ML20072G364
| ML20072G364 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/16/1994 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072G367 | List: |
| References | |
| NUDOCS 9408240291 | |
| Download: ML20072G364 (8) | |
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20S$5-0001
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s WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 License No. DPR-24 1.
The Nuclear Regulatory temmission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated February 26, 1993, as supplemented on March 9, 1993, 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 all applicable. requirements have been satisfied.
i 9408240291 940816 PDR ADOCK 05000266 P
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license l
amendment, and paragraph 3.8 of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Technical Specification 1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 149, 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 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.~s Allen G. Hansen, Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 16, 1994
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-t UNITED STATES E ) Ifl E NUCLEAR REGULATORY COMMISSION
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_E WASHINGTON, D.C. 20555 0001 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.153 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 February 26, 1993, as supplemented on March 9, 1993, 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 all applicable requirements have been satisfied.
. 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:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
153, 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 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 16, 1994
ATTACHMENT TO llCENSE AMENDMENT NOS.149 AND 153 TO FACillTY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 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 marginal lines indicating the area of change.
REMOVE INSERT TS 15.3.1-2 TS 15.3.1-2 TS 15.3.1-3c TS 15.3.1-3c TS 15.3.1-3d TS 15.3.1-2d i
1 I
l u
(c)
Residual Heat Removal Loop (A)*
(d)
Residual Heat Removal Loop (B)*
(2)
If the conditions of specification (1) above cannot be met, corrective action to return a second decay heat removal method to operable status as soon as possible shall be initiated immediately.
(3)
If no decay heat removal method is in operation, except as permitted by (4) below, all operations causing an increase in the reactor decay heat load or a reduction in reactor coolant system boron concentration shall be suspended.
Corrective actions to return a decay heat removal method to operation shall be initiated immediately.
(4) At least one of the above decay heat removal methods shall be in operation.
(a) All reactor coolant pumps and residual heat removal pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:
(1) No operations are permitted that would cause dilution of reactor coolant system boron concentration, and (2)
Core outlet temper.ature is maintained at least 10 F below saturation temperature, b.
Reactor Coolant Temperature less Than 140 F (1)
Both residual heat removal loops shall be operable except as permitted in items (3) or (4) below.
(2)
If no residual heat removal loop is in operation, all operations causing an increase in the reactor decay heat load or a reduction in reactor coolant system boron concentration shall be suspended.
Corrective actions to return a decay heat removal method to operation shall be initiated immediately.
(3) One residual heat removal loop may be out of service when the reactor vessel head is removed and the refueling cavity flooded.
(4) One of the two residual heat removal loops may be temporarily out of service to meet surveillance requirements.
4.
Pressurizer Safety Valves a.
At least one pressurizer safety valve shall be operable whenever the reactor head is on the vessel.
b.
Both pressurizer safety valves shall be operable whenever the reactor is critical.
- Mechanical design provisions of the residual heat removal system afford the necessary flexibility to allow an operable residual heat removal loop to con-sist of the RHR pump from one loop coupled with the RHR heat exchanger from the other loop.
Electrical design provisions of the residual heat removal system afford the necessary flexibility to allow the normal or emergency power sourcetobeinoperableortiedtogetherwhenthereactorcoolanttemperature is less than 200 F.
Unit 1 - Amendment No. /4,55,66,97, 15.3.1-2 149 Unit 2 - Amendment No.49,60,71,9E,153
surveillance testing, calibration, or inspection requirements.
The surveillance procedures follow administrative controls which allow for timely restoration of the residual heat removal loop to service if required.
Additionally, with reactor coolant temperature between 350 F and 140 F, all operating decay heat removal pumps (either reactor coolant pumps or residual heat removal pumps) are allowed to be deenergized for a short time (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) with the stipulation that boron dilution activities are not allowed and that core outlet temperature remain 10 F below saturation.
The operation of one reactor coolant pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the reactor coolant system. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.
Each of the pressurizer safety valves is designed to relieve 288,000 lbs per hour of saturated steam at setpoint.
If no residual heat is removed by any of the means available, the amount of steam which could be generated at safety valve relief pressure would be less than half the valves' capacity.
One valve, therefore, provides adequate defense against overpressurization.
Below 350 F and 400 psig in the Reactor Coolant System, the residual heat removal system can remove decay heat and thoreby control system temperature and pressure.
A PORV is defined as OPERABLE if leakage past the valve is less than that allowed in Specification 15.3.1.0 and the PORV has met its most recent channel test as specified in Table 15.4.1-1.
The PORVs operate to relieve, in a con-trolled manner, reactor coolant system pressure increases below the setting of the pressurizer safety valves.
These PORVs have remotely operated block valves to provide a positive shutoff capability should a PORV become inoperable.
l 15.3.1-3c Unit 1 - Amendment No. SI), /,9f,y;i,149 Unit 2 - Amendment No, pf,//,p),$/,153
l The requirement that 100 KW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of offsite power condition to maintain pressure control and natural circulation at hot shutdown.
The requirement to have a reactor coolant system gas vent operable from the reactor vessel or the pressurizer steam space assures that non-condensible gases can be released from the Reactor Coolant System if necessary.
The Reactor Coolant Gas Vent System (RCGVS) provides an orificed vent path from the pressurizer steam space and an orificed vent path from the reactor vessel.
Both vent paths include two parallel solenoid-operated isolation valves which are powered from emergency buses and vent to a common header.
From the common header, gases may be vented via separate lines, each with a single solenoid operated isolation valve powered from the emergency bus to the pressurizer relief tank or containment atmosphere.
The orifice in these vent lines restricts leakage so that, in the event of a pipe break or isolation valve failure, makeup water for the leakage can be provided by a single coolant charging pump.
If a RCGVS vent path from either the pressurizar or reactor vessel head is inoperable, Specification 15.3.1. A.7.c requires the remotely operable valves in that inoperable path to be shut with power removed.
If a vent path from the common header to the pressurizer relief tank or containment atmosphere is inoperable, the isolation valve in that path must be shut but reactor operations may continue, if both vent paths to or both vent paths from the common header are inoperable, the RCGVS is inoperable and the steps in specification 15.3.1.A.7.d must be taken.
d)
FSAR Section 14.1.11.
(2)
FSAR Section 7.2.3, Unit 1 - Amendment No. 9/, 2 3,149 15.3.1-3d Unit 2 - Amendment No. 97.M6.153