ML17228B119

Amends 135 & 74 to Licenses DPR-67 & NPF-16,respectively, Relocating Seismic Monitoring Instrumentation Lco,Sr & Associated Tables Contained in TS 3.3.3.3,4.3.3.3.1 & 4.3.3.3.2 to UFSAR

ML17228B119
Person / Time
Site:	Saint Lucie
Issue date:	04/25/1995
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML17228B120	List: ML17228B119 ML17228B121
References
NUDOCS 9505040092
Download: ML17228B119 (16)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 FLORIDA POWER 8E LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No.

DPR-67 1.

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

A.

B.

C.

D.

E.

The application for amendment by Florida Power 8 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 will 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.

50504009P 9504 PDR ADQCK 05000335 P

PDR jg

2.

3.

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. 135, 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 David B. Matthews, Director Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

'Specifications Date of Issuance:

April 25, 1995

ATTACHMENT TO LICENSE AMENDMENT NO.

135 TO FACILITY OPERATING LICENSE NO.

DPR-67 DOCKET NO. 50-335 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 IV 3/4 3-27 thru 3/4 3-29 B 3/4 3-2 Insert Pa es IV 3/4 3-27 8 3/4 3-2

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3 4.2 POWER DISTRIBUTION LIMITS PAG 3/4.2.1 LINEAR HEAT RATE...................................

3/4 2-1 3/4.2.2 DELETED 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR F........

3/4 2-9 r'''

3/4.2.4 AZIMUTHAL POWER TILT T...........

q 3/4.2.5 DNB PARAMETERS......................

3 4.3 INSTRUMENTATION

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13 3/4.3. 1 REACTOR PROTECTIVE INSTRUMENTATION................. 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION INSTRUMENTATION.....................

SYSTEM

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~ 3/4 3 9 3/4.3.3 MONITORING INSTRUMENTATION....;.................... 3/4 3-21 Radiation Monitoring...............................

3/4 3-21 Incore Detectors...................................

3/4 3-25 Meteorological Instrumentation...

3/4 3-30 Remote Shutdown Instrumentation....................

3/4 3-33 Accident Monitoring Instrumentation................

3/4 3-41 Exp1osive Gas Monitoring Instrumentation...........

3/4 3-50 3 4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...... 3/4 4-1 3/4.4.2 SAFETY VALVES SHUTDOWN...........................

3/4 4-2

'3/4.4.3 SAFETY VALVES OPERATING..........................

3/4 4-3 ST.

LUCIE UNIT 1 IV d

d N

. NNNN;Nd-,dd-,

Pages 3/4 3-28 and 3/4 3-29 have been DELETED.

The next page is 3/4 3-30.

ST.

LUGIE - UNIT 1

3/4 3-27 Amendment No. )P,135

3/4.3 INSTRUMENATION BASES 3 4.3.1 and 3 4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES ESF INSTRUMENTATION The OPERABILITY of 'the protective and ESF instrumentation systems and bypasses eg'sure that 1} the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combi-nation thereof reaches its setpoint,

2) the specified coincidence logic is maintaihed,

3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-ditions.

The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.

The periodic surveillance tests per-formed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies pro-vides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response

time may be demonstrated by any series of sequential, over-lapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response

'time verification may be demonstrated by either 1} in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

The Safety Injection Actuation Signal (SIAS) provides direct actuation of the Containment Isolation Signal (CIS) to ensure containment isolation in the event of a small break LOCA.

3 4.3.3 MONITORING INSTRUMENTATION 3 4.3. 3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that

1) the radiation levels are continually measured in the areas served ST.

LUCIE - UNIT 1

8 3/4 3-1 Amendment No.

27~

37

INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION (Continued) by the individual channels; and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient infor-mation is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations ef Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," December 1980 and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

3 4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.'

4.3.3.3 DELETED 3 4.3.3.4 tlETEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that:

sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radio-active materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs,"

February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

ST.

LUGIE - UNIT 1

B 3/4 3-2 4

Amendment No. 5-9; 135

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 FLORIDA POWER

& 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. 74 License No. NPF-16 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 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; B.

The facility will operate in conformity with the application, the

'rovisions 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, 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 t'o read as follows:

2.

Technical S ecifications 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 74

, are hereby incorporated in the license.

The licensee shall operate the facili'ty 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 David B. Matthews, Director Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 25, 1995

ATTACHMENT TO LICENSE AMENDMENT NO.

74 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 V

XXIII 3/4 3-32 thru 3/4 3-34 B 3/4 3-2 Insert Pa es V

XXIII 3/4 3-32 B 3/4 3-2

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3 4. 2 POWER DISTRIBUTION LIMITS PAGE 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 LINEAR HEAT RATE......................................

TOTAL PLANAR RADIAL PEAKING FACTOR F..............

