ML17340A648
| ML17340A648 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/19/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17340A649 | List: |
| References | |
| NUDOCS 8101300239 | |
| Download: ML17340A648 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASMINGTON, D. C. 20555 FLORIDA POINTER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
DPP,-31 l.
The A.
B.
C.
D.
Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Florida Power and Light Company (the licensee) dated January 31, 1979 as supplemented on September 26,
- 1980, complies with the standards and requirements.
of the Atomic Eriergy Act of 1954, as aIIIended (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'pub'lie',
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 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.
81 01 30 03 39
2..Accordingly, the licdnse 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:
(B)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62
, 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 Date o
Issuance:
December 19, 1980 Steven A.
- arga, C ie Operating Reactor ranch gl Division of Licenying
UNITED STATES NUCLEAR REGULATORYCOMMlSSION lSACHlNGTOfV, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AHENDtIENT TO FACILITY OPERATING LICENSE Amendment No.
53 License No.
DPR-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Povrer and Light Company (the licensee) dated January 31, 1979 as supplemented on September 26,
- 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) arid 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 Commis'sion's regulations and all applicable requirements have been satisfied.
20 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. 53, 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 ev n
. Varga, C
ef Operating Reactors ranch 0'1 Division of Licensing
Attachment:
.Changes to the Technical Specifications Date of Issuance:
December 19, 198O
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
62TO FACILITY OPERATING LICENSE NO.
DPR-31 AMENDMENT NO.
53TO FACILITY OPERATING LICENSE NO.
DPR-41 DOCVET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
i through v
1-6 Insert Pa es i,through vi 1-6
TABLE OF CONTENTS Section 1.0 1.1 1.2
'.3 1.4 1.5 1.6 1.7 1'. 8 1 9'
].10
- l. 11
- l. 12
- 1. 13
- 1. 14
- l. 15
- l. 16
- 1. 17 2.0 2.1 2.2 2 ~ 3 3.0 3.1 3.2.
'3. 3 DEFINITIONS Title Safety Limits Limiting Safety Systems Settings Limiting Conditions for Operation Operable Containment Integri ty Protective Instrumentation Logic Instrumentation Survei'I lance Shutdown Power Operation Refueling Operation Rated Power (R.P.)
Thermal Power Design Power (Deleted)
Power Tilt Interim Limits Low Power Physics Tests SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Saf ety Limit, Reactor Core Safety Limit, Reactor Cool a nt System Pressure Limiting Safety System Settings, Protective Instrumentation LIMITING COND ITIONS FOR OPERATI OH Reactor Coolant System Operational.
Components Pressure-Temperature Limits Leakage Maximum Reactor Coolant Activity Peactor Coolant Chemistry DNB Parameters Control Rod and Power Distribution Limits Control Rod Insertion Limits Misaligned Gontrol Rod Rod Drop Time Inoperable Control Rods
'Control Rod Position Indication Power Distribution Limits I'-Core Instrumentation Axial Offset Alarms Containment
