ML20012D594
| ML20012D594 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/21/1990 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20012D588 | List: |
| References | |
| NUDOCS 9003280110 | |
| Download: ML20012D594 (5) | |
Text
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Attachment B to 4
LCA 195 l
Page 1 of 5 l
OEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.22 The REACTOR TRIP SYSTD1 RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until los,s of stationary gripper coil voltage.
i ENGINEERED SAFETY FEATURE RESPONSE TIME 1.23 The ENGINEERED SAFETY FEATURE RESPCNSE TIME shall be that time I
interval from when the monitored parameter exteeds its ESF actuation setpoint at the channel sensor until the E3F equipment is capable of perfoming its safety function (i.e., the valves travel to their re-quired positions, pump discharge pressures reach their requir:d values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
AX!Al FLUX O!FFERENCE 1.24 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux
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detector.
signals between the top and bottom halves of a two section excore neutron PHYSICS TESTS 1.25 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear c tragtetittjes_of_the.. reactor _ cortand_related instrumentation and3 described _in_Chaptgr_14.0 o authorized under the provisions of 10 CFR 50.59,_o,f he FSAR, 2) 4 herwise approved by the Coenission.
I - AVERAGE O!SINTEGRATION ENERGY 1.26 Y shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and ganma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-todine activity in the coolant.
I TROJAN-UNIT 1 1-5 9003280110 900321 PDR ADOCK 05000344 p
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Attachment B to LCA 195 Page 2 of 5 j
3 5.0 OCSIGNFEATURQ 5.1 $!TE i
EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.
LOW POPUt.ATION 20NE 5.1.2 The low population zene shall be as shown in Figure 5.1-2.
FLOOD CONTROL The flood control pro' visions (dikes, leveesijstc.) shall be 5.1.3 designed and maintained in accordance with tW6Figinal design pro-visions contained in Section 2.4.2.2 of the FSAR. ~ 4 t
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i 5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel Ifned, reinferced concrete building of cylindrical shape, with a dome rocf and having the following design features:
a.
Nominal inside diameter = 124 feet.
b.
Nominal inside height = 141 feet, c.
Minimum thickness of concrete walls = 42 inches.
1 d.
Minimum thickness of concrete roof = 30 inches.
l-e.
Minimum thickness of concrete f1cer pad = 72 inches.
f.
Ncminal thickness of steel liner = 0.25 inches.
6 g.
Net free volume = 2x10 cubic feet.
k TROJAN-UNIT 1 5-1
l Attachment B to LCA 195 4
Page 3 of 5 DESIGN FEATURES DESIGN PRES $URE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 60 psig and a temperature of 280'F.
PENETRATIONS 5.2.3 Penetrations through the reactor contaiM& building are designed and shall be maintained in accordance with theftiginal> design provisions contained in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4, except that limited A
substitutions of fuel rods by filler rods consisting of Zircaloy-4 or g
stainless steel, or by vacancies, may be made as justified by cycle-specific reload safety analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235. Reload f uel shall be similar in
- physical design to the initial core loading and of low enrichment.
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[0NTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 90 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.
Eight part length control rod assemblies originally installed in the core contained a nominal 36 inches of absorber material at their lower ends. The part length control rod assemblies have been removed and are stored in the spent fuel pool.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
TROJAN-UNIT 1 5-4 Amendment No. 70, 776, 757 W Iy T4 3 989 m
i 0
Attachment B to LCA 195 1
Page 4 of 5 DE514N FEATURf5 a.
In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
YOLUME
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5.4.2 The total water and steam volume of the Reactor Coolant System is 12,900 1 100 cubic feet at a nominal Tavg n' 584.7'F.
5.5 EMERGENCY CORE COOLING SYSTEMI 5.5.1 The emergency cor: cooling systems re decigned and shall be maintained in accordance with theCprigin esign provisions contained in Section 6.3 of the FSAR with alliWant for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY
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- 5. 6.1.1 The fuel storage racks for new fuel are designed and shall be maintained with a nominal 21-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Kerr of 10.95 with the storage pit filled with unborated water, and with new fuel containing l
not more than 57.0 grams of U-235 per axial centimeter of active fuel
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assembly (4.5 wt5 enrichment).
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5.6.1.2 The storage racks for spent fuel are designed and shall be main-tained with a nominal 10.5-inch center-to-center distance between fuel i
assemblies placed in the storage racks to ensure a Keft of 50.95 with i
the storage pool filled with unborated water and with new fuel centaining (l[M not more than 57.0 grams of U-235 per axial centimeter of active fuel assembly (4.5 wt5 enrichment). The criticality analysis includes a con-servative allowance for uncertainties as described in Section 3.1 of j
PGE-1037.
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TROJAN-UNil 1 5-5 Amendment 30. Pf 3d, 88. 770
- q rch 17, 19893
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Attachment B to
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v' e
LCA 195 Page 5 of 5 DESIGN FEATURES
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DRAINAGE-5.6.2 The spent fuel storage pool is designed and shall be maintained with siphon breakers in the piping extending into the pool which prevent inadvertent draining of the pool below elevation 83'11".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a
-storage capacity limited to no more than 1408 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 1
6.7.1 Those structures, systems and components identified as Category I items in Section 3.2.1 of the FSAR shall be designed and maintained to the(originalP design provisions contained in Section 3.7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements except for the Control Building Complex which is subject to Specifications 5.7.2.1 and 5.7.2.2.
5.7.2.1 The Control-Auxiliary-Fuel Building Complex (Complex) shall be designed and maintained to the design _proYis19ns contained in Sections 3.7 and3.8oftheFSARC(jLamended_tEougLAmendmentNo.T47With= allowance for normal degradation pursuant to the appilcaMe Surveillance Requirements.
5.7.2.2 No modifications which will result in a net:
(a) 3 percent increase in lateral shear forces on any story of the Complex; (b) 1 percent decrease in lateral shear resistance of any story of the Complex; (c) 5 percent increase in combined interstructure displacements i
between the Contro! and Turbine Buildings; or (d) 5 percent reduction in clear space between the Turbine and Control Buildings l
l shall be performed without prior approval of the Director of Nuclear Reactor 1
Regulation. An increase in equipment weight not to exceed 10 percent on a per story, per building basis is permissible and excluded from consideNtion under this specification, l
l-TROJAN-UNIT 1 5-6 Amendment No. 16, 3#, #7, 67, 88 MI
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l J une-20,-1989-u