ML20236R945
| ML20236R945 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/23/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236R947 | List: |
| References | |
| NUDOCS 9807240043 | |
| Download: ML20236R945 (11) | |
Text
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t UNITED STATES g
NUCLEAR RECULATORY COMMISSION WASHINITIN, D.O. 30086 4 001
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- WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 16,1997, as supplemented on April 17, August 7, and August 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 and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; I
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
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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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9007240043 970923 I
PDR ADOCK 05000266 4
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I 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-24 is hereby amended to read as follows:
3 B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, are hereby incorporated in the license. The licensee shall operate the facility in accordance with 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.
FOR THE NUCLEAR REGULATORY COMMISSION l
h Linda L. Gundrum, Project Manager Project Directorate lil-1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of issuance: September 23, 1997 l
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_____._______________________.______._____________.______________.___..__.______________.____________________._.__________________J
,p UNITED STATES p
j NUCLEAR REGULATORY COMMISSION g
CAsHINITcN, D.o. 30e06-0001 4,.....,o WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 16,1997, as supplemented on April 17, August 7, and August 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 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 oli applicable requirements have been satisfied.
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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:
4 B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised j
through Amendment No.184, are hereby incorporated in the license. The i
licensee shall operate the facility in accordance with 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.
FOR THE NUCLEAR REGULATOPY COMMISSION s
Linda L. Gundrum, Project Manager Project Directorate ill-1 Division of Reactor Projects - fil/IV Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of issuance: September 23, 1997
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l ATTACHMENT TO LICENSE AMENDMENT NOS.18CANQ1g l
TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50 266 AND 50-301 Revise Appendix A Tt.:Anical 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.
&,,MQVE INSERT 15.3.2-2 15.3.2-2 Table 15.3.2-1 Table 15.3.2-1 15.3.3-1 15.3.3-1 15.3.6-7 15.3.6-7 l
i 15.3.6-19 15.3.6-19 15.3.8-1 15.3.8-1
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. D.
During power cperation, the requirements of 15.3.2-B cnd C may be modifsd to cliow the f:liowing componInts to be inoperable for a specified time. If the system.is not restored to meet the requirements of 15.3.2-B or C within the time period specified, the appropriate reactor (s), except as otherwise noted, shall be pieced in the hot shutdown condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a shutdown margin equivalent of at
'least 1.0% delta k/k at cold shutdown, no xenon conditions. If the requirements of 15.3.2-B or C are not satisfied within an additional 7 days, the appropriate reactor (s) shall be placed in the cold shutdown condition within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1.
One of the two operable charging pumps associated with an operating reactor may be removed from service provided a charging pump associated with that reactor is 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 />.
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2.
One of the two boron injection flow paths specified in B.2 or C.2 may be out of service provided two boron injection flow paths are 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 />.
3.
One of the boric acid transfer pumps designated in B.3 or C.3 may be out of service provided a boric acid transfer pump is restored to operable status l
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Basis j
The chemical and volume control system provides control of the reactor coolant system l
boron inventory. This is normally accomplished by using one or more charging pumps in l
series with one of the two boric acid transfer pumps. Above cold shutdown conditions, a minimum of two boron injection flow paths are required per unit to insure functional capability in the event that an assumed single active failure renders one of the flow paths inoperable.
The boration volume available through any flow path is sufficient to provide the required 4
shutdown margin at cold shutdown, xenon-free conditions from any expected operating condition. The volume requirement is associated with boration from just critical, hot zero or l
l full power, peak xenon with control rods at the insertion limit, to xenon-free, cold shutdown with the highest worth control rod assembly fully withdrawn. This requires approximately L
- 26,600 gallons of 2700 ppm borated water from the refueling water storage tank (RWST) or - l l
the concentrations and volumes of borated water specified in Table 15.3.2-1 from the boric
- scid storage tanks (BASTS).
These RWST parameters are in effect following U1R25 for Unit 1 and U2R24 for Unit 2; and take effect prior to leaving the cold shutdown condition of those outages.
