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d  t d    A    ndme t  I I d t d l      85        NPF-l 6 Poge 8
: 18. Reactor    Tri    Breakers  Post-Tri    Review Procedures    (Section
                        . .3. .        R4 Within 60 days of issuance of this amendment, the licensee shall provide the upgraded post-trip review procedures for NRC staff review.
: 19. Prior to storing extended burnup fuel in the modified spent fuel pool (greater than 38,000 Mwdays/Metric ton) the licensee must submit and obtain approval of a new analysis that addresses the potential of large gap releases for the extended burnup fuel.
D. The licensees      shall fully implement and maintain in effect all the provisions of    the  Commissionmpproved physical security, guard training and qualification    and safeguards contingency plans including amendments made pursuant to the authority of 10 CFR Section 50.54(p).                The approved plans,      which  contain information  described in 10 CFR  Section 73.21, are collectively entitled "Florida Power and Light Company, St.
Lucie Plant Security Plan, Revision 6, dated August 9, 1982; St. Lucie Plant Safeguords.Contingency Plan" dated June 19, 1980; and St. Lucie Plant Training and Qualification Plan dated April 29, 1981, as revised by pages dated June 23, 198I. Prior to initial criticality, the licensees shall satisfy the commitments in FPQ 's letters L3-2I5 doted April 5, 1983 and L-83-217 dated April 6, 1983. Also prior to initial criticalityf the licensees shall perform a reevaluation of vital areas with due, regard to the sofety-safeguards interface, and provide the NRC the results of their reevaluation.
E. Before engoging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evalauted in the Final Environmental Statement dated April 1982, the licensees shall provide written notification to the Office of Nuclear Reactor Regulation.
F.  -  The licensees shall report any violations of the requirements contained in Section 2, Items C.(l), C.(3) through C.(17), D. and E. of this license within 24 hours by telephone and confirm by telegram, mailgram or facsimile transmission to the NRC Regional Administrator, Region II, or his designee, no later than the first working day following the violation,
                'with a written followup report within fourteen (14) days.
G. The licensees shall notify the Commission, as soon as passible but not later than one hour, of any accident at this facility which could result in.
an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.
The licensees shall hove and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
8b04280078 860421 PDR    ADacK 05000389 P
PDR}}

Latest revision as of 14:53, 4 February 2020

Proposed Tech Specs,Deleting Condition 2.C.19 to Permit Discharge of Fuel at End of Cycle 3 Operation Above Stated Limits
ML17216A505
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/21/1986
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17216A504 List:
References
NUDOCS 8604280078
Download: ML17216A505 (1)
v • d • e


Text

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d t d A ndme t I I d t d l 85 NPF-l 6 Poge 8

18. Reactor Tri Breakers Post-Tri Review Procedures (Section

. .3. . R4 Within 60 days of issuance of this amendment, the licensee shall provide the upgraded post-trip review procedures for NRC staff review.

19. Prior to storing extended burnup fuel in the modified spent fuel pool (greater than 38,000 Mwdays/Metric ton) the licensee must submit and obtain approval of a new analysis that addresses the potential of large gap releases for the extended burnup fuel.

D. The licensees shall fully implement and maintain in effect all the provisions of the Commissionmpproved physical security, guard training and qualification and safeguards contingency plans including amendments made pursuant to the authority of 10 CFR Section 50.54(p). The approved plans, which contain information described in 10 CFR Section 73.21, are collectively entitled "Florida Power and Light Company, St.

Lucie Plant Security Plan, Revision 6, dated August 9, 1982; St. Lucie Plant Safeguords.Contingency Plan" dated June 19, 1980; and St. Lucie Plant Training and Qualification Plan dated April 29, 1981, as revised by pages dated June 23, 198I. Prior to initial criticality, the licensees shall satisfy the commitments in FPQ 's letters L3-2I5 doted April 5, 1983 and L-83-217 dated April 6, 1983. Also prior to initial criticalityf the licensees shall perform a reevaluation of vital areas with due, regard to the sofety-safeguards interface, and provide the NRC the results of their reevaluation.

E. Before engoging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evalauted in the Final Environmental Statement dated April 1982, the licensees shall provide written notification to the Office of Nuclear Reactor Regulation.

F. - The licensees shall report any violations of the requirements contained in Section 2, Items C.(l), C.(3) through C.(17), D. and E. of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm by telegram, mailgram or facsimile transmission to the NRC Regional Administrator, Region II, or his designee, no later than the first working day following the violation,

'with a written followup report within fourteen (14) days.

G. The licensees shall notify the Commission, as soon as passible but not later than one hour, of any accident at this facility which could result in.

an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.

The licensees shall hove and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

8b04280078 860421 PDR ADacK 05000389 P

PDR

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