ML20028F612
| ML20028F612 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/14/1982 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20028F609 | List: |
| References | |
| NUDOCS 8302020310 | |
| Download: ML20028F612 (16) | |
Text
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4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES Figure 2.1 Core Protection Safety Limit, Pressure vs. Temperature 2.1-2 Core Protection Safety Limits, Reactor Power Imbalance 2.1-3 Core Protective Safety Bases 2.3-1 Protective System Maximum Allowable Setpoints, Pressure vs.
Temperature 2.3-2 Protective System Maximum Allowable Setpoints, Reactor Power imbalance 3.1.2-1 Reactor Coolant System Pressure-Temperature -Limi ts for Heatup for the First 5 EFPY 3.1.2-2 Reactor Coolant System Pressure-Temperature Limi ts for Cooldown for the First 5 EFPY 3.1.2-3 Inservice Leak and Hydrostatic Test (5 EFPY) Heatup and Cool-down 3.1.2-4 Reactor Coolant System, Emergency / Faulted Condition--Cooldown Limitations, Applicable for 5 EFPY 3.1.9-1 Limiting Pressure vs. Temperature for Control Rod Drive Operation 3 5.2-1 Rod index vs. Power Level for Four-Pump Operation, O to 60 EFPD 3 5.2-2 Rod index vs. Power Level for Four-Pump Operation, 50 to 305 EFPD 3.5.2-3 Rod ;ndex vs. Power Level for Four-Pump Operation, after 305 EFPD 3 5.2-4 hod Index vs. Power Level for Three-Puinp Operation, O to 60 EFPD 3.5.2-5 Rod Index vs. Power Level for Three-Pump Operation, 50 to 305 EFPD 3.5 2-6 Rod Index ys. Power Level for Three-Pump Operation, af ter 305 EFPD 88 3.5.2-9 Core Imbalance vs. Power Level, O to 60 EFPD 3.5.2-10 Core Imbalance vs. Power Level, 50 to 305 EFPD 3.5.2-11 Core imbalance vs. Power Level, af ter 305 EFPD 8302020310 821214 PDR ADOCK 05000312 ix p
g..
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES (Continued)
Figure 3 5.2-12 LOCA Limited Maximum Allowable Linear Heat Rate 35.4-1 incore Instrumentation Specification Axial imbalance Indication 3.5.4-2 incore instrumentation Specification Radial Flux Tilt Indication 3.5.4-3 incore instrumentation Specification 4.13-1 Main Steam inservice inspection 4.13-2 Main Feedwater Inservice Inspection 4.13-3 Main Steam Dump Inservice inspection 6.2-1 SMUD Organization Chart 6.2-2 Plant Organization. Chart x
RANCHO SECO' C;!T 1
=
TECHNICAL SPECIFICATIONS i
Limiting Conditions for Operation a
3.5.2.
Control Rod Croup and Power Distribution Li=its Appl'ic ab il ity This specification applies to power distribution and operation of control rods during power operation.
Objective To assure an acceptable core power distribution during power operation, to set a limit on potential reactivity insertion from a hypothetical control rod ejec--
tion, and to assure core suberiticality af ter a reactor trip.
Specification 3.5.2.1.
The available shutdown margin shall be not less than 1% ak/k'with the highest wo'rth control rod fully withdrawn.
If the shutdown margin is less than 1%.ak/k then, within one hour, initiate and continue bora-tion until the required shutdown margin is established.
3.5.2.2.
Operation with inoperable rods:
A.
Operation with more than one inoperable rod as defined in Speci-fication 4.7.1 and 4.7.2.3 in the safety or regulating rod banks shall not be permitted.
B.
If a control rod in the regulating and/or safety rod banks is declared inoperable in the withdrawn' position as defined in-Spec-ification paragraph 4.7.1.1 and 4.7.1.3, an. evaluation shall be initiated immediately to verify the existence of 1" ak/k hot l
Boration may be initiated to increase the avail-able rod worth either to compensate for the worth of the inoper-able rod or until the regulating banks are fully withdrawn, whichever occurs first.
C.
If within one hour of determination of an inoperable rod as de-
)
fined in ' Specification 4.7.1, it is not determined that a 1%
ak/k' hot shutdown margin exists combining the worth of the in-operable rod with each of the other rods, the reactor shall be brought to the hot standby condition until this margin is estab-lished.
D.