Prior to U1R25, the Unit 1 minimum RWST volume and boron concentration values for I
this basis statement are 24,100 gallons and 2000 ppm respectively. Prior to U2R24, the Unit 2 minimum RWST volume and boron concentration values for this basis statement are 24,100 gallons and 2000 ppm respectively.
j Unit 1 - Amendment No. 48,448,180 Unit 2 - Amendment No. 23,442,184 j
15.3.2-2
Tcble 15.3.2-1 Boric Acid Storage Tank (s)
Minimum Volume / Temperature / Concentration p
Boric Acid Soln Minimum Combined Minimum Temperature Concentrabon Volume (Gal.)")
(7)
(wt%)
Prior to U1R25 After U1R25 or U2R24 or U2R24 l
3.00 to <3.50 6860*
7950*
56.0 l
3.50 to <4.00 5870*
6740*
62.5 4.00 to <4.50 5120*
5850*
69.5 4.50 to <5.50 4550*
5180*
85.0 l
5.50 to <6.50 3700*
4210*
97.0 6.50 to <7.50 3150*
3550*
107.0 i
7.50 to <8.50 -
2720*
3070*
116.0 l
8.50 to <9.50 2390 2710*
123.5 l
9.50 to <10.50 2140 2420 131.0 10.50 to <11.50 1930 2190 138.0 11.50 to s;12.50 1750 2000 145.0 l
(1)
Per unit relying on BAST (s) as source of borated water.
(2)
Requires more than one BAST per unit.
(3)
Requires more than one BAST for two units combined.
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Unit 1 - Amendment No. 468,180 Unit 2 - Amendment No. 443,184 l
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l 15.3.3 EMERGENCY CORE COOLING SYSTEM, AUXILIARY COOLING SYSTEMS, AIR RECIRCULATION FAN COOLERS, AND CONTAINMENT SPR/.Y Anoticability.
l Applies to the operating status of the Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray.
Obiective-t To define those limiting conditions for operation that ere reessary: (1) to remove decay heat from the core in emergency or normal shutdown situations, (2) to remove heat from containment in normal operating and emergency situations, and (3) to remove airbome iodine j
from the containment atmosphere following a postulated Design Basis Accident.
l Specification.
A.
Safety Iniection and Residual Heat Removai System _g I
1.
A reactor shall not be made critical, except for low temperature physics tests, unless the following conditions associated with that reactor are met:
j a.
The refueling water tank contains not less than 275,000 gal of water with a boron concentration of at least 2700 ppm.*
l b.
Each accumulator is pressurized to at least 700 psig and contains at least 1100 ft' but no more than 1136 ft' of water with a boron l
concentration of at least 2600 ppm." Neither accumulator may be l
isolated.
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c.
Two safety injection pumps are operable.
d.
Two residual heat removal pumps are operable.
e.
Two residual heat exchangers are operable.
This value is in effect following U1R25 for Unit 1 and U2R24 for Unit 2; and takes effect prior to leaving the cold shutdown condition of those outages. Prior to U1R25, l
the Unit 1 minimum RWST boron concentration is 2000 ppm. Prior to U2R24, the Unit 2 minimum RWST boron concentration is 2000 ppm.
l This value is in effect following U1R25 for Unit 1 and U2R24 for Unit 2; and takes effect prior to leaving the cold shutdown condition of those outages. Prior to U1R25, the Unit 1 minimum Si accumulator boron concentration is 2000 ppm. Prior to U2R24, the Unit 2 minimum Si accumulator boron concentration is 2000 ppm.
f Unit 1 - Amendment No.180 Unit 2 - Amendment No.184 -
15.3.3-1 l
L.
l B.
Intemal Pressure 1.
If the intemal pressure exceeds 3 psig or the intemal vacuum exceeds 2.0 psig, the condition shall be corrected within one hour, i
2.
