ML20085L686
| ML20085L686 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 06/14/1995 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20085L689 | List: |
| References | |
| NUDOCS 9506280607 | |
| Download: ML20085L686 (26) | |
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UNITED STATES -
NUCLEA74 GEGULATORY COMMISSION l
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WASHINGTON, D.C. enana anni COPMONWEALTH EDISON COMPANY DOCKET N0. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.-135-License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company
'(the licensee) dated December 15, 1993, as supplemented April 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the' Commission's-rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of-the Commission; i
C.
There is reasonable assurance (1) that the activities authorized.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be
.)
conducted in compliance with the Commission's regulations;:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
]
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable l
requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and 1
I paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:
9506290607 950614 PDR ADOCK 05000237 P
)
. 2-(2)
Technical Specifications The. Technical Specifications centained in Appendix A, as revised through Amendment No.135, are hereby incorporated in the L
license. The licensee shall operate: the. facility. in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented no later than December 31, 1995.
.i FOR THE NUCLEAR REGULATORY COMMISSION t
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ohn F. Stan V, Senior Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Attachment-Changes to the Technical Specifications Date of Issuance:
June 14, 1995 1
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UNITED STATES g
,g NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. BoeodHmot O
49.....,o COPMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 129 License No. DPR-25 l
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company i
(the licensee) dated December 15, 1993, as supplemented April 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;-
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
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R B.
Technical Specifications The Technical Specif_ications contained in Appendix A, as revised through Amendment-No.129. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and~
shall be implemented no later than December 31, 1995.
FOR THE NUCLEAR REGULATORY COMMISSION B
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s J n F. Stan
. Senior Project Manager i
Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 14, 1995 i
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l ATTACHMENT TO LICENSE AMENDMENT NOS.135 AND 129 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number.
UNIT 2 UNIT 3 REMOVE REMOVE INSERT 5-1 5-1 5-1 5-2 5-2 5-2 5-3 5-4 5-5 5-6 5-7 5-8
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SITE 5.1 5.0 DESIGN FEATURES El Ellf flNTENTIONALLY BLANK 1 s
5.1. A
[lNTENTIONALLY BLANK)
P F
Low Pooulation Zone 5.1.B The low population zone shall be as shown in Figure 5'.1.B 1.
Radioactive Gaseous Effluents t
5.1.C Information regarding radioactive gaseous effluents shall be located in the OFFSITE DOSE CALCULATION MANUAL.
Radioactive Liould Effluents 5.1.D information regarding radioactive liquid effluents shall be located in the OFFSITE DOSE CALCULATION MANUAL.
t i
i DRESDEN - UNITS 2 & 3 5-1 Amendment 135, 129
SITE 5.1 FIGURE 5.1. A-1 IINTENTIONALLY BLANK 1 DRESDEN - UNITS 2 & 3 5-2 Amendment 135, 129
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,/ f icm..ius DRESDEN - UNITS 2 & 3 5-3 Amendment 135, 129 ;
t CONTAINMENT 5.2
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5.0 DESIGN FEATURES L2 CONTAINMENT 1
A ConfiguratiDD 5.2.A The primary containment is a steellined concrete structure consisting of a drywell and suppression chamber. The drywellis a steel structure composed of a spherical lower portion, a cylindrical middle portion, and a hemispherical top head. The drywell is attached to the suppression chamber through a series of downcomer vents. The drywell has a minimum free air volume of 158,236 cubic feet. The suppression chamber has an air region of 116,300 to 112,800 cubic feet and a water region of 116,300 to 119,800 cubic feet.
l Design Temoerature and Pressure 5.2.B The primary containment is designed and shall be maintained for:
1.
Maximum internal pressure:
62 psig.
2.
Maximum internal temperature: drywell 281*F.
suppression pool 281*F.
3.
Maximum external pressure:
drywell 2 psig, suppression pool 1 psig.
Secondarv Containment 5.2.C The secondary containment consists of the Reactor Building and a portion of the main steam tunnel and has a minimum free volume of 5,760,000 cubic feet.
