ML20138M048
| ML20138M048 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/20/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138M052 | List: |
| References | |
| NUDOCS 9702250244 | |
| Download: ML20138M048 (12) | |
Text
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION j
2 WASHINGTON, D.C. Saams m I
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I WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendt.ent No.172 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 19, 1996, as supplemented November 18, 1996, revised on January 13 and supplemented on January 27, 1997, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 4
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 i
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.
J 9702250244 970220 PDR ADOCK 05000266 P
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 172, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 45 days from the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION 4
J 0 k h.ne$wsw Linda L. Gundrum, Project Manager 4
Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: February 20, 1997 n
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION s*
l WASHINGTON, D.C. 20066-0001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 19, 1996, as supplemented November 18, 1996, revised on January 13 and supplemented on January 27, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comiscion'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 Comission; 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 Comission'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.
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l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
j B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 176, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE. NUCLEAR REGULATORY COMMISSION
)
hec /o k
>uhm Linda L. Gundrum, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation l
l
Attachment:
Changes to the Technical Specifications Date of issuance:
February 20, 1997
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ATTACHMENT TO LICENSE AMENDMENT NOS.172L_AND 176 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET N05. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 15-1 15-1 15.3.1-3 15.3.1-3 15.3.15-1 15.3.15-1 15.3.15-2 15.3.15-2 15.3.15-3 15.3.15-3 Table 15.4.1-1 Table 15.4.1-1 (Page 3 of 6)
(Page 3 of 6) 15.6.9-4 15.6.9-4 I
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TABLE OF CONTENTS Section Title hgg
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15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Definitions 15.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 1
15.2.3 Limiting Safety System Settings, Protective l
Instrumentation 15.2.3-1 l
15.3 Limiting Conditions for Operation 15.3.0 15.3.0 General Considerations 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power Conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 l
15.3.6 Containment System 15.3.6-1 1
15.3.7 Auxiliary Electrical Systems 15.3.7-1 15.3.8 Refueling 15.3.8-1 15.3.9 Effluent Releases 15.3.9-1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In-Core Instrumentation 15.3.11-1 15.3.12 Control Room Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressors (Snubbers) 15.3.13-1 l
15.3.14 Fire Protection System (This section was deleted as of 1/8/97) 15.3.14-1 i
15.3.15 Low Temperature Overpressure Protection System 15.3.15-1 l
15.3.16 Reactor Coolant System Pressure Isolation Valves 15.3.16-1 4
15.4 Surveillance Requirements 15.4-1 15.4.1 Operational Safety Review 15.4.1-1 15.4.2 In-Service Inspection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15.4.4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment Cooling System Tests 15.4.5-1 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 15.4.9 Reactivity Anomalies 15.4.9-1 15.4.10 Operational Environmental Monitoring 15.4.10-1 l
15.4.11 Control Room Emergency Filtration 15.4.11-1 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane Lifting Devices 15.4.14-1 15.4.15 Fire Protection System (This section was deleted as of 1/8/97) 15.4.15-1 l
15.4.16 Reactor Coolant System Pressure Isolation Valves Leakage Tests 15.4.16-1 Unit 1 - Amendment No. 96, Me, 172 Unit 2 - Amendment No. 400, W4, 176 15-1
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5.
Pressurizer Power-Operated Relief Valves (PORV) and PORV Block Valves If a unit is placed in the HOT SHUTDOWN condition in accordance with the requirements of Specifications a(1) through a(5) below, then the reactor l
coolant system temperature should be maintained greater than 355 *F.
If l
l cooldown to less than this temperature is required in order to take action to restore the inoperable component (s) to service, then the i
requirements of Specification 15.3.15 apply.
d a.
Two PORVs and their associated block valves shall be operable.
l (1)
If one or both PORVs are INOPERABLE due to seat leakage in
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excess of that allowed in Specifications 15.3.1.0, within one hour either restore the PORVs to an operable status or close the associated block valves (s).
If these conditions l
cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
(2)
If one PORV is INOPERABLE due to causes other than excessive j
seat leakage, within one hour either restore the PORV to j
OPERABLE status or close its associated block valve and il remove power from the block valve.