If the above action cannot be completed within the time specifed, place the affected unit in:
a.
hot shutdown within six hours, AND l.
b.
cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
I C.
. Positive reactivity changes shall not be made by rod drive motion when the containment integrity is not intact except for the testing of one bank of rods at a time, rod disconnecting, and rod reconnecting provided the reactor is initially suberitical by at least 5% Ak/k.
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D.
Positive reactivity changes shall not be made by boron dilution when the containment l
integrity is not intact unless the boron concentration in the reactor is maintained l
> 2100 ppm *.
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This boron concentration value is in effect following U1R25 for Unit 1 and following U2R24 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to U1R25, the Unit 1 boron concentration value of this specification is 1800 ppm. Prior l
' to U2R24, the Unit 2 boron concentration value of this specification is 1800 ppm.
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Unit 1 - Amendment 9,86,440,180 Unit 2 - Amendment 43,00,444,184 15.3.6-7 l.
cxperience, to re:ch tha required pl:nt conditians from full power conditions in cn crdirly manner and without challenging plant systems.
Specifications 15.3.6.C. and D.
The shutdown conditions of the reactor are selected based on the type of activities that are being carried out. When the reactor head is not to be removed, the specifed cold shutdown margin of 1% Ak/k precludes criticality under any occurrence. During refueling the reactor is subcribcal by 5% Ak/k. Positive reactivity changes for the purpose of rod assembly testing will not result in criticality because no control bank worth exceeds 3%. Positive reactivity changes by boron dilution may be required or small concentration fluctuations may occur during preparation for, recovery from, or during refueling but maintaining the boron concentration greater than 2100 ppm
- precludes criticality under these circumstances.
2100 ppm
- is a nominal value that ensures 5% shutdown for typical reload cores. Should continuous dilution occur, the time intervals for this incident are discussed in Section 14.1.4 of the FSAR.
References (1) FSAR - Section 5.1.1 (2) FSAR - Section 14.3.4 (3) FSAR - Section 5.5.2 l
1 This boron concentration value is in effect following U1R25 for Unit 1 and following l
U2R24 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to U1R25, the Unit 1 boron concentration value of this specification is 1800 ppm. Prior to U2R24, the Unit 2 boron concentration value of this specification is 1800 ppm.
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Unit 1 - Amendment 64,66,6g,444,44g,180 l
Unit 2 - Amendment Sg,94,94,407,464,184 15.3.6-1 g
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15.3.8 REFUELING Apohcability' Applies to operating limitations during refueling operations.
Obiective:
To ensure that no incident could occur during refueling operations that would affect public health and safety.
Specifications:
During refueling operations:
1.
The equipment hatch shall be closed and the personnel locks shall be capable of being closed. A temporary third door on the outside of the personnel lock shall be in L
l-place whenever both doors in a personnel lock are open (except for initial core loading).
2.
Radiation levels in fuel handling areas, the containment and spent fuel storage pool shall be monitored continuously.
3.
' Core subcritical neutron flux shall be continuously monitored by at least two neutron j.
monitors, each with continuous visual indication in the control room and one with l
audible indication in the containment available whenever core geometry is being changed. When core geometry is not being changed, at least one neutron flux l
L
- monitor shall be in service.
l 4.
At least one residual heat removal loop shall be in operation. However, if refueling I
operations are affected by the residual heat removal loop flow, the operating residual l
heat removal loop may be removed from operation for up to one hour per eight hour period.
L 5.
- During reactor vessel head removal and while loading and unloading fuel from the reactor, a minimum boron concentration of 2100 ppm
- shall be maintained in the l
primary coolant system.
i This boron concentration value is in effect following U1R25 for Unit 1 and following l.
U2R24 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to U1R25, the Unit 1 boron concentration value of this specification is 1800 ppm. Prior to U2R24, the Unit 2 boron concentration value of this specification is 1800 ppm.
Unit 1 - Amendment No. 35,88, OS,180 Unit 2 - Amendment No. 44,74,400,184 15.3.8-1 w
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