ML20236U717
| ML20236U717 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/21/1998 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236U719 | List: |
| References | |
| NUDOCS 9807300396 | |
| Download: ML20236U717 (9) | |
Text
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- 844 0
UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enana amit
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WISCONSIN ELECTRIC POWER COMPANY 1
DOCKET NO. 50-3Q1 POINT BEACH NUCI FAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
l Amendment No.190 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 j
licensee) dated May 15,1998, complies with the standards and requirements of l
the Atomic Energy Act of 1954, as amended (the Act), and the Commission's j
rules and regulations set forth in 10 CFR Chapter I; r'
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 i
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 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 satisfed.
l r
1 l
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9907300396 990721 PDR ADOCK 05000266
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P PM
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragrapn 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.190, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specificatioris.
i i
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from f.he date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION OLy Ah Cynthia A. Carpenter, Director Project Directorate lll-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 21, 1998 L
i
ATTACHMENT TO LICENSE AMENDMENT NO. 190 l
TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 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 15.3.2-2 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 15.3.6-19 15.3.6-19 15.3.8-1 15.3.8-1
D.
During power operation, the requirements of 15.3.2-B and C may be modified to allow the following components to be inoperable for a specified time. If the system is not restored to meet the requirements of 15.3.2-8 or C within the time period specified, the' appropriate reactor (s), except as otherwise noted, shall be placed 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 j
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 />.
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 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
l Basis The chemical and volume control system provides control of the reactor coolant system boron inventory. This is normally accomplished by using one or more charging pumps in 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 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 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
- 26,600 gallons of 2700 ppm borated water from the refueling water storage tank (RWST) or the concentrations and volumes of borated water specified in Table 15.3.2-1 from the boric acid storage tanks (BASTS).
These RWST parameters are in effect following U1R25 for Unit 1 and U2R23 for l
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 this basis statement are 24,100 gallons and 2000 ppm respectively. Prior to U2R23, l
the Unit 2 minimum RWST volume and boron concentration values for this basis
.. statement are 24,100 gallons and 2000 ppm respectively.
l Unit 1 - Amendment No. 48,468,180 (SEP 231997)
Unit 2 - Amendment No. 98,462,464,190 15.3.2-2
Table 15.3.2-1 Boric Acid Storage Tank (s)
Minimum Volumerremperature/ Concentration Boric Acid Soln Minimum Combined Minimum Temperature Concentration Volume (Gal.)")
('F)
(wt%)
Prior to U1R25 After U1R25 or U2R23 or U2R23 l
3.00 to <3.50 6860(2) 7950<2) 56.0 3.50 to <4.00 5870c2) 6740(2) 62.5 4.00 to <4.50 5120c23 5850<2) 69.5 4.50 to <5.50 4550(3) 5180<2) 85.0 5.50 to <6.50 3700(2) 4210(3) 97.0 6.50 to <7.50 3150(')
3550(2) 107.0 7.50 to <8.50 2720()
3070(2) 116.0 8.50 to <9.50 2390 2710()
123.5 9.50 to <10.50 2140 2420 131.0 10.50 to <11.50 1930 2190 138.0 11.50 to s12.50 1750 2000 145.0 (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.
i l
1 Unit 1 - Amendment No. 468,180 (SEP 231997)
Unit 2 - Ament"
't No. 469,484,190
15.3.3 EMERGENCY CORE COOLING SYSTEM, AUXILIARY COOLING SYSTEMS, AIR RECIRCULATION FAN COOLERS, AND CONTAINMENT SPRAY Anolicability:
l Applies to the operating status of the Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray.
l Objective-l.
To define those limiting conditions for operation that are necessary: (1) to remwe decay l
heat from the core in emergency or normal shutdown situations, (2) to remove heat from i
containment in normal operating and emergency situations, and (3) to remove airborne iodine from the containment atmosphere following a postulated Design Basis Accident.
i Specification:
l A.
Safetv Iniection and Residual Heat Removal Systems l
l 1.
A reactor shall not be made critical, except for low temperature physics tests, unless the following conditions associated with that reactor are met:
a.
The refueling water tank contains not less than 275,000 gal. of water with a boron concentration of at least 2700 ppm.*
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 concentration of at least 2600 ppm." Neither accumulator may be
- isolated, 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 U2R23 for Unit 2; and takes l
effect prior to leaving the cold shutdown condition of those outages. Prior to U1R25, the Unit 1 minimum RWST boron concentration is 2000 ppm. Prior to U2R23, the l
Unit 2 minimum RWST boron concentration is 2000 ppm.
This value is in effect following U1R25 for Unit 1 and U2R23 for Unit 2; and takes l
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 U2R23, l
the Unit 2 minimum Si accumulator boron concentration is 2000 ppm.
Unit 1 - Amendment No.180 (SEP 231997)
Unit 2 - Amendment No. 484, 190 15.3.3-1
l B.
IDternal Pressure l
1.
If the intemal pressure exceeds 3 psig or the intemal vacuum exceeds 2.0 l
psig, the condition shall be corrected within one hour.
2.
If the above action cannot be completed within the time specified, place the affected unit in:
a.
hot shutdown within six hours, AND 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 subcritical by at least 5% Ak/k.
D.
Positive reactivity changes shall not be made by boron dilution when the containment integrity is not intact unless the boron concentration in the reactor is maintained
> 2100 ppm *,
This boron concentration value is in effect following U1R25 for Unit 1 and following U2R23 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to l
U1R25, the Unit 1 boron concentration value of this specification is 1800 ppm. Prior to U2R23, the Unit 2 boron concentration value of this specification is 1800 ppm.
l l
Unit 1 - Amendment 9,86,460,180 (SEP 23199'/)
Unit 2 - Amendment 49,99,464,484,190 15.3.6-7
experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems, i
Specifications 15.3.6.C. and D.
i 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 specified cold shutdown margin of 1% Ak/k precludes criticality under any occurrence. During refueling the reactor is subcritical 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
This boron concentration value is in effect following U1R25 for Unit 1 and following U2R23 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to l
U1R25, the Unit i boron concentration value of this specification is 1800 ppm. Prior to U2R23, the Unit 2 boron concentration value of this specification is 1800 ppm.
l Unit 1 - Amendment 64,86,89,404,460,180 (SEP 231997)
Unit 2 - Amendment 69,94,94,407,464,484,190 15.3.6-19
15.3.8 REFUELING l
Anolicabilitv:
l l
Applies to operating limitations during refueling operations.
f l
l Obbctive-l l
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 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, i
3.
Core subcritical neutron flux shall be continuously monitored by at least two nwron monitors, each with continuous visual indication in the control room and one with audible indication in the containment available whenever core geometry is being changed. When core geometry is not being changed, at least one neutron flux monitor shall be in service.
4.
At least one residual heat removal loop shall be in operation. However, if refueling operations are affected by the residual heat removal loop flow, the operating residual heat removal loop may be removed from operation for up to one hour per eight hour period.
1 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 primary coolant system.
This boron concentration value is in effect following U1R25 for Unit 1 and following U2R23 for Unit 2; and takes effect prior to loading fuel for those outages. Prior to l
U1R25, the Unit 1 boron concentration value of this specification is 1800 ppm. Prior L
to U2R23, the Unit 2 boron concentration value of this specification is 1800 ppm.
l
[
Unit 1 - Amendment No. 66,66, 96,180 (SEP 231997)
Unit 2 - Amendment No. 44,M,400,484,190 15.3.8-1 J