ML17341B357

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Amends 88 & 82 to Licenses DPR-31 & DPR-41,respectively, Changing Tech Specs to Modify Fq & Figure 3.2-3,k(z) Vs Core Height,For Repaired Steam Generators
ML17341B357
Person / Time
Site: Turkey Point  
Issue date: 08/13/1982
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17341B358 List:
References
NUDOCS 8209010359
Download: ML17341B357 (10)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA'POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.BB License No.

DPR-31 1.

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

A.

The application for amendment by Florida Power and Light Company (the licensee) dated April 15,

1982, 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.

8209010359 820813 PDR ADQCK 05000250 P

PDR

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.

DPR-31 is hereby amended to read as follows:

(B)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 88

, are hereby incorporated in the license.

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

3.

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

F THE NUC GULATORY COMMISSION ar'a", C-perating Reactor 8

Division of Licen i f

anch 81

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 13, 1982

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UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.82 License No. DPR-41 1.

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

A.

The application for amendment by Florida Power and Light Company (the licensee) dated April 15, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the.Act) and the Commission's ru'1es 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 saf ty 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-41 is hereby amended to read as follows:

(B)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82

, are hereby incorporated in the license.

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

3.

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

FO

,THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications A.

arga, Ch f B

Operating Reactors B anch 81 Division of Licens g

Date of Issuance:

August 13, 1982

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO.

DPR-31 AMENDMENT NO.

82 TO FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 Revise Appendix A as follows:

Remove Pa es 3 ~ 2 3 Figure 3.2-3a Insert Pa es 3.2-3 Figure 3.2-3a

reactivity inse 'on upon ejection greater than 5

k/k at rated power.

Inopera rod worth shall be determined hin 4 weeks.

b.

A control rod shall be considered inoperable if (a) the rod cannot be moved by CRDM, or (b) the rod is misaligned from its bank'by more than 15 inches, or (c) the rod drop time is not met.

c.

If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased.by boron addition to compensate for the wi thdrawn worth of the i'noperable rod.

5.

CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm is not operable, rod positions shall be logged once per shift and after a load change greater than 10/ of rated power.

If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93$ of rated power.

6.

POWER DISTRIBUTION LIMITS a.

Hot channel factors:

(1)

FQ Limit The hot channel factors (defined in Bases) must meet the following limits at all times except during low power physics tests:

FQ (Z)

< ([FQ]L(p) x K(Z), for P

> 0. 5 FQ (Z)

< (2 x [FQ]L) x K(Z), for P

< 0.5 FN

< 1.55 [1.0 + 0.2 (1 - P)3

>H Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3 or Figure 3.2-3a; Z is the core height location of Fz.

[FQ)L and K(Z) are dependent on the steam generator tube plug)ing level as follows:

Plugging level

>5 5 and

< 28$

fFQ]L Figure Number for K(Z) 2.125 3.2-3*

< 55

2. 30 3>> 2-3a l

I

~ 4 i

(2)

Augmented Surveillance (MIDS)

If [FQ]

, as predicted by approved physics calculations, exceeds

[FQ)L tIen the power will be limited to a turnon power fraction, PT, equal to the ratio of [Fz]L divided by fFQ], or, for operation at power levels ab6ve Pq, augmented sLrveillance of hot channel factors shall

.be implemented, except in Base Load g

25 d Fi 3.2-3 of the new steam generators.

3.2-3 Amendment Nos.

88

& 82

HOT CHANNEL FACTOR NO&fALIZED OPERATING ENVELOPE (for < 5% steam generator tube plugging and F

2.30)

(6.0, 1.000)

(10.8,

.939)

(12.0,

.43 10 12 CORE HEIGHT (FT.)

FIG. 3.2-3a Amendment Nos.

88 5 82