ML020640284
| ML020640284 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/26/2002 |
| From: | Chandu Patel NRC/NRR/DLPM/LPD2 |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| TAC MB2727, TAC MB2728 | |
| Download: ML020640284 (4) | |
Text
TABLE OF CONTENTS (continued) 3.7 PLANT SYSTEMS.................................................................................
3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs)..............................................
3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs).............................................
3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs),
Main Feedwater Control Valves (MFCVs),
Associated Bypass and Tempering Valves...............................
3.7.3-1 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs).............................................................................
3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System................................................
3.7.5-1 3.7.6 Condensate Storage System (CSS)...............................................
3.7.6-1 3.7.7 Component Cooling Water (CCW) System.....................................
3.7.7-1 3.7.8 Nuclear Service Water System (NSWS).........................................
3.7.8-1 3.7.9 Standby Nuclear Service Water Pond (SNSW P)............................
3.7.9-1 3.7.10 Control Room Area Ventilation System (CRAVS)........................... 3.7.10-1 3.7.11 Control Room Area Chilled Water System (CRACWS)................... 3.7.11-1 3.7.12 Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)....................................................................
3.7.12-1 3.7.13 Fuel Handling Ventilation Exhaust System (FHVES)...................... 3.7.13-1 3.7.14 Spent Fuel Pool Water Level..........................................................
3.7.14-1 3.7.15 Spent Fuel Pool Boron Concentration............................................
3.7.15-1 3.7.16 Spent Fuel Assembly Storage........................................................
3.7.16-1 3.7.17 Secondary Specific Activity.............................................................
3.7.17-1 3.8 ELECTRICAL POW ER SYSTEMS.........................................................
3.8.1-1 3.8.1 AC Sources-Operating................................................................
3.8.1-1 3.8.2 AC Sources-Shutdown................................................................
3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.......................................
3.8.3-1 3.8.4 DC Sources-Operating................................................................
3.8.4-1 3.8.5 DC Sources-Shutdown...............................................................
3.8.5-1 3.8.6 Battery Cell Parameters.................................................................
3.8.6-1 3.8.7 Inverters-- Operating.....................................................................
3.8.7-1 3.8.8 Inverters-Shutdown.....................................................................
3.8.8-1 3.8.9 Distribution Systems-Operating..................................................
3.8.9-1 3.8.10 Distribution Systems-Shutdown..................................................
3.8.10-1 3.9 REFUELING OPERATIONS..................................................................
3.9.1-1 3.9.1 Boron Concentration.......................................................................
3.9.1-1 3.9.2 Nuclear Instrumentation.................................................................
3.9.2-1 3.9.3 Containment Penetrations..............................................................
3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation -- High Water Level.................................................
3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -
Low Water Level.................................................
3.9.5-1 3.9.6 Refueling Cavity Water Level.........................................................
3.9.6-1 Amendment Nos. 195/188 Catawba Units 1 and 2 iii
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)
Reactor Trip System Instrumentation Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 4.3% (Unit 1) and 4.5% (Unit 2) of RTP.
AT (I+ Ts)
- 1) 1
<_ AT, K, -K2 (I+1-s)
T 1
-Tr
+ K3(P -P') - f,(A/)
01+
Z_2 S
(
1 s)
I (1+
s)
Where:
AT is the measured RCS AT by loop narrow range RTDs, °F.
AT0 is the indicated AT at RTP, °F.
s is the Laplace transform operator, sec-'.
T is the measured RCS average temperature, OF.
T' is the nominal Tavg at RTP (allowed by Safety Analysis), < 585.1'F (Unit 1)
< 590.80F (Unit 2).
