ML20141M930
| ML20141M930 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/19/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141M924 | List: |
| References | |
| NUDOCS 8603030064 | |
| Download: ML20141M930 (10) | |
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UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION n
.,I WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated July 12, 1985, supplemented July 26 August 2 and 7,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in c;nformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
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 Comission'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 Comission'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 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
m3SEMBETEP P
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.94, 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.
FOR THE NUCLEAR REGULATORY COMMISSION l'
M's S ven ar, tirector
@P Project Directorate #3 Di ision of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: February 19, 1986 e
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o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION D
rj WASHINCTON, D. C. 20555
,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment nob 4 License No. DPR-48 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated July 12, 1985, supplemented July 26, August 2 and 7, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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, ar:d the rules and regulations of the Comission; 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
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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 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
~ (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.84 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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s Et ven A V rga, Director RWR Project Directorate #3 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: February 19, 1986 h
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
Remove Pages Insert Pages 3 of DPR-39 3 of DPR-39 3 of DPR-48 3 of DPR-48 296 296 298 298 299 299 l
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(5) The licensee may proceed with and is required to complete the modifications indicated in Paragraphs 3.1.1 through-3.1.20 of the NRC's Fire Protection Evaluation (SE) on the Zion Nuclear Power Station dated March 10, 1978 and supplements thereto.
Tnese modifications shall be completed as specified in Table 3.1 of Supplement No.1 or in subsequent supplements to that SE.
In addition, the licensee shall submit the additional information identified in Table 3.2 of the above cited SE in accordance with the schedule contained therein.
In the event these dates for submittal cannot be met, the licensee shall submit a report explaining the circumstances, together with a revised schedule. (added 4-13-79; Am. 48)
(6) Pursuant to the recuirements of 10 CFR 50.3d(c), 10 CFR 50.54(p) and 10 CFR 73.55, as applicable, the licensee shall fully implement and maintain in effect all previsions and changes to the following plans: (revised 1-15-81; Am. 61)
(a)
Zion Station Unit Nos. I and 2 Physical Security Plan, approved March 14, 1979; (b)
Zion Nuclear Power Station Safeguards Contingency Plan, approved November 17, 1980 and to be fully implemented within 30 days; (c)
Zion Nuclear Power Station Guard Training and i
Qualification Plan approved January 15, 1981 and to be fully implemented within 60 days.
(7)
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated April 13,1978, as supplemented October 24, November 8 and 29, 1978, January 24 and 26, February 23, March 7 and March 19, 1979. (revised 1-15-81; Am. 61)
(a)
Fuel stored in the spent fuel pool shall have a U-235 l
loading less than or equal to 46.4 grams per axial centimeter.
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l 0383X Amendment No. 94 and 84 l
DPR-48 '
(5) The licensee may proceed with and is required to complete the modifications indicated in Paragraphs 3.1.1 through 3.1.20 of the NRC's Fire Protection Evaluation (SE) on the Zion Nuclear Power Station dated March 10, 1978 and supplements thereto.
These modifications shall be completed as specified in Table 3.1 of Supplement No. 1 or in subsequent supplements to that SE.
In addition, the licensee shall submit the additional information identified in Table 3.2 of the above cited SE in accordance with the schedule contained therein.
In the event these dates for submittal cannot be met, the licensee shall submit a report explaining the circumstances, together with a revised schedule. (revised 4-13-79; Am. 48)
(6) Pursuant to the requirements of 10 CFR 50.34(c), 10 CFR 50.54(p) and 10 CFR 73.55, as applicable, the licensee shall fully implement and maintain in effect all provisions and changes to the following plans: (revised 1-15-81; Am. 58)
(a)
Zion Station Units Nos. I and 2 Physical Security Plan, approved March 14, 1979; (b)
Zion Nuclear Power Station Safeguards Contingency Plan, approved November 17, 1980 and to be fully implemented within 30 days; (c)
Zion Nuclear Power Station Guard Training and Qualification Plan approved January 15, 1981 and to be fully implemented within 60 days.
(7) Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated April 13, 1978, as supplemented October 24, November 8 and 29, 1978, January 24 and 26, February 23, March 7 and March 19, 1979. (revised 1-15-81; Am. 58)
(a)
Fuel stored in the spent fuel pool shall have a U-235 loading less than or equal to 46.4 grams per axial centimeter.
en en and 84 0383K
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5.0 DESIGN FEATURES
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5.1 Site Zion Units 1 and 2 are located at the Zion Station which The R'eactor Coolant System transfers the heat consists of a tract of land of approximately 250 acres generated in the core to the steam generators located in the extreme eastern portion'of the city of where steam is generated to drive the turbine
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Zion, Lake County, 1111nois, on the west shore of Lake generator.
