ML20248A963
| ML20248A963 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/27/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248A969 | List: |
| References | |
| NUDOCS 9806010118 | |
| Download: ML20248A963 (13) | |
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'4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30ee6 0001
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 l
BEAVER VALLEY POWER STATION. UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.214 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated March 17,1998, as supplemented May 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the l
Commission's rules and regulations set forth in 10 CFR Chapter I; j
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.
1 l
9906010119 990527 PDR ADOCK 05000334 p
. 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. DPR-66 is hereby amended to read as follows:
l l
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 214, 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, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Ta2Ja.. Q Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 27, 1998 l
ATTACHMENT TO LICENSE AMENDMENT NO.214 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO, 50-334 Replace the following pages cf Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove 1011!1 3/4 3-21 3/4 3-21 B 3/4 3-1b B 3/4 3-1b l
1
DPR-66 TABLE 3.3-3 (Continued)
ACTION STATEMENTS With the number of OPERABLE Channels or.e less than the ACTION 33 Total Number of
- Channels, the Emergency Diesel Generator associated with the 4kV Bus shall be declared inoperable and the ACTION Statements for Specification 3.8.1.1 or Specification 3.8.1.2, as appropriate, shall apply.
a.
With the number of OPERABLE channels one less ACTION 34 than the Minimum Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; otherwise, immediately enter the applicable ACTION statement (s) for the associated Emergency Diesel Generator made inoperable by the degraded voltage start instrumentation.
b.
With the number of OPERABLE channels two less than the Minimum Number of Channels, restore at least one of the two channels to OPERABLE status and place the other in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; otherwise, immediately enter the applicable ACTION statement (s) for the associated Emergency Diesel Generator made inoperable by the degraded voltage start instrumentation.
The block of the automatic actuation logic introduced ACTION 36 by a reset of safety injection shall be removed by resetting (closure) of the reactor trip breakers within one hour of an inadvertent initiation of safety injection providing that all trip input signals have reset due to stable plant conditions.
Otherwise, the requirements of ACTION statement 13 shall have been met.
Not applicable.
ACTION 37 With less than the Minimum Number of Channels ACTION 38 OPERABLE, within one hour determine by observation of the associated permissive annunciator window (s)
(bistable status lights or computer checks) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
(
BEAVER VALLEY - UNIT 1 3/4 3-21 Amendment No.214 l
r DPR-66
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INSTRUMENTATION l
l BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESP)
INSTRUMENTATION (Continued)
Below the setpoint P-11 allows the manual block of safety injection actuation on low pressurizer
- pressure, allows manual block of safety injection and steamline isolation on low steamline pressure (with Loop Stop Valves Open) and enabling steamline isolation on high steam pressure rate, l
automatically disables, auto actuation of the pressurizer PORVs unless the Reactor Vessel Over Pressure Protection System is in service.
P-12 Above the setpoint P-12 automatically reinstates an arming signal to the steam dump system.
Below the setpoint P-12 blocks steam dump and allows manual bypass of the steam dump block to cooldown condenser dump valves.
Table 3.3-1 Action 2 has been modified 11 two notes.
Note (4) allows placing the inoperable channel in the bypass condition for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> while performing:
a) routine surveillance testing of other channels, and b) setpoint adjustments of other channels when required to reduce the setpoint in accordance with other technical specifications.
The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time limit is justified in accordance with WCAP-10271-P-A, Supplement 2, Revision 1, June 1990.
Note (5) only requires SR 4.2.4 to be performed if a Power Range High Neutron Flux channel input to QPTR becomes inoperable.
Failure of a
component in the Power Range High Neutron Flux channel which renders the High Neutron Flux trip function inoperable may not affect the capability to monitor QPTR.
As such, determining QPTR using the movable incore detectors once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> may not be necessary.
The following discussion pertains to Table 3.3-3, Functional Units 6.b and 6.c and the associated ACTION 34.
The degraded voltage protection instrumentation system will automatically initiate the separation of the offsite power sources from the emergency buses.
This action results in an automatic diesel generator start signal being generated as a direct result of the supply breakers opening between the normal and emergency buses.
The failure of the degraded voltage protection system results in a loss of one of the automatic start signals for the diesel generator.
Therefore, the ACTION statement requires the affected diesel generator to be declared inoperable if the required actions cannot be met within the specified time period.
BEAVER VALLEY - UNIT 1 B 3/4 3-lb Amendment No.214
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20N50001 s...../
DUQUESNE LIGHT COMPANY QHiO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412
{
t BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the dicensee) dated March 17,1998, as supplemented May 14,1998, 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.
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 (1) 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 q
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.
l l
l I
I
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicted in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2) TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION I
3,J,.+ 4GL..Cp Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 27, 1998 I
e l
l ATTACHMENT TO LICENSE AMENDMENT NO. 91 l
FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines i
l indicating the areas of change.