P is the measured pressurizer pressure, psig P is the nominal RCS operating pressure, = 2235 psig K1
=
Overtemperature AT reactor NOMINAL TRIP SETPOINT, as presented in the COLR, K2
= Overtemperature AT reactor trip heatup setpoint penalty coefficient, as presented in the COLR, K3
= Overtemperature AT reactor trip depressurization setpoint penalty coefficient, as presented in the COLR, T1, Tr2
= Time constants utilized in the lead-lag compensator for AT, as presented in the COLR, "13
=
Time constant utilized in the lag compensator for AT, as presented in the
- COLR, "14, T5
=
Time constants utilized in the lead-lag compensator for Tavg, as presented in the COLR, 16
=
Time constant utilized in the measured Tavg lag compensator, as presented in the COLR, and fl(AI)
= 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:
(i) for qt - qb between the "positive" and "negative" fl(Al) breakpoints as presented in the COLR; fl(AI) = 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; (ii) for each percent Al that the magnitude of qt - qb is more negative than the f1(AI) "negative" breakpoint presented in the COLR, the AT Trip Setpoint shall be automatically reduced by the fl(AI) "negative" slope presented in the COLR; and (continued)
Amendment Nos. 195/188 Catawba Units 1 and 2 3.3.1-18
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)
Reactor Trip System Instrumentation (iii) for each percent Al that the magnitude of qt - qb is more positive than the fl(AI) "positive" breakpoint presented in the COLR, the AT Trip Setpoint shall be automatically reduced by the f1(Al) "positive" slope presented in the COLR.
Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 2.6% (Unit 1) and 3.1% (Unit 2) of RTP.
AT (l+1-1 S)
< ATO K 4
-K 5
T7S T-K 6 T Tf]-f 2 (AI)}
Z-S+
-7 S 1+
s T -C6 S
1+
-f-6 Where:
AT is the measured RCS AT by loop narrow range RTDs, OF.
ATo is the indicated AT at RTP, °F.
s is the Laplace transform operator, sec1.
T is the measured RCS average temperature, °F.
T" is the nominal Ta 8 g at RTP (calibration temperature for AT instrumentation),
< 585.1OF (Unit 1) < 590.8 0F (Unit 2).
K4
=
Overpower AT reactor NOMINAL TRIP SETPOINT as presented in the
- COLR, K5
=
0.02/°F for increasing average temperature and 0 for decreasing average temperature, K6
=
Overpower AT reactor trip heatup setpoint penalty coefficient as presented in the COLRforT > T and 1K6 = OforT <T,
' 1, 'r2
=
Time constants utilized in the lead-lag compensator for AT, as presented in the COLR, T 3
=
Time constant utilized in the lag compensator for AT, as presented in the
- COLR, "r6
=
Time constant utilized in the measured Tavg lag compensator, as presented in the COLR, "T7
=
Time constant utilized in the rate-lag controller for Tavg, as presented in the COLR, and f2(AI)
=
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:
(i) for qt - qb between the "positive" and "negative" f2(AI) breakpoints as presented in the COLR; f2(Al) = 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; (continued)
Amendment Nos. 195/188 3.3.1-19 Catawba Units 1 and 2
RTS Instrumentation B 3.3.1 BASES APPLICABLE SAFETY ANALYSES, LCO, AND APPLICABILITY (continued) against positive reactivity additions or power excursions in MODE 3, 4, 5, or 6.
- 3.
Power Range Neutron Flux - High Positive Rate The Power Range Neutron Flux-High Positive Rate trip uses the same channels as discussed for Function 2 above.
The Power Range Neutron Flux-High Positive Rate trip Function ensures that protection is provided against rapid increases in neutron flux that are characteristic of an RCCA drive rod housing rupture and the accompanying ejection of the RCCA. This Function compliments the Power Range Neutron Flux-High and Low Setpoint trip Functions to ensure that the criteria are met for a rod ejection from the power range.
The LCO requires all four of the Power Range Neutron Flux-High Positive Rate channels to be OPERABLE.
In MODE 1 or 2, when there is a potential to add a large amount of positive reactivity from a rod ejection accident (REA), the Power Range Neutron Flux-High Positive Rate trip must be OPERABLE.
In MODE 3, 4, 5, or 6, the Power Range Neutron Flux-High Positive Rate trip Function does not have to be OPERABLE because other RTS trip Functions and administrative controls will provide protection against positive reactivity additions. In MODE 6, no rods are withdrawn and the SDM is increased during refueling operations. The reactor vessel head is also removed or the closure bolts are detensioned preventing any pressure buildup. In addition, the NIS power range detectors cannot detect neutron levels present in this mode.
- 4.
Intermediate Range Neutron Flux The Intermediate Range Neutron Flux trip Function ensures that protection is provided against an uncontrolled RCCA bank rod withdrawal accident from a subcritical condition during startup.
This trip Function provides redundant protection to the Power Catawba Units 1 and 2 B 3.3.1 -10 Revision No. 1