ML19210C931
| ML19210C931 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/03/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210C932 | List: |
| References | |
| NUDOCS 7911200336 | |
| Download: ML19210C931 (7) | |
Text
.
,/
'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
g WASHINGTcd, D. C. 20555 g
ej
\\...../
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY P0llER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) of the Atomic Energy Act of 1954, as amended (the Act) quirements dated June 26, 1979, complies with the standards and re and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in confonnity 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 Commission's regulations and all applicable requirements have been satisfied.
7/7 2c)5 4
70112 00 3 h
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to t his license amendment, and paragraph 2.C.(2) of Facility Opert ting License No. OPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 21, 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 (W
A. Scliwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Spec ific ations Date of Issuance: November 3,1979 296
ATTACHMENT TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pager of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 2-6 B 2-4 4257 297 BEAVER VALLEY - UNIT 1 i
' SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The reactor trip system instrumentation setpoints shall be set 2.2.1 consistent with the Trip Setpoint values shown in Table 2.2-1.
AS SHOWN FOR EACH CHANNEL IN TABLE 3.3-1.
APPLICABILITY:
ACTION:
With a reactor trip system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION state-ment requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
267 293 4
2-5 BEAVER VALLEY - UNIT 1
E TABLE _2.2__'l_
g E
REACTOR TRIP SYSTEM INSTRilMfNTATION TRIP SETPOINTS
<N filNC,TIONAL_ llNIT_
TRIP SETPOINT AL,LOWABLE VALUES E
- 1. Manual Reactor Trip Not Applicable Not Applicable
- 2. Pwer Range, Neutron Flux Low Setpoint - 1 75" of RATED Low Setpoint - 1 26" of RATED H
TilERMAL POWER THERMAL POWER High Setpoint - ; 1097 of RATED High Setpoint - 1 110", of RATED THERMAL POWER TilERMAL POWER
- 3. Power Range, Neutron Flux,
- 5". of RATED THERMAL POWER with 1 5.5f, of RATED THERMAL POWER liiqh Positive Rate a time constant 2 1 second with a time constant > l second
'?
- 4. Power Range, Neutron Flux, 1 3?- of RATED THERMAL POWER with
- 3.5" of RATED THERMAL POWER liiqh Neqative Rate a time constant 2 1 second with a time constant > l second m
- 5. Intermediate Range, Neutron 5 25", of RATED THERMAL POWER 1 30", of RATED THERMAL POWER 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 g
- 8. Overpower AT See Note 2 See Kate 3 o
R
- 9. Pressurizer Pressure--Low
> 1945 psig
> 1935 psig
- 10. Pressurizer Pressure--High 5 2385 psig i 2395 psig 5
- 11. Pressurizer Water Level--High 1 92% of instrument span 1 93% of instrument span
- 12. Loss of Flow
> 90% of design flow
> 89% of design ficw per loop
- per loop *
)
- Design flow is 88,500 gpm per loop.
..s O
N 4
C
2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SET POINTS The Reactor Trip Setpoint 6:..iits specified in Table 2.2-1 are the The Trip values at which the Reactor Trips are set for each parameter.
Values 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 Setpoint less conservative than its Setpoint Limit 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 to occur for each trip used in the accident 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 The low set protected by temperature and pressure protective circuitry.
point provides redundant protection in the power range for a powerThe trip a excursion beginning from low power.
setpoint may be manually bypassed when P-10 is active (two of the four power range channels indicate a power level of above approximately 9 per cent of RATED THERMAL POWER) and is autom below approximately 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. Specifically, 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.
B 2-3
'26 300 BEAVER VALLEY - UNIT 1
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 tne automatic rod control system, could cause an unconservative local DNBR to exist.
The Power Range Negative Rate trip wi1* p.revent this from occurring by tripping the reactor for all single or multiple dropped rods.
Intermediate and Source Range, Nuclear Flux The Intemediate and Source Range, Nuclear 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 Intemediate 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 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 specification to enhance the overall reliability of the Reactor Protection System.
Overtemperature AT The Overtemperature AT 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 p ping transit delays from the core to the temperature detectors (about seconds), and pressure is within the range between the High and Low ressure reactor trips. This 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. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown on Figures 2.1-1, 2.1-2 and 2.1-3.
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.
i BEAVER VALLEY - UNIT 1 B 2-4 Amendment No. 21
... -