ML20248B809
| ML20248B809 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/01/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248B812 | List: |
| References | |
| NUDOCS 8906090176 | |
| Download: ML20248B809 (17) | |
Text
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4 UNITED STATES
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j (. %I NUCLEAR REGULATORY COMMISSION y
W ASHINGTON, D. C. 20555 e-e
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT t AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.116 License No. DPR-77 1.
lee Nuclear Regulatory Commission (the Comission).has found that:
A.
The application for amendment by Tennessee Valley Authcrity (the licensee)datedJanuary 25, 1984, complies with the standards and requirements of the Atomic' Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; C.
There is reasonable assurance' (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
8906090176 890601 PDR ADOCK 05000327 P
e
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.116, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
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1:ndan^nW BThek, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 1,1989 9
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c ATTACHMENT TO LICENSE AMENDMENT NO. 116 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT v
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Vi vi vii vii viii viii 3/4 4-28 8 3/4 4-3 B 3/4 4-13*
B 3/4 4-14 I
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
SECTION' PAGE
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3/4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference......................................
3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor..............................
3/4 2-5 3/4.2.3
.RCS Flowrate and R........................................
3/4-2-10 3/4.2.4 Quadrant Power Tilt Ratio..................................
3/4 2-15 3/4.2.5-DNB Parameters............................................
3/4 2-18 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......................
3/4 3-1
'3/4.3.2' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........................................
3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Moni toring Instrumentation.....................
3/4 3-39 Movable Incore Detectors..................................
3/4 3-43 Seismic Instrumentation...................................
3/4 3-44 Meteorological ~ Instrumentation...................'.........
3/4 3-47 Remote Shutdown Instrumentation...........................
3/4 3-50 Chlorine Detection Systems (Deleted) 3/4 3-54 Accident Monitoring Instrumentation......................
3/4 3-55 Fire Detection Instrumentation......................
3/4 3-58 Radioactive Liquid' Effluent Monitoring Instrumentation....
3/4 3-69 Radioactive Gaseous Effluent Monitoring Instrumentation...
3/4 3-74 SEQUOYAH'- UNIT 1 V
Amendment No. 62
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'INDEX LIMITING CONDITIONS FOR'0PERATION AND SURVEILLANCE REQUIREMENTS' q
SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM
?3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT. CIRCULATION Startup and Power 0peration...............................
3/4 4-1 Hot Standby...............................................
3/4 4-la Shutdown..................................................
3/4 4-2 a
13/4.4.2 SAFETY VALVES - SHUTD0WN..................................
3/4 4-3 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety Valves -
Operating.................................
3/4 4-4 Relief Valves - Operating.................................
3/4 4-4a 3/4.4.4 PRESSURIZER...............................................
3/4 4*5 3/4.4.5~
STEAM GENERATORS..........................................
3/4 4-6
' 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.................................
3/4 4-13 Operational Leakage.......................................
3/4 4-14 3/4.4.7 CHEMISTRY.................................................
3/4 4-16 3/4.4.8.
SPECIFIC ACTIVITY.........................................
3/4 4-19 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System....................................
3/4 4-23 Pressurizer.................................
3/4 4-26
' 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components.....................
3/4 4-27 p
3/4.4.11 REACTOR COOLANT SYSTEM VENTS...........
3/4 4-28 SEQUOYAH - UNIT 1 VI Amendment No.
116
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i INDEX-
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE s
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4 5.1
. ACCUMULATORS ColdlegInjectionAccumulators...........................
3/4 5 UpperHeadInjectionAccumulators..........................
3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T,yg greater thanlor equal to 350*F.....
3/4 5-5 3/4.5.'3 ECCS SUBSYSTEMS - T,yg less than 350'F....................
3/4 5-9 3/4.5.4 BORON INJECTION SYSTEM Boron'InjectionTank......................................
3/4 5-11 Heat Tracing...............................................
3/4 5-12 3/4.5.5 REFUELING WATER STORAGE TANK..............................
3/4 5-13
.3/4.6' CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.....................................
3/4 6-1 Containment Leakage.......................................
3/4 6-2 Containment Air Locks.....................................
3/4 6-7.'
Internal Pressure.........................................
3/4 6-9 Air Temperature...........................................
3/4 6-10 Containment Vessel Structural Integrity...................
3/4 6-11 Shield Building Structural Integrity......................
3/4 6-12 Emergency Gas Treatment System (Cleanup Subsystem)........
3/4 6-13 Containment Ventilation System..........
3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System..................................
3/4 6-16 Lower Containment Vent Coolers................
3/4 6-16b SEQUOYAH - UNIT 1 VII Amendment No. 67,69 116
l Condensate Storage Tank..............
