ML17229A341

Amend 151 to License DPR-67,deleting Footnote Which Requires Reactor Thermal Power to Be Limited to 90% of 2700 Megawatts Thermal for Cycle 14 Operation Beyond 7000 Effective Full Power Hours

ML17229A341
Person / Time
Site:	Saint Lucie
Issue date:	05/16/1997
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML17229A342	List: ML17229A341 ML17229A343
References
NUDOCS 9705200311
Download: ML17229A341 (7)

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UNITED STATES NUCLEAR REGULATORY COlVIMISSION WASHINGTON> D.C. 20555-0001

'FLORIDA POWER

& LIGHT COMPANY DOCKET NO. 50-335 S

C P

NT T

0 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

License No.

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

A.

B.

C.

D.

The application for amendment by Florida Power

& Light Company, (the licensee),

dated December 20,

1996, as supplemented February 13, and April 17,

1997, 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 operate in conformity with the application, 'the provisions of the Act, and the rules and regulations of the Commission; 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 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.

97052003li 9705ih POR ADOCK 05000335 P

PDR

f

2.

Accordingly,.Facility Operating License No.

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

(2) echnical S ecif'cat'ons The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 151, are hereby incorporated in the license.

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

Also, the license is amended by adding a new License Condition, Paragraph 2.C.(6), to page 3a of the Facility Operating License DPR-67, as follows:

3.

'(6) Sustained Core Uncover Actions Procedural guidance shall be in place to instruct operators to implement actions which are designed to mitigate a small break loss of coolant accident prior to a calculated time of sustained core uncovery (Amendment No. 151 ).

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

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J.

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

1.

Page 3a of license 2.

Changes to the Technical Specifications Date of Issuance:

May 16, 1997 Page 3a is attached, for convenience, for the composite license to reflect this change.

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~X IIIg Procedural guidance shall be in place to instruct operators to implement actions which are designed to mitigate a small break loss of coolant accident prior to a calculated time of sustained core uncovery (Amendment Ho. 151 ).

2.D The licensee shall fully imolement and maintain in effect. al'I provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions'of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the'authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

'"St. Lucie Plant Security Plan,"

with revisions submitted through April 11, 1988; "St. Lucie Plant Training and gualification Plan," with revisions submitted through August 8, 1985; and "St. Lucie Plant Safegvards Contingency Plan,"

with'evisions submitted through December 8, 1986.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set, forth therein.

4

ATTACHMENT TO LICENSE AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

DPR-67 DOCKET NO. 50-335 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.

The revised page is identified by amendment number and

~

contains a vertical line indicating the area of change.

~R 2-1 Insert Pa e

2-1

2.0 2.1 REACTOR'.1.)

The ceabtnatfm of THENlLpe, pressurizer pressure>

and aad ee cold leo coolant teeperature shall aoCrexceed the lialts shoe m figure 2'l-l.

AP CAl s

NOES 1 and t lCT~ONs Neneve the yofnt defined by the coIbinatfon of sixteen cold les taipei ature and THUNAL PNER has exceeded the appropriate pressur)e'er pres~

l)ne. be fn HOT STANOIY Hthin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REACTtN COOLANT TN PR tN 2.1.2 The Reactor Coolant Systoe pressure shall not exceed 2750 ps)a.

ANLTCASl TY:

NOES ly 2y 3e 4 and Io ACTIOll:.

NteES 1 and 2 Nenever the Reactor Coolant Syitm pressure has exceeded f750 ps$ a>

be

$ n HOT STANOSY Qth the Reactor Coolant Systee pressure &thea its 1)m)t ~3th)n l hour.

MODES 3o 4 and 5 Nenevei ~ the Raacti Coolant Systee pressure has exceeded

@50 ps1a, reduce the Reactor Coolant System pressure to Hth$ n its lWt

~)th)n I Hmtes.

Amendment No.~

151'To LUC?K NIT 1 2l