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i DRESDEN - UNITS 2 & 3 54 Amendment 135, 129
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REACTOR CORE 5.3 i
5.0 DESIGN FEATURES t
i JL3 REACTOR CORE q
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Fuel Assemblies i
5.3.A 'The reactor core shall contain 724 fuel assemblies. Each assembly consists of a matrix of Zircaloy clad fuel rods with an initial composition of natural or slightly
- enriched uranium dioxide as fuel material and water rods. Limited substitutions of i
zirconium alloy'or stainless steel filler rods for fuel rods, in accordance with NRC-i approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
Control Rod Assemblies I
5.3.B The reactor cora shall contain 177 cruciform shaped control rod assemblies. The control material shall be boron carbide powder (B,C) and/or hafnium metal. The control rod assembly shall have a nominal axial absorber length of.143 inches.
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DRESDEN - UNITS 2 & 3 55 Amendment 135,12 i
.e REACTOR COOLANT SYSTEM 5.4 5.0 DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature 5.4.A The reactor coolant system is designed and shall be maintained:
1.
In accordance with the code requirements specified in Section 5 of the UFSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, 2.
For a pressure and temperature of:
a.
1175 psig at 565 F on the suction side of the recirculation pump.
b.
1450 psig at 575'F from the recirculation pump discharge to the outlet side of the discharge shutoff valve.
c.
1325 psig at 580*F from the discharge shutoff valve to the jet pumps.
Volume 5.4.B The total water and steam volume of the reactor vessel and recirc'ulation system is approximately 14,626 cubic feet at 68'F.
DRESDEN - UNITS 2 & 3 5-6 Amendment 135, 129
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. DESIGN FEATURES.
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- DRESDEN - UNITS 2 & 3 5-7 Amendment 135,12 :
FUEL STORAGE 5.6 5.0 DESIGN FEATURES i
5.6 FUEL STORAGE Criticality 5.6.A The spent fuel storage racks are designed and shall be maintained with:
1.
A k,,, equivalent to 50.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 9.1 of the UFSAR.
2.
A nominal 6.30 inch center-to-center distance between fuel assemblies placed in the storage racks.
i Drainane 5.6.8 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 589' 2.5".
Capacity 5.6.C The spent fuel storage poolis designed and shall be maintained with a storage capacity limited to no more than 3537 fuel assemblies.
l DRESDEN - UNITS 2 & 3 5-8 Amendment 135, 129 j
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,ei UNITED STATES
'j NUCLEAR REGULATORY COMMISSION
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f WASH!NGTON, D.C. 20666 4001 i.
49.....,o COMMONWEALTH EDISON COMPANY AND IQWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 RUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 15, 1993, as supplemented April 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. cf Facility Operating License No. DPR-29 is hereby
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amended to read n, follows:
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i B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as..
revised through Amendment No.'156, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented no later than June 30, 1996.
FOR THE NUCLEAR REGULATORY COMMISSION'
~ >-
f Robert M. Pulsife, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachment-Changes to the Technical Specifications t
Date of Issuance: June 14, 1995 l
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UNITED STATES 3j
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NUCLEAR REGULATORY COMMISSION i
t WASHINGTON. D.C. 20666-0001 o
COMMONWEALTH EDISON COMPANY AtiQ IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 152 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Commission) has found that:
[
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 15, 1993, as supplemented April 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized i
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
j 2.
Accordingly, the license is amended by changes to the Technical Specifications as. indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
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B.
Technical S9acifications y
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.152, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented no later than June 30, 1996.
FOR THE NUCLEAR REGULATORY COMMISSION f
Y
'f Robert M. Pu sifer, oject Manager i
Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 14, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT N05.156 AND 152 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-263 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number.
UNIT 1 UNIT 2 REMOVE REMOVE INSERT 5.0-1 5.0-1 5-1 5.0-2 5-2 5-3 5-4 5-5 5-6 5-7 5-8
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' SITE 5.1
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' 5.0
' DESIGN FEATURES -
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IINTENTIONALLY BLANK 1 5.1.A
[lNTENTIONALLY BLANK)
' Low Poouf ation Zone 5.1.B - The low population zone shall be as shown in Figure 5.1.B 1.
Radioactive Gaseous Effluents
.l 5.1.C Information regarding radioactive gaseous effluents shall be located in the OFFSITE DOSE CALCULATION MANUAL.
Radioactive Liould Effluents 1
F 5.1.D information regarding radioactive liquid effluents shall be located in the OFFSITE DOSE.
-l CALCULATION MANUAL.
