the system design. Allowance to change modes is provided. under. these conditions as long as the surveillances are completed within specified time requirements.
The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit. The set~oint is considered to be adjusted consistent with the nominal value when the 'as measured" setpoint is within the band allowed for, calibration accuracy.
To accommodate the instrument drift that may occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Setpoints have been specified in Table 3.3-3. Opera-tion with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accomaodate this error. If no value is listed in the Allowable column, the Setpoint value is the limiting setting.
For some functions, an optional provision has been included fol determining the OPERABILITY of a channel when its trip setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncer-tainties of the'instrumentation to measure the process variable and the +uncer tainties in calibrating the instrumentation. In Equation 2.2-1, Z + R S "as g TA, the interactive effects of the errors in the rack and the sensor, and the measured" TURKEY POINT - UNITS 3 8L 4 B 3/4 3-1 AMENDMENT NOS. 140AND 135
r
'1 P
4'
i'?
~
INSTRUMENTATION
~
'a BASFS REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Cont nued values of the errors are considered. I, as specified in Table 3.3-3, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of their measurement. TA or Total Allowance is the difference, in percent span, between the trip setpoint and the value used in the analysis for actuation. R or Rack Error is the "as measured" deviation, in percent span, for the affected channel from the specified trip setpoint. S or Sensor Drift is either the "as measured" deviation of the sensor from its calibration point or the value speci-fied in Table 3.3-3, in percent span, from the analysis assumptions. Use 2.2-1 allows for a sensor drift factor, an increased rack drift factor,of'"-'quation and provides a threshold value for REPORTABLE EVENTS.
The methodology to derive the Trip Setpoints includes an allowance for instrument uncertainties. Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and rack instrumenta-tion utilized in these channels are expected to be capable of operating within the allowances- of. these. uncertainty magnitudes..
Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance. Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents events, and transients. Once the required logic combination is completed, the system sends actuation signals to TURKEY POINT - UNITS 3 4 4 B 3/4 3-la AMENDMENT NOS3,40 AND 135
L I 4