TOTAL INTEGRATED RADIAL PEAKING FACTOR F...........

AZIMUTHAL POWER TILT..................................

DNB PARAMETERS........

3/4 2-1 3/4 2-7 3/4 2-9 3/4 2-13 3/4'2-14 3 4.3 INSTRUMENTATION 3/4.3.

1 REACTOR PROTECTIVE INSTRUMENTATION..........

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................

3/4.3. 3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION........

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1 3/4 3-11 3/4 3-24 INCORE DETECTORS.............................

. 3/4 3-30 METEOROLOGICAL INSTRUMENTATION........................ 3/4 3-35 REMOTE SHUTDOWN INSTRUMENTATION....................... 3/4 3-38 ACCIDENT MONITORING INSTRUMENTATION................... 3/4 3-41 LOOSE-PART DETECTION INSTRUMENTATION.................. 3/4 3-47 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............. 3/4 3-53 3/4.3.4 TURBINE OVERSPEED PROTECTION..........................

3/4 3-60 3 4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION...........................

HOT STANDBY...........................................

HOT SHUTDOWN..........................................

COLD SHUTDOWN (LOOPS FILLED)...

COLD SHUTDOWN (LOOPS NOT FILLED).............

3/4,4-1 3/4 4-2 3/4 4-3 3/4 4-5 3/4 4-6 ST.

LUCIE - UNIT 2 Amendment No.~~ 74

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LIST OF TABLES INDEX TABLE 1.2

2. 2-1 FREQUENCY NOTATION........................................

OPERATIONAL MODES REACTOR. PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITSe

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PAGE 1-8 1-9 2-4 3.1-1

3. 2-1 3 ~ 2 2 3.3-1 3.3-2 4.3-1 3 ~ 3 3 3.3-4 3.3-5 4.3-2 3.3-6 4.3-3 MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION FOR ST. LUCIE-2.................................

3/4 1-1?

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D DNB MARGIN LIMITS.........................................

3/4 2-11 3/4 2-15 REACTOR PROTECTIVE INSTRUMENTATION........................ 3/4 3-2 ELETfD ~ ~ ~

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D REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................

3/4 3-8 ENGINEERED SAFfTY FEATURES ACTUATION SYSTEM INSTRUMENTATION...........................................

3/4 3-12 ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM INSTRUMENTATION TRIP VALUES...............................

3/4 3-17 ELETf Do

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D ENGINEfRED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-22 RADIATION MONITORING INSTRUMENTATION...................... 3/4 3-25 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................

3/4 3-28 3.3-8 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION.............. 3/4 3-36 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-37 ST.

LUCIE-UNIT 2 XXIII Amendment No. ~ +i 74

INSTRUMENTATION SURVEILLANCE RE UIREMENTS (Continued 3 ~

Monitoring the AZIMUTHAL POWER TILT, or 4.

Calibration of the Power Level Neutron Flux Channels.

b.

At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.

The neutron detectors shall be calibrated prior to installation in the reactor core.

ST.

LUCIE - UNIT 2 3/4 3"31

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Pages 3/4 3-33 and 3/4 3-34 have been DELETED.

The next page ls 3/4 3-35.

ST.

LUGIE - UNIT 2 3/4 3-32 Amendment No. 74

3/4.3'NSTRUMENTATION BASES 3/4.3. 1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEEREO SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION The OPERABILITY of the reactor protective and Engineered Safety Features Actuation Systems.'instrumentation and bypasses ensure that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.

The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original

'design standards.

The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective ahd ESF action function associated with each channel is completed within the time limit assumed in the safety analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response

time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time verification may be demonstrated by either (1) in place, onsite, 'or offsite test measurements or (2) utilizing replacement sensors with certified response times.

The Safety Injection Actuation Signal (SIAS) provides direct actuation of the Containment Isolation Signal (CIS) to ensure containment isolation in the event of a small break LOCA.

3/4. 3. 3 MONITORING INSTRUMENTATION 3/4. 3. 3. 1 RAOIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:

(1) the radiation levels are continually measured in the areas served by the ST.

LUCIE - UNIT 2 B 3/4 3"1

INSTRUMENTATION BASES individual channels; and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1'.97, "Instrumentation for Light-Mater-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," December 1980 and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980..

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4. 3, 3. 3 DELETED 3/4. 3. 3. 4.

METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to

'valuate the need for initiating protective measures to protect the health and safety of the public.

3/4.3.3.5 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION The OPERABILITY of the remote shutdown system instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.

The OPERABILITY of the remote shutdown system instrumentation ensures that a fire will not preclude achieving safe shutdown..

The remote shutdown system instrumentation, control circuits, and transfer switches are independent of areas where a fire could damage systems normally used to shut down the reactor.

This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

ST.

LUCIE " UNIT 2 B 3/4 3"2 Amendment No. 74