3/4 7-7 i
Activity..................................................
3/4 7-8 1
l Main Steam Line Isolation Va1ves..........................
3/4 7-10 1
3/4.7.2 STEAM GENERATOR PRESSURE /TEMPERAToiE LIMITATION...........
3/4 7-11
. 3/4.7.3 COMPONENT COOLING WATER SYSTEM..
3/4 7-12 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM Essential Raw Cooling Water System.......................
3/4 7-13 SEQUOYAH - UNIT 1 VIII Amendment No.116 a
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.3/4.4.11 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11' Two Reactor Coolant System Vent (RCSV) paths shall be OPERABLE.
- APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
With only one RCSV path OPERABLE, STARTUP and/or POWER OPERATION may a.
continue provided the inoperable path is maintained closed with power removed from the valve actuators; restore the inoperable path to OPERABLE status within 30 days; or be in HOT STANDBY within E hours and 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 />, b.
With no RCSV path OPERABLE, restore at least one path 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.11 Each RCSV path shall be demonstrated OPERABLE at least once per 18 months by:
a.
Verifying that the upstream manual isolation valve is locked in the open position for the head vent.
b.
Operating each remotely controlled valve through at least one cycle from the control room, and Verifying flow through the RCSV paths during venting.
c.
T
- Use of Power Operated Relief Valves (PORV's) with associated block valves is considered one system.
Closure of one or both block valves does not make the vent path inoperable pr;,ided the valve (s) can be opened.
SEQUOYAH - UNIT 1 3/4 4-28 Amendment No.
116
REACTOR COOLANT SYSTEM BASES thermal stresses and different Ky 's for do not offset each other and the hressuresteady-state and finite heatup rates temperature curve based on steady-state-conditions no longer represents a lower bound of all similar curves for finite heatup rates when the 1/4T flaw is considered.
Therefore, both cases have to be analyzed in order to assure that at any coolant temperature the lower value of the allowable pressure calculated for steady-state and finite heatup rates is obtained.
The second portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4T deep outside surface flaw is assumed.
Unlike the situation at the vessel inside surface, the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and thus tend to reinforce any pressure stresses present.
These thermal stresses, of course, are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp. Furthermore, since the thermal stresses, at the outside are tensile and increase with increasing heatup rate, a lower bound curve cannot be defined.
Rather, each heatup rate of interest must be analyzed on an individual basis.
Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced as follows. A composite curve is constructed based on a point-by point comparison of the steady-state and finite heatup rate data.
At any given temperature, the allowcble pressure is taken to be the lesser of the three values taken from the curves under consideration.
The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist such that over the course of the heatup ramp the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.
l Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the respective curves.
Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.
SEQUDYAH UNIT - 1 B 3/4 4-13
REACTOR COOLANT SYSTEM BASFS-3/4.4,10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a (g)(6)(i).
Components of the reactor coolant system were designed prior to issuance of Section XI of the ASME Boiler and Pressure Vessel Code.
These components will be tested to the extent practical within the limitations of the original i
plant design, geometry, and materials of construction of the components.
3/4.4.11 REACTOR COOLANT SYSTEM VENTS The function of the RCS vents is to remove noncondensables or steam from the reactor vessel head and/or pressurizer.
This system is designed to mitigate a possible condition of inadequate core cooling, inadequate natural circulation, or inability to depressurize the RHR System initiated conditions resulting from the accumulation of noncondensable gases in the Reactor Coolant System.
The reactor vessel head vent and the pressurizer vent are 'each designed with redundant safety grade vent paths.
Having either system 0PERABLE or having one path in each system from opposite trains OPERABLE is sufficient to meet the provisions of Specification 3.4.11.
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l SEQUOYAH - UNIT 1 B 3/4 4-14 Amendment No. 116
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/** "'*4,o UNITED STATES
- ! ',,I., ^,k NilCLEAR REGULATORY COMMISSION 1
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WASHINGTON, D. C. 20555 5
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_ TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated Janaury 25, 1984, 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 i
Comission; C.
There is reasonable assurance (1) 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.
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i 2-2.
Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-79 is hereby dmended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 106, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b{ ~
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~
pdzanne Black, Assistant Director for Projects TVA Projects Division l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
(
Specifications 1
Date of Issuance:
June 1, 1989 l
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t ATTACHMENT TO LICENSE AMENDMENT NO. 106 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.- The revised pages.
are identified by the captioned amendment number and contain marginal lines indicating the ared of change. Overleaf pages* are provided to maintain document completeness.
l REMOVE INSERT
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vi vi 3/4 4-34 B 3/4 4-15 i
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INDEX m
LIMITING CONDITI'ONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' SECTION PAGE 3/4.2 ' POWER DISTRIBUTION LIMITS L
AXIAL-FLUX DIFFERENCE.....................................