If the PORV cannot be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, place the unit
-in a HOT SHUTDOWN condition within the next six hours.
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(3)
If both PORVs are INOPERABLE due to causes other than j
excessive seat leakage, within one hour restore at least one PORV to OPERABLE status.
If this condition cannot be met, j
close the associated block valves, remove power from the l
block valves and place the unit in a HOT SHUTDOWN condition I
within the next six hours.
(4)
If one block valve is inoperable, within one hour either restore the block valve to OPERABLE status or place the l
associated PORV in manual control. Restore the block valve j-to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If these conditions a-cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
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Unit 1 - Amendment No. M 6, 172 l
Unit 2 - Amendment No. M9,176 15.3.1-3 4
4 l
15.3.15 LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM l
Apolicability Applies to operability of the low temperature overpressure protection (LTOP) system when the reactor coolant system temperature is < 355 *F.
Ob.iective To specify functional requirements and limiting conditions for operation on the use of the pressurizer power operated relief valves when used as part of the LTOP system and to specify further limiting conditions for operation when the reactor coolant system is operated at low temperatures.
Soecification A.
System Operability 1.
Except as specified in 15.3.15. A.2 below, the LTOP system shall be l
operable whenever the reactor coolant system is not open to the atmosphere and the temperature is < 355 F.
Operability l
requirements are:
a.
Both pressurizer power operated relief valves operable at a 1
setpoint of s 440 psig.
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b.
Both power operated relief valve block valves are open.
i 2.
The requirements of 15.3.15.A.1 may be modified as specified below:
a.
With one PORY inoperable while reactor coolant system temperature is > 200 *F but < 355 F, either restore the l
inoperable PORV to operable status within 7 days, or depressurize and vent reactor coolant system within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one PORV inoperable while reactor coolant system temperature is s 200 *F, either restore the inoperable PORV to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or depressurize and vent the reactor coolant syster within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Unit 1 - Amendment No. M E, 172 Unit 2 - Amendment No. M9, 176 15.3.15-1
l c.
With both power operated relief valves inoperable while the reactor coolant system temperature is < 355 'F, the reactor l
coolant system must be depressurized and vented within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l 3.
If the reactor coolant system is vented per Specification 15.3.15.A.2.a. b, or c, the pathway must be. verified at least once j
every 31 days when it is provided by a non-isolable pathway or by j
a valve (s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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B.
Additional Limitations l
l 1.
When LTOP is required to be enabled by Specification 15.3.15.A.1, l
j no more than one high pressure safety injection pump shall be operable. The second high pressure safety injection pump shall be i
rendered inoperable whenever LTOP is required to be enabled by l
l verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying that the discharge valves from the high pressure safety injection pumps to' the reactor coolant system are shut and that' power is removed from
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l their operators.
2.
A reactor coolant pump shall not be started when the reactor coolant system temperature is < 355 'F unless:
l-i a.
There is a pressure absorbing volume in the pressurizer or in the steam generator tubes or b.
The secondary water temperature of each steam generator is less than 50 'F above the temperature of the reactor coolant system.
Basis The Low Temperature Overpressure Protection System consists _of a redundant means of relieving pressure during periods of water solid operation and when,
l the reactor coolant system temperature is.< 355 'F.
This method of water l
Unit 1 - Amendment No. M6,172 Unit 2 - Amendment No M9,176 15.3.15-2
relief utilizes the pressurizer power operated relief valves (PORV's).
The j
PORV's are made operational for low pressure relief by utilizing a dual setpoint where the low pressure circuit is energized and de-energized by the operator with a keylock switch depending on plant conditions. The logic required for the low pressure setpoint is in addition to the existing PORV actuation logic and will not interfere with existing automatic or manual
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actuation of the PORV's. The 0PERABILITY of the PORVs is determined on the basis of their being capable of automatically mitigating an overpressure event during low temperature operation. The LTOP setpoint of 440 psig is valid through an inside surface neutron fluence of the limiting reactor vessel material of less than or equal to 2.05 x 10" n/ca' (E > 1.0 Mev).
l During plant cooldown prior to reducing reactor coolant system temperature l
below 355 *F, the operator under administrative procedures shall place the keylock switch in the " Low Pressure" position. This action enables the Low Temperature Overpressure Protection System. The redundant PORV channels shall remain enabled and operable while the LTOP system is required to be in operation.
