ML20058A178
| ML20058A178 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/19/1993 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058A181 | List: |
| References | |
| NUDOCS 9311300142 | |
| Download: ML20058A178 (7) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION p
WASHINGTON, D. C. 20555 r,,.
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TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UhlT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.181 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated June 23, 1993, as supplemented on October 5,-1993, 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 Chapte.- I; B.
The facility will operate in conformity with the application, the t
provisions of the Act, and the ruks 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 tne 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 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
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(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
181, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Jon B. Hopkins,
. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November 19, 1993
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ATTACHMENT TO LICENSE AMENDMENT N0.181 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 1
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 9-13 3/4 9-13 3/4 9-14 3/4 9-14 5-5 5-5 b
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DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,1110 1 200 cubic feet at a nominal T,,of 525'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 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A K,,, equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance of 1% delta k/k for calculation uncertainty.
b.
A rectangular array of stainless steel cells spaced 12 31/32 inches on centers in one direction and 13 3/16 inches on centers in the other direction.
Fuel assemb11N stored in the spent fuel pool shall be placed in a stainlest neel cell of 0.125 inches nominal thickness or in a failed fuel container.
Fuel assemblies stored in the spent fuel pool in accordance with c.
Technical Specification 3.9.13.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
A K,,,
ted water, which includes a conservative allowance of 1% delta equivalent to less than or equal to 0.95 when flooded with a.
unbora k/k for uncertainties as described in Section 9.1 of the USAR.
b.
A K,,, equivalent to less than or equal to 0.98 when immersed in a hydrogenous " mist" of such a density that provides optimum moderation (i.e., highest value of X,h,)for uncertainties as i
, which includes a conservative allowance of 1% delta k/
described in Section 9.1 of the USAR.
A nominal 21 inch center-to-center distance between fuel assemblies c.
placed in the storage racks.
d.
Fuel assemblies having a maximum initial enrichment of 5.0 weight percent uranium-235.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 9 feet above the top of the fuel storage racks.
DAVIS-BESSE, UNIT 1 5-5 Amendment No. 19,179,181
9 DESIGN FEATURES CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 735 fuel assemblies.
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 limit of Table 5.7-1.
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DAVIS-BESSE, UNIT 1 5-6 Amendment No.13
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REFUELING OPERATIONS SPENT FUEL POOL FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.13 Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel storage racks in' ace'rda~ ce 'with the crit'eria shown in Fiaure 3.9-1.
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APPLICABILITY:
Whenever fuel assemblies are in the spent fuel pool.
4 ACTION:
With the requirements of the above specification not satisfied, suspend all other fuel movement within the spent fuel p o1 and move the non-complying fuel assemblies to allowable locations in the spent fuel pool in accordance with Figure 3.9-1.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13.1 Prior to. Stnring the fuel assembly in the spent fuel pool, verify by administrative means that the initial enrichmont end. burnup of.'the fuel assembly is in accordance with Figure 3.9-1.
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I DAVIS-BESSE, UNIT 1 3/4 9-13 Amendment No. J3p.181
Figure 3.9-1
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Burnup vs. Enrichment Curves For Davis-Besse Spent Fuel Storage Racks 60 i
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5.0,44.2 i
D s.-
!(4.5,37.8 o
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(4.0. 32.6y l
E 30 (3.5,28.4 [
Allowed c
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(3.0,23.1
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(2.5,17.9[
"B" (5.0,10.8g
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(4.5,7.9 (4.0,4.4).
1I tI (1.6, OJ)
(3.56,0.0) s 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 InitialEnrichment (wt% U-235) i Category "A": May be placed in any rack location Category "B": ?fust not be placed directly adjacent to Category "C" assemblies Category "C": May only be placed directly adjacent to Category "A" assemblies or non-fuellocadons DAVIS-BESSE. UNIT 1 3/4 9-14 Amendment No, 130,181
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