Following the determination of an inoperable rod as defined in Specification 4.7.1, all rods shall be exercised by a movement until indication is noted but not exceeding 2 inches within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and exercised weekly until the rod problem is solved.
E.
If a control rod in the regulating or safety rod groups is de-clared inoperable per 4.7.1.2, power shall be reduced to 60% of the thermal power allowable for the reactor coolant pump combination.
PROPOSED AMENDMENT NO. 88 3-31
=
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation E.
Whenever the reactor is brought to hot shutdown pursuant to 3.5.2.4.D above, subsequent reactor operation is permitted for the purpose of mea-surement, testing, and corrective action provided the thermal power and power range high flux setpoint allowable for the reactor coolant pump combination are restricted by a reduction of 2% of maximum allowable power for each 1% tilt, or fraction thereof, for the maximum tilt observed prior to shutdown.
F.
The quadrant power tilt shall be determined to be within the limits at least once every shif t during operation above 15% of rated thermal power except when the quadrant power tilt alarm is inoperable, then the quadrant power tilt shall be calculated and evaluated at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3.5.2.5.
Control Rod Positions A.
Technical Specification 3.1.3.5 (safety rod withdrawal) does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
B.
Operating rod group overlap shall be 25% 15% between three sequential groups, except for physics tests.
C.
Position limits are specified for regulating control rods.
Excep.t for phy-sics tests or exercising-control reds, the regulating control rod -insertion /
withdrawal limits are specified on ?igures 3.5.2-1 through 3.5.2-6. If any of these control rod position limits are exceeded, such that control rod posi-tions are in the restricted region, an acceptable control rod position shall be obtained within two hours.
If control rod positions exceed the shutdown cargin limit, such that control rods are in the region defined as operatica not allowed then, within one hour, initiate and continue boration until the required shutdown margin is achieved.
D.
Except for physics test, power shall not be increased above the power level cutoff of 92% of the maximum allowable power level unless one of the following conditions is satisfied:
1.
Xenon reactivity is within 10% of the equilibrium value for opera-tion at the maximum allowable power level and asymptotically ap-proaching stability.
2.
Except for xenon-free startup, when 3.5.2.5.D(1) applies, the re-actor has operated within a range of 87 to 92% of the maximum allow-able power for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the soluble poison con-trol mode.
PROPOSED AMENDMENT NO. 88 3-33
=
RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Design Features 5.3.
Reactor Specification 5.3.1.
Reactor Core 5.3.1.1.
The reactor core contains slightly enriched uranium dioxide pellets.
The pellets are encapsulated in zircaloy-4 tubing to form fuel rods.
The reactor core is made up of 177 fuel assemblies. Each fuel as-sembly contains 208 fuel rods.1,2 5.3.1.2.
The reactor core shall approximate a right circular cylinder with an equivalent diameter of 128.9 inches and a nominal active height of 144 inches. 2 5.3.1.3.
The maximum enrichment of the core for Rancho Seco is a nominal 3.5 weight percent of Uzss, 5.3.1.4.
There are 61 full-length control rod assemblies (CRA) and 8 axial power shaping rod assemblies (APSR) distributed in the reactor core as shown in FSAR Figure 3.2-45.
The full-length CRA contain a 134 inch length of silver-indium-cadmium alloy clad with stainless steel.
The APSR contain inconel clad with stainless steel.3 5.3.1.5.
The core may utilize burnable poison assemblies with similar dimen-sions as the full-length control rods.
5.3.1.6.
Reload fuel assemblies and rods shall conform to design and evalua-tion described in the USAR.
5.3.2.
Reactor Coolant System 5.3.2.1.
The reactor coolant system shall be designed and constructed in ac-cordance with code requirements."
5.3.2.2.
The reactor coolant system and any connected auxiliary systems ex-posed to the reactor coolant conditions of temperature and pressure, shall be designed for a p: essure of 2,500 psig and a temperature of 650*F.
The pressurizer and pressurizer surge line shall be designed for a temperature of 670*F.s l
5.3.2.3.
The reactor coolant system volume shall be less than 17,200 cubic feet.