The reactor coolant system is defined as vented if there is an opening in the l
reactor coolant system pressure boundary to atmosphere or the pressurizer relief tank that has an equivalent system pressure relieving capability as a PORV. Some examples of such openings include an open or removed PORV, open steam generator or pressurizer manways, a removed pressurizer safety valve, i
and the top of the reactor vessel when the reactor vessel head has been l
unbolted or removed.
The mass input transient used to determine the PORV setpoint assumes a worse l
L case transient of a single high pressure safety injection pump discharging to l
the reactor coolant system while the system is solid. Therefore, when LTOP is required to be enabled, only one high pressure safety injection pump shall be operable at any time except when the reactor coolant system is open to the atmosphere.
The heat input transient used to determine the PORV setpoint assumes a temperature difference between the reactor coolant system and the steam l
generator of 50 *F.
Therefore, before starting a reactor coolant pump when the reactor coolant system is solid, the operator shall ensure that the l
secondary. temperature of each steam generator is less than 50 *F above the
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temperature of the reactor coolant system unless a pressure absorbing volume j
has been verified to exist in the pressurizet or steam generator tubes.
i.
I Unit 1 - Amendment No. ME,172 Unit 2 - Amendment No. M 9, 176 l
15.3.15-3
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TABLE 15.4.1-1 (continued)
PLANT CONDITIONS E
CHANNEL DESCRIPTION CHECK CALIBRATE IEi1 WHEN REQUIRED 20.
Auxiliary Feedwater Flowrate (13)
R
.ALL 21.
Boric Acid Control System R
ALL i
22.
Boric Acid Tank Level D
R ALL 23.
Charging Flow R
ALL 24.
Condensate Storage Tank Level S(l)
R ALL 25.
Containment High Range Radiation S(l)
R(14)
M(1)
ALL 26.
Containment Hydrogen Monitor D
ALL
-Gas Calibration Q(15)
ALL y
-Electronic Calibration R
ALL 27.
Containment Pressure S
R-Q(1,3,9)
ALL 28.
Containment Water Level M
R ALL 29.
Emergency Plan Radiation Survey Instruments Q
R Q
ALL 30.
Environmental Monitors M
ALL t
31.
In-Core Thermocouples M
R(14)
ALL 32.
Low Temperature Overpressure l
Protection System S(12)
R (10)
ALL
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33.
PORY Block Valve Position Indicator Q
R ALL 34.
PORV Operability R
Q(11)
ALL 35.
PORY Position Indicator S(21)
R R
ALL Unit 1 - Amendment No. 4 W, 172 Unit 2 - Amendment No. 4 M, 176 Page 3 of 6
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l 15.6.9.2 Uniaue Reportina Reauirements l
l The following written reports shall be submitted to the Director, j
Office of Nuclear Reactor Regulation, USNRC:
1 A.
Deleted l
8.
Poison Assembly Removal From Soent Fuel Storace Racks Plans for removal of any poison assemblies from the spent j
fuel storage racks shall be reported and described at least 14 days prior to the planned activity.
Such report shall describe neutron attenuation testing for any replacement poison assemblies, if applicable, to confirm the presence of l
boron material.
C.
Low Temoerature Overoressure Protection System Operation l
In the event the low temperature overpressure protection system (power operated relief valves in the low temperature l
overpressure protection mode) or residual heat removal system relief valves are operated to relieve a pressure transient which, by licensee's evaluation, could have l
resulted in an overpressurization incident had the system not been operable, a special report shall be prepared and submitted to the Commission within 30 days. The report shall describe the circumstances initiating the transient, the effect of the system on the transient and any corrective action necessary to prevent recurrence.
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l Unit 1 - Amendment No. M9,172 Unit 2 - Amendment No. W 4, 176 15.6.9-4
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