~Pa e
1-1 1-1l-l 1-1 1-2 1-2 1-3 1-3 1-4 1-4 1-4 1-4 1-4 1-5 1-5 1-6 1-6
- 2. 1-1
- 2. 1-1 2.2-1 2.3-1
- 3. 1-1
- 3. 1-1 3.1-1 3.1-2
- 3. 1-4 3.1-5 3.1-6
- 3. 1-7
- 3. 2-1 3.2-1 3.2-2 3.2-2 3.2-2 3.2-3 3.2-3 3.2-7 3.2-8 3.3-1 Amendments 62 8
53
TABLE OF CONTENTS (Continued)
Section 3.4 3.5 3.6 3.7 3.8
';,3. 9
- 3. 10
- 3. 11
- 3. 12
- 3. 13
- 3. 14
- 3. 15 4.p 4.1 4.2 4.3 4,4
. 4.5 4.6 4.7 4.8 9
Title Engineering Safety Features Safety Injection and RHR Systems Emergency Containment Cooling Systems Emergency Containment Filtering System Component,Cooling System Intake Cooling Mater System Instrumentation Chemical and Volume Control System Electrical Systems Steam Power Conversion Systems Radioactive Materials Release Liquid Wastes Gaseous Wastes Containerized Wastes Ref uel i ng Miscellaneous Radioactive Materials Sources C ask Ha ndl i ng Shock Suppressors (Snubbers)
. Fire Protection Systems Overpressure Mitigating System SURVEILLANCE REQUIREMENTS Operational Safety Review Reactor Coolant System In Service Inspection Reactor Coolant System Integrity Containment Tests Integrated Leakage Rate Test - Post Operational Local Penetration Tests Report of Test Results Isolation Valves Residual Heat Removal System Tendon Surveillance End Anchorage Concrete Surveillance Liner Surveillance Sa fety Inject ion Emergency Containment Cooling Systems Emergency Containment Filtering and Post Accident Containment Vent Systems Emergency Power System Periodic Tests Main Steam Isolation Valves Pa(ac 3.4-1 3.4-1 3.4-3 3.4-4 3.4-4 3.4-5 3.5-1
- 3. 6-1
- 3. 7-l 3.8-1 3.9-1 3.9-1 3.9-3 3.9-5 3.10-1 3.11-1 3.12-1
- 3. 13-1
- 3. 14-1
- 3. 15-1
- 4. 1-1 4.1-~
4e I 4.4-1 4.4-1 4.4-2 4.4-2 4.4-3 4.4-3 4,4 4
4.4-6 4.4-7 4.5-1 4.6-1 4.7-1 4.8-1 4.9-1 Amendments, 62 5 53
TABLE OF CONTENTS (Continued)
Section 4.10 4.11 4-12 4.13 4.1<
- 4. 15
- 4. 16 5.0 5.1 5..2 5;3 5.4.
6.0 6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.S 6.9 6.10
- 6. 11
- 6. 12
- 6. 13 82.1 82.2 82.3 83.1 B3. 2 83.3 Q3.4 Title Auxiliary Feedwater System
- Reactivity Anomalies Environmental,.Radi ation Survey Radioactive Materi ls Sources Surveillance Shock Suppressors
(~nubbers)
Fire Protection Systems Overpressure Mitigating System DESIGN FEATURES Site Reactor.
Containment Fuel Storage ADMINISTRATIVE COHTROLS Responsibility Organization Faci 1 ity Staff qua 1 ificat ions Training Reviewer and Audit Reportable Occurrence Action Safety Limit Violation Procedures Reporting Requirements Record Retention Radiatioi Protection Program lligh Radiation Area Environmental Ilualification Bases for Safety Limit, Reactor Core Bases for Safety Limit, Reactor Coolant System Pressure Bases for Limiting Safety System Settings, Protective Instrumentatior.
Bases for Limiting Conditicns for Operation, Reactor Coolant System Bases for Lim'ting Conditions for Operation, Control and Power Distribution Limits Bases for Lim ting Conditions for Operation, Contain e
~
Bases foi. Limiting Conditions for Operation, Eng',neered Safety Features
~Pa e
- 4. 10-1 4.11-1
- 4. 12-1
- 4. 13-1
- 4. 14-1
- 4. 15-1
- 4. 15-1
- 5. 1-1 5.1-1
- 5. 2-1
- 5. 3-1 5.4-1 6-1 6-1 6-1 6-5 6-5 6-6 6-14 6-14 6-14 6-16 6-27 6-29 6-29 6-30
- 82. 1-1 82.2-1 82.3-1
. 83. 1-1 83.2-1 83.3-1 83.4-1 Amendments 62 8
53
TABLE OF CONTENTS (Continued)
Section 83.5
- 83. 6 83 7
83.8'3.