PROPOSED AMENDMENT NO. 88 5-4
FIGURE 2.1-2 Cote Protection Safety Limits, Reactor Power Imbalance, Cycle 6 THERMAL POWER LEVEL ',
- 120 W.44,ll2)
(.35.84.112) 112 ACCEPTABLE
- 110 CURVE 1 4 PUMP OPERAT.ON
- 100
(-47.39.92.84)
(45.57,91.54)
( 35.84.88.65) 88.65
- 5d (41.44.88.65)
ACCEPTABLE CURVE 2 4 & 3 PUMP 80 OPERATION
(-47.39,69.49) 70 (45.57,68.19)
( 35.84,61.51) 61 51 (41.44.61.51)
- 60 m3 ACCEPTABLE 4.3 & 2 PUMP OPERATION
- pq
(-47.39.42.35)
- AO (45.57,41.05)
- 30 i
UNACCEPTABLE UNACCEPTABLE
- 20 OPERATION OPERATION
- 10 I
t f
f I
I I
t 1
I f
f 60 50 40 30 20 10 0
10 20 30 40 50 60 Reactor Power Imaalance, 5 l
CURVE REACTOR COOLANT DESIGN FLOW, gpm 1
387,600 2
288,374 3
187.986 FR0 POSED AMENDMENT NC. 88 1
$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT
FIGGE 2.3-2 Protective System Maximum Allowable Setpoints, Reactor Power Imbalance, Cycle 6 THERMAL POWER LEVEL, ",
- 120
~Il
(-18,106) 106 (18,106) 2 ACCEPTABLE -100 Mi = 1. 452 0@e 4 PUMP OPERATION
- 90
(-33.5,83.5)
( -18, 7 8. 8-)
78.8
- 80 (18 78 8)
~ (32,82,2)
ACCEPTABLE
- 70 NWW UNACCEPTABLE 4l OPERATION
- l l
l0PERATION-60
( -33. 5,56. 3 )
(32,55)
( - 18,51. 4) 51.4 (18, 51. 4-)
50 I
ACCEPTABLE 4,3&2
- 40 9
l l PUMP e$
OPERATION - 30 l
(-33.5,28.9) l (32,22.6) l
- 20 s I e l
=
=
N
- 10 i
H n
n l
E i
- i E
I i
i 1
i i
i li il i
-60
-50 40
-30
-20
-10 0
10 20 30 40 50 60 Reactor Power imoalance, 5 CURVE RC DESIGN FLOW, gpm 1
387,600 2
288,374 3
187,986 PROPOSED AMENDMENT NO. 88 f$SMUD SACRAMENTO MUNICIPAL UTILITY D' STRICT
FIGURE 3.5.2-1 Rod Index Vs Power Level for Four-Pump Operation, 0-60 EFPD,
Cycle 6
=
110 (124,102)
(283.102) 100 (278,92) 90 OPERATION (270,80) 80 NOT ALLOWE0 RESTRICTED 70 SHUTDOWN MARGIN LIMIT 60 m
C (226,50) 50 (77,50)
C op 40 OPERATION 1.
ALLOWED 5
30 e
20 - (41,15) 10 (0.7.4) 0 i
i i
i 0
20 40 60 80 100 120 140 160 180 200 220 240' 260 '280 300 Rao inaex I
f n
i f
f I
a b
25 50 75 10 0
25 50 75 100 BANK 5 BANK 7 0
25 50 75 100 BANK 6 l
1 l
l l
l PROPOSED AMENDMENT NO. 88
$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT
FIGURE 3.5.2-2 Rod Index Vs Power Level for Four-Fump Operation, 50 to 305 EFPDs, Cycle 6 110 100 (223,102)
(283,102)
(2'io,92) i 90 OPERATION NOT ALLOWED (270,80) g 80
- 2 70 SHUTDOWN RESTRICTED m
k MARGIN LIMIT -
60
%o (157,50)
(226,50) 50 b!
40 c.