Michigan approximately 6 miles NNE of the center of the 4
I city of Waukegan, 1111 nots, and 8 miles south of the The Reactor Coolant System provides a boundary center of the city of Kenosha, Wisconsin. It is located for containing the coolant under operating i
at longitude 87* 48.I'W and latitude 42* 26.8'N.
temperature and pressure conditions. It serves to i
confine radioactive material and limits to The minimum distance from the reactor center line to the acceptable values of uncontrolled release to the i
boundary of the exclusion area is 400 meters as shown in secondary system and to other parts of the plant figure 1.2-1 of the Zion FSAR and the low population under conditions of either normal or abnormal zone is one mile as shown in figure 2.2-2 of the Zion reactor behavior. During transient operation, the FSAR, as defined in 10 CFR 100.3.
system's heat capacity attenuates thermal transients generated by the core or steam Reference generator.
i FSAR, Section 2 The reactor coolant system components are designed in accordance with standards set in l
5.2 Reactor Coolant System chapter 5 of the FSAR.
A reactor coolant system consists of four similar 5.3 Reactor Core i
heat transfer loops connected in parallel to the i
reactor vessel. Each loop contains a circulating The reactor is a mult1 region core consisting of 1
pump, two isolation valves and a steam generator.
193 fuel assemblies with 204 Individual fuel rods The system also includes a pressurtzer, connecting sier assembly.
j piping, pressurizer safety and relief valves, and a relief tank.
A total of about.2 million Ibs. of urantum ldioxidewithenrichmentsbetween2.2and3.7 i
weight percent U-235 is contained in cold worked partially annealed Zircalloy tubes.
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Theequivalentcorediameteris132'.iinchesand the active core height is 144 inches and l
generates 3250 MWth-07580/07590 296' Amendment No. 94 ano 84 s
1 The reactor containment structure for Zion Unit 2 l1herearethreesectionsofrackswitheachsection p
essentially identical in design and constru' tion to made up of two rows. The two paraIIe1 rows in each c
that of Unit 1 except that it is reoriented, humerous section have a nominal center to center spacing of 21
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mechanical and electrical systems penetrate the inches and each section is separated by a distance of e
3 containment wall through welded steel 44" to assure a K effective of less than 0.95 even for i
penetrations.(2) a condition of optimum moderation if water was to fill l
the vault, for fuel having a maximum loading of 50.2 i
l5.4.3ContainmentPenetrations gm U-235 per axial centimeter of fuel assembly length l
(about 4.0 weight percent U-235). 1he new fucI storage I
All containment penetrations (both electrical and vault is protected from flooding by,its free flood 1
piping) are double barrier assemblies consisting of a drain.
closed sleeve, in most cases, or a double gasketed
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closure for special penetrations such as the fuel New fuel may also be temporarily stored in the si,ent transfer tube. The space between the double barriers fuel pool in preparation for refueling. The fuel will be continuously pressurized, either by the assemblies are stored in racks in parallel rows, Penetration Pressurization System or Nitrogen System, having a nominal center to center distance of 10.35 to a pressure in excess of the containment design inches in both directions. This spacing 1s sufficient pressure. (*)
to maintain a K effective of less than.95 when
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flooded with unborated water, for fuel having a References maximum loading of 46.4 gms. U-235 per axial centimeter of fuel assembly length (about 3.7 welght (1)
ISAR Section 5.1.1 percent U-235).
ij (2)
ISAR Section 5.1.2 (3)
ISAR Section 5.1.4 5.5.2 Spent Fuel Storage
- 1 5.5 fuel Storage Irradiated fuel assemblies will be stored prior to
- j offsite shipment in the stainless steel lined fuel 1
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I 5.5.1 New fuel Storage pool which is located in the fuel handling building.
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Borated water is used to fill the spent fuel storage p
New fucl assemblies are stored in a separate pit at a concentration to match that used in the
!j storage vault which is designed to hold 132 new reactor cavity and refueling canal during refueling 9
assemblies. The new fuel storage racks operations. The fuel is stored in a vertical array 4
acconrnodate 2/3 of a core, with a nominal center to center spacing of 10.35' l
between assemblies to assure a K effective of less i
I than 0.95 even if unborated water is used to fill the M
l pit, for fuel having a maximum load.ing of 46.4 gms.
L U-235.
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Amendment No. 94 and 84 07500/01590 298
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5.5.2 Spent Fuel Storage (Continued) 5.6 Seismic Design
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s e; per axial centimeter of fuel assembly length (about 1he structures, mechanical components and EngineereJ. M ';.
l 3.7 weight percent U-235).
Saf,eguards Systems vital to safe shutdown and
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containment isolation, or whose f ailure might cause or T" '7 Reference increase the severity of a loss of coolant, accident, are designed per the seismic criteria of Design Dasts Criticality Analysis of Zion Units 1 and 2, fresh and Earthquake (DDE). Design Basis Earthquake is based on Spent Fuel Racks, dated October 25, 1984.
ordinary allowable stresse' as set for' in applicable codes, plus the additional requirement that a safe shutdown be made during a horizorital ground acceleration of 0.179 and a vertical acceleration of 0.11g occurring simultaneously. These systems and equipment are defined as Seismic Class 1.
Other systems and mechanical components in a support or auxiliary function are designed per the seismic criteria of Operational Basis Earthquake (00E), or per applicable codes. These systems and equipment are defined as either Classes 2 or 3 depending on their function.
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l Amendment No. 94 and 84 01500/01590 299 i
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