ML17223B360

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Amends 111 & 52 to Licenses DPR-67 & NPF-16,respectively, Revising Tech Specs for Both Units to Clarify Testing Requirements for Main Steam & Feedwater Line Isolation Valves
ML17223B360
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/05/1991
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17223B362 List:
References
NUDOCS 9112110321
Download: ML17223B360 (11)


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O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 4~

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FLORIDA POWER 8( LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

License No.

DPR-67 1.

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

A.

The application for amendment by Florida Power 5 Light Company, et al. (the licensee),

dated July 26,

1989, 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.

9112110321 911205 PDR ADOCK 05000335 P

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2.

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. 111, 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 H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 5, 1991

ATTACHMENT TO LICENSE AMENDMENT NO.

111 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 vertical lines indicating the area of change.

The corresponding over leaf page is also provided to maintain document completeness.

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3/4 7-9 Insert Pa e

3/4 7-9

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALV S LIMITING CONDITION FOR OPERATION RRQRQQRQC1%RRRRRR R

RRQRE5QOlSNCSCSQSSStCCQCQSCCRCSCCZCC5ZSRRRRCQRtQRSSZSRZCRRQRRQQSZRR 3.7. 1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1

- With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in HOT STANDBY within the next 6

hours.

MODES 2

and 3

With one or both main steam isolation valve(s) inoperable, subsequent operation in MODES 2 or 3 may proceed provided the isolation valve(s) is (are) maintained closed.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS RC CCRC R

R 4RRRRRRRQRCRtQC5RSZCQQRZSRQRCARR CCIDCCQQ QRIECCCRRSCORRQQRR R

4.7. 1.5 Each main steam line isolation valve that is open shall be demonstrated OPERABLE by verifying full closure within 6.0 seconds when tested pursuant to Specification 4.0.5.

ST.

LUCIE UNIT 1

3/4 7-9 Amendment No 99 111

THIS PAGE LEPT INTENTIONALLYBLANK ST, LUCIE - UNIT 1 3/4 7-10 Amendment No. 86

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 8( 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.

52 License No.

NPF-16 1.

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

A.

The application for amendment by Florida Power 8 Light Company, et al. (the licensee),

dated July 26, 1989, 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'.

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.

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, 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 Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 5,

1991

ATTACHMENT TO LICENSE AMENDMENT NO.

52 TO FACILITY OPERATING LICENSE NO.

NPF-16 DOCKET NO.

50-389 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.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Pa es 3 4 7-9 3/4 7-10 Insert Pa es 3/4 7-9 3/4 7-10

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P ANT SYSTEMS MA N STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7. 1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

MODE 1

MODES 2, 3 and 4

With one main steam line isolation valve inoperable but

open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With one or both main steam line isolation valve(s) inoperable, subsequent operation in MODES 2, 3 or 4 may proceed provided the isolation valve(s) is (are) maintained closed.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS aasnsaQRsnsssssas sn>>

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easneasnea cR aasasaaa snDRDRR RasQsncccRQQSR osaaaacR 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 6.75 seconds when tested pursuant to Specification 4.0.5.

ST.

LUCIE UNIT 2 3/4 7-9

/

Amendment No. 35, 52

C HAIN FE DWATER LI ISO ATION VA V S LIMITING CONDITION FOR OPERATION CR RCRRCCCRRRRRRZSQCC CSSSQSRCRRQRRR 0

RCS?SStRXRRQCtCZ5%%

QQWCR5RRDRC?5Ã5BSISRRQ 3.7. 1.6 Each main feedwater line isolation valve shall be OPERABLE.

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ACTION:

MODE 1-With one main feedwater line isolation valve inoperable but

open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2, 3 and 4

With one or both main feedwater line isolation valve(s) inoperable, subsequent operation in MODE 2, 3, or 4 may proceed provided the isolation valve(s) is (are) maintained closed.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN.within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

~SSSQRRR'RR'RRR RRRSRQQCSCRQRSQRRRRRRRRRQRCRQCCNSNR5QC5CSQQSRCQRQ QQQCSRRNZ5RRNCRRR 4.7. 1.6 Each main feedwater line isolation valve shall be demonstrated OPERABLE by verifying full closure within 5. 15 seconds when tested pursuant to Specification 4.0.5 ST.

LUCIE UNIT 2 3/4 7-10 Amendment No. 8, SS, 52 E