ML20040B383
| ML20040B383 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/21/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040B384 | List: |
| References | |
| NUDOCS 8201250500 | |
| Download: ML20040B383 (10) | |
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NUCLEAR REGULATORY COMMISSION
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BALTIMORE GAS AND' ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLI'FFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The' application for amendment by Baltimore Gas & Electric.
Company (the licensee) dated October 6, 1981, 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; m
7 B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission;
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C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without
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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 arendment
.il not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR
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Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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8201250500 811221 PDR ADOCK 05000317 P
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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-53 is hereby amended to read as follows:
(2) Technical Specifications
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The Techr.ical Specifice+'--e -- **ined in'Appen;! ices A and B, as revised through Amendment Ho. 63, are hereby inccrporated in the license. The licensee shall operate
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the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as-of the date of its issuance.
FOR THE NUCLEAR REGULAT.ORY COMMISSION G/TrWawA oj. Robert A. Clark, Chief 9J Operating Reactors Branch #3 Division of Licensing j
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Attachment:
Changes to the Technical Specifications l
Date of Issuance: December 21, 1981' l
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C ATTACHMEtiT TO LICENSE AMENDMEtiT tJ0. 63 i
i FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the followingpage of the Appendix A Technical Specifications with the enclosed page as indicated.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document complete-ness.
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DESIGN FEATURES l
l VOLUME l
5.4.2 The total water and steam volume of the reactor coolant system is 10,614 460 cubic. feet at a nominal T,yg of 532'F.
5.5 METEOROLOGICAL TOWER LOCATION
- 5. 5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 1
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- 5. 6.1 The spent fuel storage racks are designed and shall be maintained with a minimum 10 3/32" x 10 3/32" center-to-center distance between fuel assemblies
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placed in the storage racks to ensure a k"f,he kequivalent to < 0.95 with the storage pool filled with unborated water. T of < 0.95 includes the conservative allowances for uncertainties descr18[d in Tection,9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 j
weight percent.
CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to-center distance between new fuel assemblies such that k
will ~not exceed 0.98 when fuel having a maximum enrichment of 4.1 weight p$f[ent U-235 is in place and various densities of unborated water are assumed including aqueous foam moderation. The k of < 0.98 includes the conserva-tive allowance for uncertainties describe 8Nn Section 9.7.? of the FSAR.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to l
prevent inadvertent draining of the pool below elevation 63 feet.
CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity,-for both Units 1 and 2, limited to no more than 1760, fuel assemblies.
5.7 COMP'ONENT CYCLIC OR TRANSIENT LIMITS 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.
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l CALVERT CLIFFS - UNIT 1 5-3 Amendment No. 27, 47, 6 3
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NUCLEAR REGULATORY COMMISSION
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER' PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated October 6,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) ahd 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 Commissio'n's regulations and all applicable requirements have been satisfied.
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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) cf racility Operating License No. OPR-69 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications ' contained in Appendices.
j A' and B, as revised through Amendment No. 45, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
j FOR THE NUCLEAR REGULATORY C0tHISSION f
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' Robert A.. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attachmsnt:
Changes to the Technical Specifications j
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l Date of Issuance:
December.21, 1981 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. DPR-69 t
DOCKET NO. 50-318
. Replace the following page of the Appendix A Technical Specifications with.
the enclosed pag'e as indicated. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document complete-ness.
Page 5-5 en e
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DESIGN FEATURES f
0 VOLUME i
5.4.2 'The total water and steam volume of the reactor coolant system is 10,614
+ 460 cubic feet at.a nominal T,yg of 532'F.
5.5 METEOROLOGICAL TOWER LOCATION
- 5. 5.1 The meteorological tower shall be loca,ted as shown on Figure 5.1-1.
i 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL t
5.6.1 The spent fuel storage racks are designed and shall be maintained with a minimum 10 3/32" x 10 3/32" center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,ff equivalent to < 0.95 with the storage pool filled with unborated water.
The k of < 0.95 includes the conservative allowances for uncertainties describ88 in Section 9.7.2 of the FSAR.
The maximum fuel enrichment to be stored in the fuel pool will be 4.1
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weight percent.
CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a i
nominal 18 inch center-to-center distance between new fuel assemblies such that will not exceed 0.98 when fuel having a maximum enrichment of 4.1 weight k, [ent U-235 is in place and various densities of unborated water are assumed i
pe including aqueous foam moderation. The k of < 0.98 includes the conserva-f f
tive allowance for uncertainties describe 8 (n Section 9.7.2 of the FSAR.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feeu.
i CAPACITY 5.6.4 The fuel s'torage pool is designed and shall be maintained with a i
l combined storage capacity, for both Units 1 and 2, limited to no more than 1760 fuel assemblies.
l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS f
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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.
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CALVERT CLIFFS - UNIT 2 5;5 Amendment No U, M, 4 5 O
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