ML20076L065
| ML20076L065 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/27/1994 |
| From: | Wharton L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076L074 | List: |
| References | |
| NUDOCS 9411030007 | |
| Download: ML20076L065 (5) | |
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,It UNITED STATES
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3 NUCLEAR REGULATORY COMMISSION
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' WASHINGTON, D.C. 20666 4001
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UNION ELECTRIC COMPANY CAllAWAY PLANT. UNIT 1 D0CKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated February 10, 1994, complies with the standards' and requirement.s 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
9411030007 941027-PDR ADOCK 05000483 P
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(2)
Technical Soecifications and Environmental Protection-Plan The Technical Specifications contained in' Appendix A,'as revised:
through Amendment No. 93, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto,,are hereby incorporated into the license. UE shall operate the. facility.
in accordance with the Technical: Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
The Technical Specifications are to be implemented within 30 days from the -
date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-kg) qw
. Raynard Wharton, Project Manager Project Directorate III-3 Division of. Reactor Projects - III/IV Office of Nuclear Reactor Regulation i:
Attachment:
Changes to the Technical Specifications Date of' issuance: October 27, 1994 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 93 OPERATING LICENSE NO. NPF-30 E
DOCKET NO. 50-483 1
Revise 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 vertical lines indicating the area of change. The corresponding overleaf pages, indicated by an asterisk, are also provided to maintain document completeness.
REMOVE INSERT-2-5(b) 2-5(b) 2-5(c)*
2-5(c)*
B 2-7*
B 2-7*
B 2-7(a)
B 2-7(a) 1 r
TABLE 2.2-1 (Continued) hb REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g
c
>=
SENSOR
~'
TOTAL ERROR l_
FUNCTIONAL UNIT ALLOWANCE (TA)
Z (S)
TRIP SETPOINT ALLOWABLE'VALUE f5
- 13. Steam Generator Water Level Low-Low (Continued) c.
Vessel AT Equivalent
> 20% RTP Coincident with Steam Generator Water Level 20.2 17.58 2.0 2 20.2% of Narrow 2 18.4% of Narrow tow-Low (Adverse Range Instrument Range Instrument Containment Environment)
Span Span-7 and 30 Containment Pressure -
2.8 0.71 2.0 s 1.5 psig s 2.0'psig 25 Environmental Allowance Modifier OR Steam Generator Water Level 14.8 12.18 2.0 2 14.8% of Narrow 213.0% of Narrow tow-Low (Normal Range Instrument Range Instrument Containment Environment)
Span Span
- 14. Undervoltage - Reactor 33.3 1.33 0
2 10584 Volts A.C.
2 10105 Volts A.C. l Coolant. Pumps 2-l
- 15. Underfrequency - Reactor 3.3 0
0 2 57.2 Hz 2 57.1 Hz gp Coolant Pumps E
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TABL_E_2.2-1_[Continuedl REACTOR TRIP SYSTEM INSTRUMENTATION _ TRIP SETPOINTS S
SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE _(TAl Z
(S)
TRIP SETPOINT ALLOWABLE VALUE z
Z 16.
a.
Low Fluid Oi' N.A.
N.A.
N.A.
> 598.94 psig
> 539.42 psig Pressure b.
Turbir.e Stop Valve N.A.
N.A.
N.A.
> 1% open
~> 1% open Coosure 17.
Safety Injection Input N.A.
N.A.
N.A.
N.A.
N.A.
"4 from ESF X
a a
n 6
e
l LIMITING SAFETY SYSTEM SETTINGS BASES Steam Generator Water Level 1
The Steam Generator Water Level Low-Low trip protects the reactor from loss of heat sink in the event of a sustained steam /feedwater flow mismatch resulting from loss of normal feedwater or a feedwater system pipe break, inside or outside of containment. This function also provides input to the steam generator level control system, therefore, the actuation logic must be able to withstand both an input failure to the control system (which may then require the protective function actuation) and a single failure in the remaining channels providing the protection function actuation. This results in a 2/4 actuation logic.
With the transmitters (d/p cells) locattJ inside containment and thus possibly experiencing adverse environmental conditions (due to a feedline break),
the Environmental Allowance Modifier (EAM) was devised. The EAM function (Containment Pressure with a setpoint of < l.5 psi adverse containment conditions (elevated pressure)g) senses the presence of
.and enables the Steam Generator Water Level - Low-Low trip setpoint (Adverse) which reflects the increased transmitter uncertainties due to this environment. The EAM allows the use of a lower Steam Generator Water Level - Low-Low trip setpoint (Normal) when these conditions are not present, thus allowing more margin to trip for normal operating conditions. The Trip Time Delay (TTD) creates additional operational margin when the plant needs it most, during early escalation to power, by allowing the operator time to recover level when the primary side load is sufficiently small to allow such action. The TTD is based on the continuous monitoring of primary side power through the use of Vessel AT. Two.
time delays are possible, based on the primary side power level, the magnitude of the trip delay decreasing with increasing power.
In the event that the EAM or TTD functions do not meet the minimum channels operable requirements, it is acceptable to place the inoperable channels in the Tripped Condition and continue operation.
Placing the inoperable channels in this mode will result in the enabling of the Steam Generator Water Level - Low-Low (Adverse) function, for the EAM, or in the removal of the trip delay, for the TTD.
In the event that the Steam Generator Water Level - Low-Low (Normal) function does not meet the minimum channels operable requirement, it is acceptable to place the associated EAM channels in the Tripped Condition and continue operation.
Performing this action will result in the enabling of the Steam Generator Water Level - Low-Low (Adverse) function which has a more conservative (higher level) trip setpoint.
At this time it would also be acceptable to place the inoperable Steam Generator Water Level - Low-Low channels in the Bypassed Condit10n to prevent an inadvertent Reactor Trip or ESFAS actuation.
Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide core protection against DNB as a result of complete loss of forced coolant flow.
The specified Setpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached. Time delays are incorporated in the Underfrequency and Undervoltage trips to prevent spurious Reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required 4
l CALLAWAY - UNIT 1 8 2-7 Amendment No. 43 i
4 LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltaae and Underfreauency - Reactor Coolant Pumo Busses (Continued) for a signal to reach the Reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers-shall not exceed 1.2 seconds.
For underfrequency, the delay is set so that-the time required for a signal to reach the Reactor trip breakers after the Underfrequency Trip Setpoint is reached shall not exceed 0.3 second. On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approximately 10% of RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10% of full power equivalent); and on increasing power, reinstated automatically by P-7.
The Total Allowance and Z values for the RCP Undervoltage trip function are based on percent of the undervoltage relay span while the Trip Setpoint and Allowable Value are based on voltages on the 13.8 kV, PA system busses powering the RCP motors. The undervoltage relay span is 30 volts, from 70 to 100 VAC.
Potential transformers PA03 and PA06 have a ratio of 120:1 (14,400V to 120V): therefore, the Trip Setpoint of 10,584 VAC on the PA bus. corresponds to 88.2 VAC at the undervoltage relay.
Likewise, the Allowable Value of 10,105 VAC on the PA bus corresponds to 84.2 VAC at the undervoltage relay.
Turbine Trio A turbine trip initiates a Reactor trip. On decreasing power the Reactor trip from the turbine trip is automatically blocked by P-9 (a power level of approximately 50% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.
Safety In.iection Inout from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection. The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.
4 CALLAWAY - UNIT 1 B 2-7(a)
Amendment No. AA,93 I
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