ML17346A206

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Amends 101 & 95 to Licenses DPR-31 & DPR-41,respectively, Revising Tech Specs to Add Motor Operated Valves 863-A & 863-B to Existing Valves Required to Have Power Removed
ML17346A206
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/22/1984
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17346A207 List:
References
NUDOCS 8403010171
Download: ML17346A206 (9)


Text

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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.

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 July ll, 1978, as supplemented August 9, 1978,'anuary 4,

1983, February 15, 1983 and October 31,
1983, 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.

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-31 is hereby amended to read as follows:

84030i017i 840~22 PDR ADOCK 05000250 P

PDR

(8)

Technical S ecification 1

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

101

, 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.

FOR THE NUCLEAR REGULATORY COMMISSION even A.

rga, hie Operating Reactors Bran No.

1 Division of Licensing

Attachment:

Change to the Technical Specifications Date of Issuance:

FEB 2 p

~984

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

101 TO FACILITY OPERATING LICENSE NO.

DPR-31 AMENDMENT NO.

95 TO FACILITY OPERATING LICENSE NO.

DPR-41 DOCKET NOS.

50-250 AND 50-251 Revise Appendix A as follows:

Remove Pa es 3.4-2 3.4-3 Insert Pa es 3.4-2 3.4-3

5. ~0 residual heat removal pumps shall be, operablc.

6 TWO residual heat exchangers qhaI1 be operable I

I

7. Allvalves, Interlocks and pSping assocIated vXth the above components and required for post acciden operation, shall be operable, except valves that are positioned and locked.

Valves 862-A&B 863-A&B; 864-A&B; 865-A.B&C; 866-A&B shall have power removed from theSr motor operators by locking open the circuit breakers at the Hotor Control Centers.

The air supply to valve 758 shall be shut off to the valve operator.

b. Wring power operation, the requirements of 3.4.la may be modified to allow one of the following com-ponents to be inoperable (including associated valves and piping) at any one time except =for the cases stated Ln 3.4.l.b.2. 'f the system is not restored to meet the requirements of 3.4.1a %thin the time period, specified, the reactor shal1 be placed in the hot shutdown condition. If the requirements of 3.4.1a are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the reactor shall be placed in the cold shutdown condition.

4 1.

ONE~ccumulator may be out of service for a period of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2; ONE of FOUR safety injection pumps may be out of service for 30 days.

A second safety in-

/ection pump may be out of service, provided the pump is restored to operable status Mthin l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TWO of the FOUR safety Infection pumps sha11 be tested to demonstrate operability before.

initiating maintenance of the Inoperable pumps.

3.

Ohr. channel of heat tracing on the flow path may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

'mendment Nos. 101 and 95

5.

ONE residual heat exchanger may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

Any valve in the system may be inoperable pro-vided repairs are cotrpleted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..

Pri or to initiati ng maintenance, al 1 valves that, provide the duplicate function shall be tested to demonstrate operability.

7.

To permit temporary operation of th

valve, e.g., for surveillance of val ve operability, for the purpose of valve maintenance, etc.,

ihe

.valves specified in 3.4.l.a.7 may be unlocked and may have supplied air or electric power res.or d ter a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

EHERGBlCY COHTAIlll<ENT COOLING SYSTBIS a.

The reactor shall not be m=-de critical, except for low power physics tests, unless ie following condi.i ons are m t:

l.

THEE emergency containment cooling uniis are ope rabl e.

2.

TWO containm nt spray pcs are operable.

3.

ALL valves and piping associated wi.h the above components, and required for post accident operation, are operable.

b.

During power operation, the requirements o

3.4.2a may be modified to allow one of the following components to be inoperable (including associated valves and piping) at any one.time.

'Tf the system is not restored to meet the requiremen.s of 3.4.2a within the tine period speci ied, the reactor shall be placed in the hot shuidown condition.

If the requirements of 3.4.2a are noi satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold, shutdown condi tion.

3.4-3 Amendment Nos.101 and 95

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~O UNITED STATES NUCLEAR REGULATORY t."OMMISSION

'WASHINGTON, O. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.

4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

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 July ll, 1978, as supplemented August 9,

1978, January 4,
1983, February 15, 1983 and October 31,
1983, 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.

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

g5

, 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.

FOR THE NUCLEAR REGULATORY COI'If EMISSION even

arga, e

Operating Reactors Br No.

1 Division of Licensing

Attachment:

Change to the Technical Specifications Date of Issuance:

FEB 2 2 f984