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{{#Wiki_filter:ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO.50-400/LICENSE NO.NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES INCREASED FUEL ENRICHMENT | {{#Wiki_filter:ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES INCREASED FUEL ENRICHMENT | ||
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I h DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5-2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380'F.5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4, stainless steel, or by vacancies may be made in fuel assemblies if justified by a cycle-specific evaluation. | ~OR nz~ocv, P ~oooooo !l Pat. | ||
Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup.Each fuel rod shall have a nominal active fuel length of 144 inches'he initial core loading shall have a maximum enrichment of 3.5 weight percent U-235.Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.Fuel with enrichments greater than 4.20 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of Specification 5.6.1.a.2 is met.CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 52 shutdown and, control rod assemblies. | |||
The shutdown and rod assemblies shall contain a nominal 142 inches of absorber material.The nominal values of absorber material shall be 80K silver, 15X indium, and 5X cadmium, or 95X hafnium with the remainder zirconium. | I h | ||
All control rods shall be clad with stainless steel tubing.5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained: | DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5-2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380'F. | ||
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.VOLUEE 5 4.2 The total water and steam volume of the Reactor Coolant System is 9410+100 cubic feet at a nominal T of 588 8'5'.SHEARON HARRIS | 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4, stainless steel, or by vacancies may be made in fuel assemblies if justified by a cycle-specific evaluation. Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches'he initial core loading shall have a maximum enrichment of 3.5 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235. Fuel with enrichments greater than 4.20 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of Specification 5.6.1.a.2 is met. | ||
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 52 shutdown and, control rod assemblies. The shutdown and rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80K silver, 15X indium, and 5X cadmium, or 95X hafnium with the remainder zirconium. All control rods shall be clad with stainless steel tubing. | |||
l.A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the PWR storage racks and 6.25 inch center-to-center distance in the BWR storage racks.2.The maximum core geometry K for PWR fuel assemblies less than or equal to 1.470 at 68'F.5.6.l.b The keff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.DRAINAGE 5.6.2 The new and spent fuel storage pools are designed and shall be main-tained to prevent inadvertent draining of the pools below elevation 277.CAPACITY 5.6.3 The new and spent fuel storage pools are designed for a storage capacity of 1832 PWR fuel assemblies and a variable number of PWR and BWR storage spaces in 48 interchangeable 7x7 PWR and llxll BWR racks.These interchangeable racks will be installed as needed.Any combination of BWR and PWR racks may be used.5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.SHEARON HARRIS | 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained: | ||
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. | |||
VOLUEE 5 4.2 The total water and steam volume of the Reactor Coolant System is 9410 + 100 cubic feet at a nominal T of 588 8'5'. | |||
SHEARON HARRIS UNIT 1 5-6 Amendment No. | |||
l~ | |||
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.a The spent fuel storage racks are designed and shall be maintained with a kerf less than or equal to 0.95 when flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3.2.6 of the FSAR. This is assured by maintaining: | |||
: l. A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the PWR storage racks and 6.25 inch center-to-center distance in the BWR storage racks. | |||
: 2. The maximum core geometry K for PWR fuel assemblies less than or equal to 1.470 at 68'F. | |||
5.6.l.b The keff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed. | |||
DRAINAGE 5.6.2 The new and spent fuel storage pools are designed and shall be main-tained to prevent inadvertent draining of the pools below elevation 277. | |||
CAPACITY 5.6.3 The new and spent fuel storage pools are designed for a storage capacity of 1832 PWR fuel assemblies and a variable number of PWR and BWR storage spaces in 48 interchangeable 7x7 PWR and llxll BWR racks. These interchangeable racks will be installed as needed. Any combination of BWR and PWR racks may be used. | |||
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1. | |||
SHEARON HARRIS UNIT 1 5-7 Amendment No.}} | |||
Latest revision as of 21:20, 3 February 2020
| ML18005A914 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/16/1989 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18005A913 | List: |
| References | |
| NUDOCS 8905230077 | |
| Download: ML18005A914 (3) | |
Text
ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES INCREASED FUEL ENRICHMENT
~O>2~OO7y 8~O
~OR nz~ocv, P ~oooooo !l Pat.
I h
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5-2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380'F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4, stainless steel, or by vacancies may be made in fuel assemblies if justified by a cycle-specific evaluation. Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches'he initial core loading shall have a maximum enrichment of 3.5 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235. Fuel with enrichments greater than 4.20 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of Specification 5.6.1.a.2 is met.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 52 shutdown and, control rod assemblies. The shutdown and rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80K silver, 15X indium, and 5X cadmium, or 95X hafnium with the remainder zirconium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
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.
VOLUEE 5 4.2 The total water and steam volume of the Reactor Coolant System is 9410 + 100 cubic feet at a nominal T of 588 8'5'.
SHEARON HARRIS UNIT 1 5-6 Amendment No.
l~
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.a The spent fuel storage racks are designed and shall be maintained with a kerf less than or equal to 0.95 when flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3.2.6 of the FSAR. This is assured by maintaining:
- l. A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the PWR storage racks and 6.25 inch center-to-center distance in the BWR storage racks.
- 2. The maximum core geometry K for PWR fuel assemblies less than or equal to 1.470 at 68'F.
5.6.l.b The keff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The new and spent fuel storage pools are designed and shall be main-tained to prevent inadvertent draining of the pools below elevation 277.
CAPACITY 5.6.3 The new and spent fuel storage pools are designed for a storage capacity of 1832 PWR fuel assemblies and a variable number of PWR and BWR storage spaces in 48 interchangeable 7x7 PWR and llxll BWR racks. These interchangeable racks will be installed as needed. Any combination of BWR and PWR racks may be used.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
SHEARON HARRIS UNIT 1 5-7 Amendment No.