OPERATION ALLOWED 30 20 10 0,, 4. 4 }
0 0
20 40 60 80 100 120 140 160 160 200 220 240 280 280 300 Roa Index i
i 0
25 50 75 160 0
25 50 75 100 BANK 7 BANK 5 O
25 50 75 10'0 1
BANK 6 I
PROPOSED AMENDMENT NO. 88
$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT
FIGURE 3.5.2-3 Rod Index Vs Power Level for Four-Pump Operation After 305 EFPD, Cycle 6 a
110 (274,102)
(231.102) 100 OPERATION (270,92) go NOT ALLOWE0 SHUTDOWN (270,80) 80 MARGIN g
[
70 (158,50) 8 (226,50)
{
40 OPERATION ALLOWED 30 20 (81,15) 10 (0,,4.4),
0 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Roa Index 8
I I
a n
m 0
25 50 75 100 0
25 50 75 100 BANK 7 BANK 5 e
0 25 50 75 100 BANK 6 PROPOSED AMENDMENT N0. 88
$SMUD---
FIGURE 3.5.2-4 Rod Index Vs Power Level for Three-Pump Operation, O to 60 EFPD, Cycle 6 m
110 100 S0 E
80 s
SHUTDOWN
[
/
N 70 MARGIN
/
S LIMIT OPERATION 60 o
NOT ALLOWED 50 RESThlCTED (226,50) g
[
(77,38) 40 OPERATION ALLOWED 30 20 - (47,16)
(41,11.75) 10 (0,6.05) 0 0
20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Rod Index i
0 25 50 75 100 0
25 50 75 180 BANK 5 BANK 7 0
25 50 75 160 BANK 6 PROPOSED AMEN 0 MENT NO. 88
$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT
FIGURE 3.5.2-5 Rod Index Vs Power Level for Three-Pump Operation 50 to 305 EFPDs, Cycle 6.
110 100 90 (265,77) 5 80 (223,77) 2 OPERATION
{
70 NOT ALLOWED SHUTDOWN MARGIN LIMIT g
60 ESTRICTE (226,50) 50 g
40 (157,38)
OPERATION ALLOWED 30
( 23,25) 20 10 - (0,3. 73)
(88.11.75) 0 i
i i
i i
i e
0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Roa Index e
i i
I a
t i
g 3
l' 0 0
25 50 75 10'0 0
0 25 50 75 BANK 7 BANK 5 0
25 50 75 100 BANK 6 PROPOSED AMENDMENT NO. 88
$SMUD PA%~E@fii@ M-ONICIPAL UTILITY DISTRICT
i l
FIGURE 3.5.2-6 Rod Index Vs Power Level for Three-Pump Operation After 305 EFPD, Cycle 6 110 1 00 90 (265.6,77)
(231,77) 5 80 2
f 70 OPERATION NOT ALLOWE0 gg g1CTED 60 SHUTDOWN MARGIN b'
50 LIMIT (226,50) 40 (158,38) 30 OPERATION ALLOWED 20 10. (0,3.8)
(81,11 )
0 0
20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Roa Index 0
25 50 75 100 0
25 50 75 l00 BANK 7 BANK 5 i
0 25 50 75 100 BANK 6 PROPOSED AMENDMENT NO. 88 esuuo SACRAMENTO MUNICIPAL UTILITY DISTRICT
O FIGURE 3.5.2-9 Core Imbalance Vs Power Level, 0-60 EFPD, Cycle 6
~
11 0 RESTRICTED (II 102)
REGION
(-10,102 ) r 100 90 (19,92 )
(-22,80)
(22,80) 80 5
PERiflSSIBLE 2
70 E
OPERATING 2
60 REGION O
o@
g' 50
(-33,50)
(33,50) a.
40 30 20 10 0
I I
I I
I I
I I
I
-50 40
-30
-20
-10 0
10 20 30 40 50 Core Imaalance, ",
r PROPOSED AMENDMENT NO. 88 l
$SMU SACRAMENTO MUNICIPAL UTILITY DISTRICT l
a FIGURE 3.5 2-10 Core Imbalance Vs Power Level Af ter 50 to 305 EFPD,
=
Cycle 6 110 -
(-15,102)
(20,102) 100 -
RESTRICTED REGION
(-15,92)
(20,92)
(-27,80)
(23,80) 80 E[E PERillSSIBl.E OPERATING 70 g
S REGION o
60 e
( 41, 50)
(41,50 )
D 50 5c.
40 30 20 10 0
-50
-40
-30 20
-10 0
10 20 30 40 50 Core Imoalance, ",
PROPOSED M1ENDMENT N0. 88 esuuo SACRAMENTO MUNICIPAL UTILITY DISTRICT l
o
~
FIGURI 3.5.2-11 Core Imbalance Vs Power Level After 305 EFPD, Cycle 6 11 0 -
(-15,102)
(20,102) 00 RESTRICTED (20,92)
(-15,92) 90
(-24,80)
PERMISSIBLE (23,80) 80 5
OPERATING 1
REGION 70
~
C E
60
(-41,50)
(41,50) 50 E
40 30 i
20 l
10 0
-50
-40
-30
-20
-10 0
10 20 30 40 60 Care imoalance, %
PROPOSED AMENDMENT NO. 88 l
9 suu1-SA@RAMENTO MUNICIPAL UTILITY DISTRICT
'