ML17229A225

Amends 148 & 87 to Licenses DPR-67 & NPF-16,respectively, Revising Plant TSs to Remove Inconsistencies Between Definition of Core Alterations & Applicability,Action & SRs of Two Specs

ML17229A225
Person / Time
Site:	Saint Lucie
Issue date:	02/10/1997
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML17229A226	List: ML17229A225 ML17229A227
References
NUDOCS 9702140251
Download: ML17229A225 (10)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER

& LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 License No.

DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power

& Light Company, et al.

(the licensee),

dated October 30,

1996, 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.

9702i4025i 9702i0 PDR ADQCK 05000335 P

PDR

2.

3.

Accordingly, Facility Operating License No.

DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph,2.C.(2) to read as follows:

(2) Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. i48, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February i0, 1997 Frederick J.

Heb on, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT N0.148 0

CI TY OPE TING ICENSE NO.

DP -67 DOCKET NO. 50-335 Replace the following pages of the Appendix

".A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Re ov Pa es 3/4 9-9 3/4 9-10 sert Pa es 3/4 9-9 3/4 9-10

~ REFUELING OPERATIO CONTAINMENTISOLATION SYSTEM LIMITINGCONDITION FOR OPERATION 3.9.9 The containment isolation system shall be OPERABLE.

APPLICABILITY:

During CORE ALTERATIONS.

During movement of irradiated fuel assemblies within containment.

ACTION:

With the containment isolation system inoperable, close each of the penetrations providing direct access from the containment atmosphere to the outside atmosphere.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment isolation system shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment isolation occurs on manual initiation and on a high radiation signal from two of the containment radiation monitoring instrumentation channels.

ST. LUCIE - UNIT 1 3/4 9-9 Amendment No. 40, 408 148

REFUELING OPERATIO WATER LEVEL-REACTOR VESSEL LIMITINGCONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated within the reactor pressure vessel, APPLICABILITY:

During CORE ALTERATIONS.

During movement of irradiated fuel assemblies within containment.

ACTION:

With the requirements of the above specifications not satisfied, immediately suspend CORE ALTERATIONSand movement of irradiated fuel assemblies within containment, and immediately initiate action to restore refueling cavity water level to within limits.

SURVEILLANCEREQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during CORE ALTERATIONSand during movement of irradiated fuel assemblies within containment.

ST. LUCIE - UNIT 1 3/4 9-10 Amendment No. 148

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&0001 FLORIDA POWER 5 LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.

LUCIE PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

87 License No.

NPF-16 1.

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

A.

B.

C.

D.

The application for amendment by Florida Power

& Light Company, et al. (the licensee),

dated October 30,

1996, 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; The facility will oper ate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; P

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; 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, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:

2.

Tec n'cal S ecifications 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 87

, are hereby incorporated in the license.

- The licensee shall operate the facility in accordance with the Technical Specifications.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION lJa4.

Frederick J.

Hebd

, Director Project Directorate II-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 10, 1997

ATTACHMENT TO LICENSE AMENDMENT NO.

87 TO CILITY OPERATING LICENSE NO. NPF-16 50 KEK 55.

5 -3 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

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P 3/4 9-10 3/4 9-11 3/4 9-10 3/4 9-11

REFUELING OPERATION 3/4.9.9 CONTAINMENTISOLATION SYSTEM LIMITINGCONDITION FOR OPERATION 3.9,9 The containment isolation system shall be OPERABLE.

APPLICABILITY:

During CORE ALTERATIONSor movement of irradiated fuel within containment.

ACTION:

With the containment isolation system inoperable, close each of the containment penetrations providing direct access from the containment atmosphere to the outside atmosphere.

SURVEILLANCEREQUIREMENTS 4.9.9 The containment isolation system shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONSby verifying that containment isolation occurs on manual initiation and on a high. radiation test signal from each of the containment radiation monitoring instrumentation channels.

ST. LUCIE - UNIT2 3/4 9-10 Amendment No. 87

REFUELING OPERATIO 3/4.9.10 WATER LEVEL-REACTOR VESSEL

~

LIMITINGCONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.

APPLICABILITY:

During CORE ALTERATIONS.

During movement of irradiated fuel assemblies within containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend CORE ALTERATIONSand movement of irradiated fuel assemblies within containment, and immediately initiate action to restore refueling cavity water level to within limits.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during CORE ALTERATIONS and during movement of irradiated fuel assemblies within containment.

ST. LUCIE - UNIT2 3/4 9-11 Amendment No.

87