ML19256E588
| ML19256E588 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/18/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256E589 | List: |
| References | |
| NUDOCS 7911080097 | |
| Download: ML19256E588 (5) | |
Text
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UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20555 g
- p
/
ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AIENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 L icense No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated June 20, 1979, complies with the standards dnd 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 Commission; C.
There is reasonable asserance (i) that the activities authorized by this amendment can be conducted without endangering the hea:th dnd sdfety of the public, and (ii) that such activities will be conoucted i.i compliance with the Commission's regulations; U.
The issuance of this amendment will not be inimical to the common defense end security or to the health and safety of the public; dnd E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comuission's regulations and all applicable requirements hdVe been satisfied.
1294 236 7911 080 h
. 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. NPF-2 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment 10. 14, 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 tie date of its issuance.
FOR THE NUC_ EAR REGULATORY COMMISSION
/ /NW/M A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1979 1294 237
ATTACHMENT TO LICENSE AMENDMENT N0.14 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET N0. 5G-348
. Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Corresponding overleaf pages are also provided to maintain document completeness.
Pages 2-5 B2-4 1294 238 FARLEY - UNIT 1 i
t 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the values at which the Reactor Trips are set for each parameter.
The Trip Setpoints have been selected to ensure that the reactor core and reactor coolant system are prevented from exceeding their safety limits. Opera-tion with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that each Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
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 pr:tective 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 '.vhen P-10 is active (two of tha four power range channels indicate a power level of above approximately 10 percent of RATED THERMAL POWER).
Power Range, Neutron Flux, High Rates The Power Range Positive Rate trip prevides protection against rapid flux increases which are characteris+.: of rod ejection events f re, any power level.
Specifically, this trip complements the Power
....,e Neutron Flux High and Low trips to ensure that the criteria are met f3r rod ejection from partial power.
FARLEY - UNIT 1 B 2-3 Jp0
?}g
LIMITING SAFETY SYSTEM SETTINGS BASES 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 an unconservative local DNBR to exist.
The Power Ragne Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rcds.
Intermediate and Source Range, Nuclear Flux The Intermediate and Source Range, Nucle.ar Flux trips provide reactor core protection during reactor startup.
These trips provide redundant protection 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 Intennediate Range Channels will initiate a reactor trip at a current level proportional to approximately 25 percent of RATED THERMAL POWER unless manually blocked when P-10 b-comes 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 use specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.
Overtemperature AT The Overtemperature t>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 changes in density and heat capacity of water with temperc'ure and dynamic com-pensation for piping delays from the core to the loop temperature detectors. With normal axial power distribution, this reactor trip limit is alvays 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.
FARLEY - UNIT 1 B 2-4 Amendment No.14
TABLE 2.2-1 E
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES k
- 1. Manual Reactor Trip Not Applicable Not Applicable
- 2. Power Range, Neutron Flux Low Setpoint - 1 25% of RATED Low Setpoint - 1 26% of RATED THERMAL POWER THERMAL POWER
~
High Setpoint - 1 109% of RATED High Setpoint - 1 110% of RATED THERMAL POWER THERMAL POWER
- 3. Power Range, Neutron Flux, 1 5% of RATED THERMAL POWER with 1 5.5% of RATED THERMAL POWER High Positive Rate a time constant 1 1 second with a time constant 1 1 second
- 4. Power Range, Neutron Flux, 1 3% of RATED THERMAL POWER with 1 3.5% of RATED THERMAL POWER High Negative Rate a time constant > 1 second with a time constant > 1 second
- 5. Intermediate Ranae, Neutron 1 ?5% of RATED THERMAL POWER 1 30% of RATED THERMAL POWER 7
Flux 5
5
- 6. Source Range, Neutron Flux 1 10 counts per second i 1.3 x 10 counts per second
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 4 b
- 9. Pressurizer Pressure--Low 1 1865 psig
> 1855 psig e
h"
.10. Pressurizer Pressure -High 1 2385 psig i 2395 psig A
h
- 11. Pressurizer Water Level--High 1 92% of instrument span 1 93% of instrument span tm B-
- 12. Loss of Flow 1 90% of design flow
> 89% of design flow per loop
- per loop *
- Design flow is 88,500 gpm per loop.
TABLE 2.2-1 (Continued) ff REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
[2 FUNCTIONAL UNIT TRIP SETP0 INT ALLOWABLE VALUES Ej
- 13. Steam Generator Water 3_15% of narrow range instrument 3,14% 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 EhTED THERMAL POWER coincicant RhTED THERMAL POWER coincident Generator Water Level with steam generator water lesel with steam generator water level
- 3. 25% of narrow range irstru-3,24% of narrow range instru-ment span--each steu geparator ment span--each steam generator
- 15. Undervoltage-Reactor
> 2680 volts-each bus
> 2640 volts-each bus Coolant Pumps
- 16. Underfrequency-Reactor
> 57.0 Hz - each bus
> 56.9 Hz - each bus n,
s, Coolant Pumps
- 17. Turbine Trip
?
Low Auto Stop Oil 3.45 psig 3.43 psig Pressure B.
Turbine Throttle Valve 3,1% open 3.0.75% open Closure
- 18. Safety Injection Input Not Applicable Not Applicable from ESF
- 19. Reactor Coolant Pump Not Applicable Not Applicable Breaker Position Trip W
4 IN) 4
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