ML17228A898

Amend 68 to License NPF-16,revising TS 3/4.7.1.1, Turbine Cycle,Safety Valves, to Delete Specific Ref to 1974 Edition of ASME Code & Refer to Testing in Accordance W/Ts 4.0.5, ISI & IST Ts

ML17228A898
Person / Time
Site:	Saint Lucie
Issue date:	11/01/1994
From:	Thadani M Office of Nuclear Reactor Regulation
To:
Shared Package
ML17228A899	List: ML17228A898 ML17228A900
References
NUDOCS 9411070369
Download: ML17228A898 (8)

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~ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINCiTON, D.'C. 20555-0001 FLORIDA POWER 5 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.

License No.

NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Florida Power

& Light Company, et al. (the licensee),

dated May 23,

1994, 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 wil'1 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.

i 94110703b9 941101 PDR'DOCK 05000389 P

PDR

1 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:

k 2.

Technical S ecifications 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. ~8

, are hereby incorporated in the license.

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

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

FOR THE NUCLEAR REGULATORY COMMISSION Mohan Thadani, Acting 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:

November 1, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

NPF-16 OOCKET 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.

Index Page XXV 3/4 7-1 3/4 7-3 Index Page XXV 3/4 7-1

. 3/4 7-3

LIST OF TABLES (Continued)

INDEX TABLE 3.7-1 3.7-2 4.7-1 4.7-2 3

~ 7 3'B 3.7-3b 3.7-4 3.7-5 4.8-1 4.8-2 3.8-1 4.11-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM......................................

3/4 7-8 SNUBBER VISUAL INSPECTION INTERVAL....................

3/4 7-22 ELETEDo

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D FIRE HOSE STATIONS..............................

3/4 7-26 3/4 7-27 3/4 7-36 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES 3/4 7-38 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-8 BATTERY SURVEILLANCE REQUIREMENT.....................'.

3/4 8-12 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES........'................................

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS 3/4 8-18 PAGE MAXIMUMALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS........................

3/4 7-2 STEAN LINE SAFETY VALVES PER LOOP......................

3/4 7-3 4.11-2 3.12-1 3.12-2 ROGRAH ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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P RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAH.....................'..........................

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.........

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.................................

3/4 11-2 3/4 11-8 3/4 12-3 3/4 12-7 4.12-1 B 3/4.2-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS~ o

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ELETED...............................................

D B 3/4.4-1 REACTOR VESSEL TOUGHNESS..............................

3/4 12-8 B 3/4 2-3 B 3/4 4-9 5.7-1 6.2-1 MINIMUM SHIFT CREW COMPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL ROOMS................................

6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS..................

5-5 ST.

LUGIE UNIT 2 XXV Amendment No. MH-,~3; 68

3 4.7 PLANT SYSTEMS 3 4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings and ori;fice si;zes as shown in Table 3.7-..2.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION a.

With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided. that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High,trip setpoint is reduced per Table 3.7-1; 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4;7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

ST.

LUGIE - UNIT 2 3/4 7-1 Amendment Noh

TABLE 3.7-1 MAXIMUMALLOWABLE POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY. VALVES DURING OPERATION WITH BOTH STEAM GENERATORS Maximum Number of Inoperable Safety Valves on An 0 eratin Steam Generator Maximum Allowable Power Level-High Trip Setpoint Percent of RATED THERMAL POWER 92.8 79.6 66.3

l foal I

VALVE NUMBER Header A

Header B

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING-

+ 1X ORIFICE SIZE a.

8201 b.

8202 c.

8203 d.

8204 e.

8209 8210 g.

8211 h.

8212 8205 8206 8207 8208 8213 8214 8215 8216 1000 psia 1000 psia 1000 psia 1000 psia 1040 psia 1040 psia 1040 psia 1040 psia 16 in. 2 16 in. 2 16 in.

16 in.

16 in.

16 in. 2 16 in. 2 16 in.

PLANT SYSTEMS AUXILIARYFEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION

3. 7. 1. 2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two feedwater

pumps, each capable of being powered.from separate OPERABLE emergency

busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

'a 0 b.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

SURVEILLANCE RE UIREMENTS 4.7. 1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a 0 At least once per 31 days by:

1.

Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to X270 psig on recirculation flow.

2.

Verifying that the turbine-driven pump develops a discharge pressure of greater than or equal to 1260 psig on recirculation flow when the secondary steam supply pressure is greater than 50 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

3.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

ST.

LUCIE - UNIT 2 3/4 7-4 Amendment No.

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