ML20028H005
| ML20028H005 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/02/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028H006 | List: |
| References | |
| NUDOCS 9010050146 | |
| Download: ML20028H005 (7) | |
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UNITED STATES 9
NUCLEAR REGULATORY COMMISSION
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T E N N E S S E E V AL L EY,,A,U,T H,0,R I,T,Y, 00,C,K,E,T,,NO. 50-328 SE000Y AH NUC,L,E,A,R,,P,L,A,N,T,,,,l4!J,T,,2 d'.EF,DF,EF,T,,T,0, f,A,C,1,LJ T Y OP E R ATJ,H G L I C E N S E Amendo.ent tlo. 129 License No. DPR-79 1.
The Nuclear Petulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee).datedJanuary 12, 1990, corplies with the standards and requirencnts of the Atowiic Energy Act of 1954, as amended (the Act),
and the Consission's rules and regulaticos set forth in 10 CFR Chapter I; B.
The facility will operate in cerforrity with the application, the provisions cf the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this an4ndment can be conducted without endangering the health and safety of the public, and (ii) that such activitics will be conducted in conplience with the Coneission's regulations; D.
The issuance of this amendment will nct be inimical to the comron defense and security or to the health and safety of the public; and E.
The issuance of this anwrdrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9010050146 901002 PDR ADOCK 05000328 P.
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Accorr'ingly, the license is arnended by changes to the Technical I
Specifications as indicated in the attachtient to this license anendtncnt and paragraph 2.C.(2) of facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Arendunt No.129, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificatiens.
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This license amendier.t is effective as of its date of issuance.
FOR THE !WCLEAR RECULATORY COMitlSSION e
L Frederick J. Heb en, Director Project Directorate 11-4
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Divisioti cf Reactor Projects - 1/II
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Office of b'uclear Reactor Regulation
Attachment:
Changes to the lechnical 1
1 Specifications i
Date of Issuance: October 2, 1990 J
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ATTACHMEN,T,,T,0,,L,l_CQSE, AMENCLENT, N,0,., J,29 FACILITY OPERATING LICENSE NO._DPR-79 00CKET NO. 50-328 Ptvise the Appendix A Technical Specifications by removing the pages t
ider.tified below and inserting the erclosed pages. The revised pages are identified by tk captior.ed en,endrert nurber ar.d cor.tain marginal lines indicating the area of char;ge. Overleaf pages' are provided te reintain docurent con.pleteriess.
PEMOVE INSERT 2-6 2-6 B 2-3 B 2-3*
B 2-4 B 2-4 3/4 3-5 3/4 3-5 i
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TABLE 2.2-1 (Continued)
'E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS SE FUNCTIONAL UNIT TRIP SETPOINT ALLOWA8LE VALUES
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- 13. Steam Generator Water
> 18% of narrow range instrument
> 17% of narrow range instrument q
Level--Low-Low span-each steam generator span-each steam generator
- 14. Steam /Feedwater Flow
< 40% of full steam flow at
< 42.5% of full steam flow at Mismatch and Low Steam
-RATED THERMAL POWER coincident RATED THERMAL POWER coincident Generator Water Level with steam generator water level with steam generator water level
> 25% of narrow range instru-
> 24% of narrow range instru-ment span--each steam generator ment span--each steam generator
- 15. Undervoltage-Reactor
> 5022 volts-each bus
> 4739 volts-each bus Coolant Pumps
- 16. Under'requency-Reactor
> 56 Hz - each bus
> 55.9 Hz each bus ry Coolant Pumps e
- 17. Turbine Trip A.
Low Trip System
> 45 psig
> 43 psig Pressure B.
Turbine Stop Valve
> 1% open
> 1% open Closure
- 18. Safety Injection input Not Applicable.
Not Applicable from ESF
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- 19. Intermediate Range Neutron
> 1 x 10 % of RATED
> 6 x 10 % of RATED 2
Flux, P-6, Enable Block THERMAL POWER THERMAL POWER y
Source Range Reactor Trip no 5
- 20. Power Range Neutron Flux
$ 10% of RATED 1 11% of RATED THERMAL POWER (not P-10) Input to Low-THERMAL POWER z?
Power Reactor Trips y
Block P-7 5
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- 2. 2 LIMITING SAFETY SYSTEM SETTINGS i
BASES i
Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip capability.
1 Power Range, Neutron Flux The Power Range, Neutron Flux channel high setpoint provides reactor core protection againi,t reactivity excursions which are too rapid to be protected i
by temperature and pressure protective circuitry.
The low set point provides i
redundant protection in the power range for a power excursion beginning from low power.
The trip associated with the low setpcint 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 approximately 9 percent of RATED THERMAL POWER).
Power Range, Neutron Flux, High Rates
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The Power Range Positive Rate trip provides protection against rapid flux
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increases which are characteristic of rod ejection events from any power level.
Specifically, this trip complements the Pruer Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power.
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.The Power Range Negative Rate trip provides protection to ensure that the minimum DNBR is maintained above 1.30 for control rod drop accidents.
At high power a single or multiple rod drop accident could cause local flux peaking which, when in conjunction with nuclear power being maintained equivalent to turbine power by action of the automatic rod control system. could cause l.
an unconservative 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 I
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The Intermediate and Source Range, Nuclear Flux trips provide reactor j
core protection during reactor startup.
These trips provide redundant protec-tiontothelowsetpointtripofthePowerRange,NeutronFlux4hannels.
The Source Range Channels will initiate a reactor trip at about 10 counts per l
second unless manually blocked when P-6 becomes active.
The Intermediate SEQUOYAH - UNIT 2 B 2-3 Revised 08/18/87 Bases Change Amendment 129
l LIMITING SAFETY SYSTEM SETTINGS BASES Intermediate and Source Range, Nuclear Flux (Continued)
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 Inter-mediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.
Overtemperature AT 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 frr-the core to the temperature detectors (about 4 seconds),
I 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 compensation for piping delays from the core to the loop temperature detectors, 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 set point modification because the P-8 setpoint and 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 mode of operation, the P-8 interlock and trip functions as a H'igh Neutron Flux trip at the reduced power level.
Overpower AT The Overpower delta T reactor trip provicies assurance of fuel integrity, e.g., no melting, under all possible overpower conditions, 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 taken for operation of this trip in the accident analyses; however, its functional capability at the specified trip setting is required by this specification to enhance the overall reliability of the Reactor Protection System.
SEQUOYAH - UNIT 2 B 2-4 Amendment No.129
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TABLE 3.3-1 (Cortinued)
TABLE NOTATION AWith the reactor trip system breakers in the closed position, the control 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 S
Range Reactor Trip) setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels 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 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/or open the reactor trip breakers.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition 1
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.
t SEQUOYAH - UNIT 2 3/4 3-5 Amendment No. 39, 122, 129
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