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l QUAD CITIES - UNITS 1 & 2 5-1 Amendment 156, 152
SITE 5.1 FIGURE 5.1. A-1 IINTENTIONALLY BLANK 1 t
OUAD CITIES - UNITS 1 & 2 5-2 Amendment 156, 15.
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POPULATION CEN"ER OtSTANCE.7 MILE RADIUS LOW POPULATION ZONE,3 MILE RADIUS QUAD CITIES - UNITS 1 & 2 5-3 Amendment 156, 152,
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'4 CONTAINMENT 5.2 i
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. 5.0 DESIGN FEATURES
~
i L2 CONTAINMENT 1
Confiouration
.j 5.2.A The primary containment is a steellined concrete structure consisting of a drywell and suppression chamber. The drywellis a steel structure composed of a sphericallower portion, a cylindrical middle portion, and a hemispherical top head. The drywell is
. attached to the suppression chamber through a series of downcomer vents. The
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drywell has a minimum free air volume of 158,236 cubic feet. The suppression chamber has an air region of.120,800 to 117,300 cubic feet and a water region of 111,500 to 115,000 cubic feet.
i Desian Temoerature and Pressure 5.2.B The primary containment is designed and shall be maintained for:
1.
Maximum internal pressure:
56 psig.
2.
Maximum internal temperature: drywell 281'F.
suppression pool 281*F.
1 3.
Maximum external pressure:
drywell 2 psig.
suppression pool 1 psig.
I Secondarv Containment 5.2.C The secondary containment consists of the Reactor Building and a portion of the main steam tunnel and has a minimum free volume of 5,760,000 cubic feet.
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OUAD CITIES - UNITS 1 & 2 5-4 Amendment 156, 152 l
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1 REACTOR CORE 5.3 i
5.0 DESIGN FEATURES L3 REACTOR CORE Fuel Assemblies
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5.3.A The reactor core shall contain 724 fuel assemblies, cach assembly consists of a matrix of Zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material and water rods. Limited substitutions of zirconium alloy, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions, i
Control Rod Assgmbhes 5.3.B The reactor core shall contain 177 cruciform shaped control rod assemblies. The control material shall be boron carbide powder 'G,C) and/or hafnium metal. The control rod assembly shall have a nominal axial absorber length of 143 inches.
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QUAD CITIES - UNITS 1 & 2 55 Amendment 156, 152 ;
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4 i
4 g-REACTOR COOLANT SYSTEM 5.4 i
3 5.0 DESIGN FEATURES t
- f 5.4 REACTOR COOLANT SYSTEM i
1 e
Desian Pressure and Temperature l
n 5.4.A The reactor coolant system is designed and sha!! be maintained:
a 1.
In accordance with the code requirements specified in'Section 5 of the UFSAR,.
with allowance for normal degradation pursuant to the applicable Surveillance
- Requirements,
.2.
For a pressure and temperature of:
i i
a.
1175 psig at 565'F on the suction side of the recirculation pump.~
i b.
1450 psig at 575'F from the recirculation pump discharge to the outlet side of '
]
the discharge shutoff valve.
c.
1325 psig at 580*F from the discharge shutoff valve to the jet pumps.
i Volume i
5.4.B ' The total water and steam volume of the reactor vessel and recirculation system is approximately 15,679 cubic feet at 68'F.
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1 QUAD CITIES - UNITS 1 & 2 5-6 Amendment 156, 152 '
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P BLANK, 5.5 i
5.0 DESIGN FEATURES
' 5J flNTENTIONALLY BLANK 1 i
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156,152l OUAD CITIES - UNITS 1 & 2 57 Amendment.
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FUEL STORAGE 5.6 5.0 DESIGN FEATURES 5.6 FUEL STORAGE Criticality 5.6.A The spent fuel storage racks are designed and shall be maintained with:
i.
l I
1.
A k,, equivalent to 50.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 9.1 of the UFSAR.
2.
A nominal 6.22 inch center-to-center distance between fuel assemblies placed in the storage racks.
Drainaae 5.6.B The spent fuel storage poolis designed and shall be maintained to prevent inadvertent draining of the pool below elevation 666' 8.5".
Capacity 5.6.C The spent fuel storage poolis designed and shall be maintained with a storage capacity limited to no more than 3657(Unit 1)/3897(Unit 2) fuel assemblies.
1 I
OUAD CITIES - UNITS 1 & 2 58 Amendment 156, 152 m
. _ _ _ _ _ _ _ _ _ _ _ _ _