3/4.2-1 3/4.2.1 3/4.2.2-HEAT FLUX HOT CHANNEL FACT 0R...............................
.3/4 2-4 3/4.2.'3 RCS FLOWRATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT0R............................................
3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATI0.................................
3/4 2-13 3/4.2.5 DNB PARAMETERS............................................
3/4 2-16 3/4.3 INSTRUMENTATION 3/4.'3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......................
3/4 3-1
'3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........................................
3/4'3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................
3/4 3-40 Movable Incore Detectors..................................
3/4 3-44 Seismic Instrumentation.................................
3/4 3-45 Meteorological Instrumentation............................
3/4 3-48 Remote Shutdown Instrumentation...........................
3/4 3-51 Chlorine Detection Systems (Deleted) 3/4 3-55 I
Accident Monitoring Instrumentation.......................
3/4 3-56 Fi re Detection Instrumentation............................
3/4 3-59 Radioactive Liquid Effluent Monitoring Instrumentation....
3/4 3-68 Radioactive Gaseous Effluent Monitoring Instrumentation..
3/4 3-76 i
SEQUOYAH - UNIT 2 V
Amendment No. 54
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,INDEX p
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-SECTION PAGE.
3/4.'4 -REACTOR COOLANT SYSTEM 3 /4. 4.- 1 REACTOR COOLANT LOOPS AND C00LANT' CIRCULATION S'tartup and Power 0peration................................
3/4 4-1 1
Hot Standby...........'...................................
3/4 4-2 Hot Shutdown...............................................
3/4 4-3 Cold Shutdown..............................................
3/4 4-5 3/4.4.2 SAFETY VALVES - SHUTD0WN..................................
3/4 4-6 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety. Valves 0perating...................................
3/4 4-7 Relief Valves 0perating..................................
3/4 4-8 3/4.4.4- ' PRESSURIZER...............................................
3/4 4-9 3/4.4.5 STEAM GENERATORS...........................................
3/4 4-10, 3/4i4.6 REACTOR C0OLANT SYSTEM LEAKAGE Leakage Detection Systems.................................
3/4 4-17 Operational Leaka'ge.......................................
3/4 4-18' 3/4.4.7. CHEMISTRY.'................................................
3/4 4-21 3/4.4.8. SPECIFIC ACTIVITY.........................................
3/4 4-24 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System....................................
3/4 4-28 Pressurizer...............................................
3/4 4-32 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components.....................
3/4 4-33 3/4.4.11 REACTOR COOLANT SYSTEM VENTS..............................
3/4 4-34 SEQUOYAH UNIT 2 VI Amendment No.
106 0
9; REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 Two Reactor Coolant System Vent (RCSV) paths shall be OPERABLE.
- APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
With only one PC5V path OPERABLE,'STARTUP and/or POWER OPERATION may a.
continue provided the inoperable path is maintained closed with power removed from the valve actuators; restore the inoperable path to OPERABLE status within 30 days; or be in HOT STANDBY within 6
. hours and 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 />.
b.
With no RCSV path OPERABLE, restore at least one path 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
SURVEILLANCE REQUIREMENTS 4.4.11 Each RCSV path shall be demonstrated OPERABLE at least once per 18 months by:
a.
Verifying that the upstream manual isolation valve is locked in the open position for the head vent.
b.
Operating each remotely controlled valve through at least one cycle from the control room, and Verifying flow through the RCSV paths during venting.
c.
- Use of Power Operated Relief Valves (PORV's) with associated block valves is considered one system.
Closure of one or both block valves does not make the vent path inoperable provided the valve (s) can be opened.
SEQUOYAH - UNIT 2 3/4 4-34 Amendment No. 106 l
l REACTOR COOLANT SYSTEM BASES 3/4.4.11 REACTOR COOLANT SYSTEM VENTS 1
The function of the RCS vents is to remove noncondensables or steam from the. reactor vessel head and/or pressurizer.
This system is designed to mitigate a possible condition of inadequate core cooling, inadequate natural circulation, or inability to depressurize the RHR System initiated conditions resulting from the accumulation of noncondensable gases in the Reactor Coolant System.
The reactor vessel head vent and the pressurizer vent are each designed with redundant safety grade vent paths. Having either system OPERABLE or having one path in each system from opposite trains OPERABLE is sufficient to meet the provisions of Specification 3.4.11.
SEQUOYAH - UNIT 2 B 3/4 4-15 Amendment No.106