Remove jngad x
x 3/4 3-22 3/4 3-22 8 3/4 3-4 B 3/4 3-4 B 3/4 3-5 B 3/4 3-5 B 3/4 3-6 8 3/4 3-6 j
NPF-73 IH12EX BASES SECTION PAGE 3/4,2 POWER DISTRIBUTION LTMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)...................B 3/4 2-1 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS Fg(Z) AND yh............ B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATIO.....................B 3/4 2-5 3/4.2.5 DNB PARAMETERS................................B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...........B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation..........B 3/4 3-4 3/4.3.3.2 Movable Incore Detectors......................B 3/4 3-5 l
3/4.3.3.3 Seismic Instrumentation.......................B 3/4 3-5 3/4.3.3.4 Meteorological Instrumentation................B 3/4 3-5 3/4.3.3.5 Remote Shutdown Instrumentation...............B 3/4 3-5 3/4.3.3.7 Chlorine Detection Systems....................B 3/4 3-6 l
3/4.3.3.8 Accident Monitoring Instrumentation...........B 3/4 3-6 3/4.3.3.11 Explosive Gas Monitoring Instrumentation......B 3/4 3-6 3/4.3.4 TURBINE OVERSPEED PROTECTION..................B 3/4 3-6 l
3/4.4 REACTOR COOLANT SYSTEM l
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT l
CIRCULATION...................................B 3/4 4-1 3/4.4.2 AND 3/4.4,.3 SAFETY VALVES.........................B 3/4 4-2 3/4.4.4 PRESSURIZER...................................B 3/4 4-2 BEAVER VALLEY - UNIT 2 X
Amendment No. 91 l
NPF-73 TABLE 3.3-3 (Continued)
ACTION STATEMENTS ACTION 33 -
With the number of OPERABLE Channels one less than the Total Number of
- Channels, the Emergency Diesel Generator associated with the 4kV Bus shall be declared inoperable and the ACTION Statements for Specifications 3.8.1.1 or 3.8.1.2, as appropriate, shall apply.
a.
With the number of OPERABLE channels one less ACTION 34 than the Minimum Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; otherwise, immediately enter the applicable ACTION statement (s) for the associated Emergency Diesel Generator made inoperable by the l
degraded voltage start instrumentation.
b.
With the number of OPERABLE channels two less than the Minimum Number of Channels, restore at least one of the two channels to OPERABLE status and place the other in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; otherwise, immediately enter the l
applicable ACTION statement (s) for the associated Emergency Diesel Generator made inoperable by the degraded voltage start instrumentation.
ACTION 36 -
The block of the automatic actuation logic introduced by a reset of safety injection shall be removed by resetting (closure) of the reactor trip breakers within one hour of an inadvertent initiation of safety injection providing that all trip input signals have l
reset due to stable plant conditions.
Otherwise, the I
requirements of ACTION Statement 13 shall have been met.
ACTION 37 -
(This ACTION is not used)
ACTION 38 -
With less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window (s)
(bistable status lights or computer checks) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 41 -
With the number of OPERABLE Channels one less than the Total Number of
- Channels, 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.
I i
l BEAVER VALLEY - UNIT 2 3/4 3-22 Amendment No.91
NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINFFRED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
Table 3.3-1 Action 2 has been modified by two notes.
Note (4) allows placing the inoperable channel in the bypass condition for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> while performing:
a) routine surveillance testing of other channels, and b) setpoint adjustments of other chanr$1s when required to reduce the setpoint in accordance with other technical specifications.
The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time limit is justified in accordance with WCAP-10271-P-A, Supplement 2, Revision 1,
June 1990.
Note (5) only requires SR 4.2.4 to be performed if a Power Range High Neutron Flux channel input to_QPTR becomes inoperable.
Failure of a component in the Power Range High Neutron Flux channel which renders, the High Neutron Flux trip function inoperable may not affect the capability to monitor QPTR.
As such, determining QPTR using the movable incore detectors once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> may not be necessary.
The following discussion pertains to Table 3.3-3, Functional Units 6.b and 6.c and the associated ACTION 34.
The degraded voltage protection instrumentation system will automatically initiate the separation of the offsite power sources from the emergency buses.
This action results in an automatic diesel generntor start signal being generated as a direct result of the supply breakers opening between the normal and emergency buses.
The failure of the degraded voltage protection system results in a loss of one of the automatic start signals for the diesel generator.
Therefore, the ACTION statement requires the affected diesel generator to be declared '
inoperable if the required actions cannot be met within the specified time period.
3 / 4 '. 3. 3 MONITORING INSTRUMENTATION i
3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:
- 1) the ' radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is i
initiated when the radiation level trip setpoint is exceeded; and 1
- 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of NUREG-0737,
" Clarification of TMI Aed cn Plan Requirements," October, 1980.
BEAVER VALLEY - UNIT 2 B 3/4 3-4 Amendment No. gj
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3/4.3 INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring Fg(Z) or Fh, a full incore flux map is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in re-calibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the Quadrant Power Tilt Ratio when one Power Range Channel is inoperable.
, 3/4.3.3.3 SEISMIC INSTRUMENTATION Tne OPERABILI'TY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the meacured response to that used in the design-basis for the facility and is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes."
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs."
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that i'
sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control I
room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 (This Specification number is not used).
BEAVER VALLEY - UNIT 2 B 3/4 3-5 Amendment No.91 l
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3/4.3 INSTRUMENTATION' l
BASES 3/4.3.3.7 CHLORINE DETECTION SYSTELS 1
i The OPERABILITY of the chlorine detection systems ensures that l
sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release.
'This capability is required to protect control room personnel and is consistent 'with the recommendations of Regulatory Guide 1.95,
" Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," January 1977.
3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine _ excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
BEAVER VALLEY - UNIT 2 B 3/4 3-6 Amendment No. 91