ML20235Z378

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Amends 136 & 117 to Licenses DPR-53 & DPR-69,respectively, Modifying Tech Spec 5.6.1, Criticality - Spent Fuel, to Increase U-235 Enrichment Limit for Unirradiated Fuel Stored in Spent Fuel Storage Racks to 5.0 Weight % U-235
ML20235Z378
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 03/07/1989
From: Capra R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235Z380 List:
References
NUDOCS 8903150405
Download: ML20235Z378 (9)
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i B_ALTIMORE GAS AND ELECTR_IC COMPANY DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No.136 License No. DPR-53 l

1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9,1988 as supplemented on October 25 November 17 and December 28, 1988, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct) and the Commission's rules and reg'ulations set forth in 10 CFR

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Chapter I;

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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 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 Cosetission's regulations and all applicable requirements have been satisfied.

E.

2.

Accorgagly,thelicenseisamendedbychangestotheTechnical Spectrvcetions 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:

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, 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.

FOR THE NUCLEAR REGULATORY COPMISSION

] oL 2 0.. C w Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 7, 1989 i

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g;(f.'- j WASHINGTON, D. C. 20686 WG BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT-CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-69 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9, 1988 as supplemented on October 25, November 17, and December 28, 1988, 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 F.

The issuance of this amendment is in accordance with 10 CFR Part Sirof the Comission's regulations and all applicable requirements ehave.been satisfied, gn.g 2.

Acc ly. the. license is amended by changes to the Technical Spec,

tions as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No.

DPR-69 is hereby amended to read as follows:

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3' (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.117, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical l

Specifications.

l 3.

This license amendment is effective as of the date of its issuance.

l FOR THE NUCLEAR REGULATORY COMISSION

& 0. ~ 0V Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II 1-

Attachment:

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Changes to the Technical t

Specifications Date of Issuance: March 7, 1989 J

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I ATTACHMENT TO LICENSE AMEN 0MENTS.

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AilENDNENT NO. 136 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

Remove Pages Insert Paoes 5-5 5-5 5-6*

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  • 0verleaf provided for continuity purposes.

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DESIM FEATURES YALE 5.4.2 The total water and steam volume of the reactor coolant syste is 10,614 f 460 cubic feet at a nominal T,,, of 532*Fs 5.5 METECR0 LOGICAL 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 5.6.1 The spent fuel storage racks are designed and shall be.asjntained 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 storage pool filled with unborated water.,ff equivalent to < 0.95 with theof < 0795 incl The k,f conservative allowances for uncertainties describ58 in s~ection 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 weight percent for irradiated fuel

  • and 5.0 weight percent for f tte l that has not been irradiated.

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.cf will not exceed 0.95 whee fuel having a maximum enrichment of 5.0 weight Mrcent U 235 is in place and various densities of unborated water are assumed including aqueous foam moderation and full flood conditions. The klgg of 10.95 includes the conservative allowance for uncertainties described t Section 9.7.2 of the FSAR.

l 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 feet.

CAPACITY I

5.6.4 The fuel storage pool is destgried and shall be maintained with a combined storage capscity, for both Units I and 2. limited to no more than 1830 fuel assemblies.

5.7 COMPONENT CYCLIC fA TRAN5!ENT L!MtT5 l

5.7.1 The components identified in Table 5.7-1 are designed and shall be i

maintained within.~the cyclic or transient limits of Table 5.7-1.

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  • Irradiated fuel is fuel thtt has experienced the critical state (K,fg greater than or equal to one).

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l CALVERT CLIFFS - UNIT 1 5-5 Amendment No.37, py, 33, 89,16/,,1 l

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5.4.2 The total water and steam volume of the reactor coolant systes is 10.614

?. 440 cubic feet at a nominal T,,, of 532*F 5.5 METEOROLOGICAL TOWER I.0 CAT 10N 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 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 storage pool filled with unborated water.,ff equivalent to < 0.95 with the placed in the storage racks to ensure a k l

conservative allowances for uncertainties describNf of < 0795 The k in $~ection 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 4.1 weight percent f or irradiated fuel

  • and 5.0 weight percent for fumi that has not been irradiated.

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 I

S.0 weight hwill not exceed 0.95 when fuel having a maximum enrichment ent U-235 is in place and various densities of unborated water

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are assumed including aqueous feas moderation and full flood conditions. The of 10.95 includes the conservative allowance for uncertainties described k

1$feSection 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 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 1830 fuel assemblies.

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5.7 CSWGNDff CYCLIC OR TRANSIENT LigI),

5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained withinJthe cyclic or transtant limits of Table 5.7-1.

  • ttradiated fuel is fuel that has experienced the critical state (K,gg greater than or equal to one).

CALVERT CLIFFS - UNIT 2 5-5 Amenh ent No. M. if. ff. W. /

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