ML20042G028
| ML20042G028 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/27/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042G029 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9005110011 | |
| Download: ML20042G028 (7) | |
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION c
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WASHING TON. O. C. 20666
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- q TENNESSEd VALLEY AUTHORITY DOCKET NO, 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licenseo)datedJanuary 12, 1990, 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.
TI'e facility will operate in conformity witL the application, the provisions of the Act, and the rules and regulations of the Comission; e
C.
There'is reasonable assurance (1) that the activities authorized by
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this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in ecmpliance 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 Comission's regulations and al' spplicable requirements have been satisfied.
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2.
Accordingly, the. license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amenoment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
1 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, are hereby incorporated in the e
license. The licensee shall operate the facility in accordance with the Technical Specifications, j
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzanne Black, Assistant Director for Prctects TVA Projtsts Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 27,.1990
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.136 FACILITY OPERATING LICENSE NO. OPR-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 2-6 2-6 f
B 2-3 S 2-3*
B 2-4 8 2-4 3/4 3-5 3/4 3-5 i
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. TABLE 2.2-1 (Continued) y, E8
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REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS-5 z
FUNCTIONAL UNIT
_ TRIP SciPOINT All0WABLE VALUES czZ
- 13. Steam Generator Water 3 18% of narrow range instrument 3 17% of narrow'ranga instrument
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Level--Low-Low span-each steam generator span-each steam generator g
- 14. Steam /Feedwater Flow
< 40% of full steam flow at
< 42.5% of full steam flow at Mismatch and Low Steam liATED THERMAL POWER coincident
~ RATED THERMAL POWER coincident Generator Water Level with steam generator water level with steam generator water level 2 25% of narrow range instru-2 24.0% of narrow range instro-ment spaa--each steam generator ment span--each steam generator
- 15. Undervoltage-Reactor 1 5022 volts each bus 1 4739 volts-each bus Coolani. Pumps
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- 16. Underfrequency-Reactor 1 56.0 Hz - each bus 1 55.9 itz each bus Coolant Pumps
- 17. Turbine Trip A.
Low Trip System 3 45 psig 1 43 psig Pressure B.
Turbine Stop Valve 1 1% open 3 1% open Closure
- 18. Safety Injection Input Not App!icable Not Applicable from ESF
-5%
- 19. Intermediate Range Neutron
> 1 x 10 of RATED
> 6 x 10~
of RATEG g
Flux - (P-6) Enable Block THERhAL POWER THERMAL POWER 3
Source Range Reactor Trip 2
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- 20. Power Range Neutron Flux
< 10% of RATED
< 11% of RATED (not P-10) Input to Low Power THERMAL POWER THERMAL POWER y
5 Reactor Trips Block P-7 c,
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$AFETY LIMITS t
BASES Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip capability.
Power Range, Neutron Flux The Power Range, Neutron Flux channel high setpoint provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.
The low set point provides redundant protection in the power range for a power excursion beginning from low power.
The trip associated with the low setpoint may be manually bypassed when P-10 is active (two of the four power range channels indicate a power level of above approximately 10 percent of RATED THERMAL POWER) and is auto-matica11y reinstated when P-10 becomes inactive (three of the four channels indicate a power level below apprcximately 9 percent of RATED THERMAL POWER).
Power Range, Neutron Flux, High Rates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of rod ejection events from any power level.
5pecifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power.
The Power Range Negatise Rate trip provides protection to ensure that the minimum DNBR is maintained above 1.30 for control rod drop arr4 dents.
At high power a single or multiple rod drop accident could cause local flux peaking which, I
'when in conjunction with nuclear power being maintained equivalent to turbine power by action of the automatic rod control system, could cause an unconserva-tive local DNBR to exist.
The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rods.
Intermediate and Source Range, Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup.
These trips provide redundant protec-tion to the low setpoint trip of the Power Range, Neutron Flux channels.
The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active.
The Intermediate SEQUOYAH - UNIT I B 2-3 Revised 08/18/87
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' SAFETY LIMITS BASES Range Channels will initiate a reactor trip at approximately 25 percent of RATED THERMAL POWER unless manually blocked when P-10 becomes active.
No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specifier.+. ion to enhance the overall reliability of the Reactor Protection System.
Overtemperature Delta T
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The Overtemperature Delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors (about 4 seconds),
and pressure is within the range between the High and Low Pressure reactor trips.
This setpoint includes corrections for axial power distribution, changes in density and heat capacity of water with temperature and dynamic
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compensation for piping delays from the core to the loop temperature detec-tors.
With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.
Operation with a reactor coolant loop out of service below the 4. loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint ar.d associated trip will prevent DNB during 3 loop operation exclusive of the Overtemperature Delta T setpoint.
Three loop operation above the 4 loop P-8 setpoint is permissible after resetting the K1, K2 and K3 inputs to the Overtemperature Delta T channels and raising the P-8 setpoint to its 3 loop value~
In this moda of operation, the P-8 inter-lock and trip functions as a High Neutron Flux trip at the reduced power level.
Overpower Delta T The Overpower Delta T reactor trip provides assurance of fuel integrity, e.g., no melting, under all possible overpower cenditions, limits the required range for Overtemperature Delta T protection, and provides a backup to the High Neutron Flux trip.
The setpoint includes corrections for changes in density and heat capacity of water with temperature, and dynamic compensation for piping delays from the core to the loop temperature detectors.
No credit was taker for operation of this trip in the accident SEQUOYAH - UNIT 1 B 2-4 Amendment No.136
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-r TABLE 3.3-1 (Continued)
TABLE NOTATION With the reactor tri~p system breakers in the closed position and the conttol rod drive system capable of rod withdrawal, and fuel in the reactor vessel.
The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.
- The provisions of Specification 3.0.4 are not applicable.
- ource Range outputs may be disabled above the P-6 (Block of Source L
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Range Reactor Trip) setpoint.
ACTION STATEMENTS ACTION 1 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STAND 3Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceec provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped conditien within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1.1.
c.
The QUADRANT POWER TILT RATIO is monitored in accordance with Technical Specification 3.2.4.
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l SEQUOYAH - UNIT 1 3/4 3-5 Amendment No. 47,135,136