9
- 83. 10
- 83. 11
- 83. 12
- 83. 13
- 83. 14
- 83. 15 84-1 84.2
- 84. 3
- 84. 4
- 94. 5
- 84. 6 84.7 84.8
- 84. 9 B4. 10 84.11
- 84. 12
- 84. 13
- 84. 14
- 84. 15 Title Bases for Limiting Conditions for Operation, Instrumentation Bases for Limiting Conditions for Operation, Chemical and Volume Control System Bases for Limiting Condition for Operation, Electrical Systems Bases for Limiting Conditions for Ozeration, Steam and Power Conversion Systems Bases fear Limiting Conditions for Operation, Radioactive Materials Release
'Bases for Limiting Conditions for Operation, Refue ling Bases for Limiting Conditions for Operation, l~iseel la neous Radi oact ive tiateri a 1 Sources Bases or Limiting Conditions for Operation, Cask Handling Bases for Limiting Conditions for Operation, Hydraulic Snubbers Bases for Fire Protection System Bases for Limiting Conditions of Operation, Overpressure Mitigating System Bases for Operational Safety Review Bases for Reactor Coo'lant System In-Service Inspection Bases for Reactor Coolant System Ir."egrity Bases for Containment Tests Bases for Safety Injection Tests Bases for Erergency Containment Coo'ling System Tests Bas s for Emergency Containment Filtering and Post Accident Con:ainment Venting Systems Tests Bases for Emergency Power System Periodic Tests Bases for Hain Steam Isolation Valve Tests Bases for Auxiliary Feedwater System Tests Bases for Peac:ivity Anomalies Bases for Envi'onhhhehi'.al Radia"..ion Survey Bases for Fire Protection Systems Bases for Hydraulic Snubbers Bases for Surveillance Requirements, Overpressure llitigating System
~Pa e
- 83. 5-1 83.6-1 83.7-1 83.8-1 83.9-1
- 83. 10-1
- 83. 11-1
- 83. 12-1
- 83. 13-1
- 83. 14-1 83.15-1
- 84. 1-1 84.2-1 84.3
- 84. "-1
- 84. 5-1 84.6-1 84.7-1 84.8-1 84.9-1
- 84. 10-1
- 84. 11-1 B4. 12-1
- 84. '3-1
- 84. l4-1
- 84. 15-1 1v Amendments 62 8
53
LIST OF TABLES Table Title
- 3. 5-1
- 3. 5-2
- 3. 5-3
- 3. 5-4
- 3. 13-1
- 3. 14-1 4.'l - l
'.1-2
- 4. 2-1
- 4. 12-1
- 4. 12-2 6.2-1 Instrument Operating Conditions for Reactor Trip Engineering Safety Features Actuation Instrument Operating Conditions for Isolation Functions, Engineered Safety Feature Set Points Safety Related Snubbers Fire Detection System
'ini'mum Frequencies for Checks, Cali brations and Test of Instrument Channels Minimum Frequencies for Equipment and Sampling Tests Reactor Coolant System In-Service Inspection Schedule Ope'rational Environmental Radiological Surveillance Program Operational Environmental Radiological Surveillance Program Types of Analysis Operating Personnel Amendments 62
& 53
e LIST OF FIGURES
~Fi ere
- 2. 1-1 2-1-1 a
- 2. 1-lb
- 2. 1-2.
- 3. 1-1 a.
- 3. 1-lb
- 3. 1-1 c 3..1-1 d
- 3. l-2
- 3. 1-2c 3.1-2d
- 3. 2-1 3 2-la 3.2-lb 3.2-1c 3.2-2 3.2-3 3.2-4
- 4. 12-1
- 6. 2-1 6.2-2 83.1-1 83.1-2 83.2-1 83.2-2 Title Peactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation Reactor Core Ther.":al and Hydraulic Safety Limits, Three
-Loop Operation Reactor Core Thermal and Hydraul
'Safety Limits, Two Looo Operation Reactor Coolant System Heatup and Cooldown Pressure Limits Reactor Coolant System Heatup and Cooldown Pressure Limits Reactor Coolant System Heatup and Cooldown Pressure Limits Reactor 'Coolant System Heatup and Cooldown Pressure Limits Radiation Induced Increase in Transition Temperature for A302-8 Steel Radiation Induced Increase in Transition Temperature for A302-8 Steel Radiation Induced Increase in Transition Temperature for A302-8 Steel Control Group Insertion Limits for Unit 4; Three Loop Operation Control Group Insertion Limits for Unit 4, Two Loop Operation Control Group Insertion Limits for Unit 3, Three Loop Operation Control Group Insertion Limits for Unit 3, Two Loop Operation Required Sh'utdowm Margin Hot Channel Factor Normalized Operating Envelope Maximum Al.vwable Local K'H/FT Sampling Locations Offsite Orgahization Chart Plant Organization Chart Effect of Fluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to 550'F Temperature Fast Neutron Fluence (E>lNEV) as a function of Effective Full Power Years Target Band on Indicat.d Flux Difference as a Function of Operating Power Level Permissible Operating
'..and on Indicated Flux Difference as a
Function of Burnup (Typical) v1 Amendments 62 5 53
1.16 REACTOR COOLANT PUl)PS The reactor shall not be operated with less than three. reactor coolant pumps in operation.
1. 1 7 LOW PO)sE R PHY S ICS TESTS Lo<<power p ysic h si s tests
- are tes.s below a nominal 5" of rated power which measure fundamental characteristics of the reactor core and related instrumentation.
1-6 A",i;endrrents 62 5 53
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