ML20056H437
| ML20056H437 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/07/1993 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H438 | List: |
| References | |
| NUDOCS 9309090319 | |
| Download: ML20056H437 (10) | |
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UNITED STATES O
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[.'fk?2 1{ j NUCLEAR REGULATORY COMMISSION y
WASHINGTON. o.C. 20565KK11
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WISCONSIN ELECTRIC POWER Cone'ANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 141 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 March 30, 1990, 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 1; 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 conmon defense and security or to the health and safety of the public; and E.
The issuance of this amenome.t is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9309090319 930907 ADOCK 05000266 PDR PDR P
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:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 141, 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 Allen G. Hansen, Project M. nager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 7, 1993
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.j NUCLEAR REGULATORY COMMISSION
- 1' WASHINGTON. D C. 20555-0001 g
g WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 145 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 March 30, 1990, 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; 9
B.
The f acility 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. 145, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective inediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR TrlE NUCLEAR REGULATORY COMMISSION
[
Allen G. Hansen, Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 7, 1993 i
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ATTACHMENT TO LICENSE AMENDMENT NOS.141 Af4D 145 TO FACIllTY OPERAflNG 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 marginal lines indicating the area of change.
REMOVE
_I_NSE RT 15.4.5-1 15.4.5-1 15.4.6-1 15.4.6-1 15.4.6-2 15.4.6-2 15.4.6-3 15.4.6-3 15.4.6-4 15.4.6-4 15.6.12-1
15.4.5 EMERGENCY CORE COOLING SYSTEM AND CONTAINMENT COOLING SYSTEM TESTS Applicability:
Applies to testing of the Emergency Core Cooling System and the Containment Cooling System.
Obiective:
1 To verify that the subject systems will respond promptly and perform their design functions, if required.
Specification:
j 1.
System Tests 1
l A.
Safety iniection System i
1.
System tests shall be performed during reactor shutdowns for j
major fuel reloading. The test shall be performed in i
accordance with the following procedure:
1 i
a.
With the Reactor Coolant System pressure less than or j
equal to 350 psig and temperature less than or equal i
to 350*F, a test safety injection signal will be j
applied to initiate operation of the systeu. The i
motor breakers for the safety injection and residual l
heat removal pumps may be placed in the " test" position or racked in and operable for this test.
i 2.
The test will be considered satisfactory if control board
}
indication and visual observations indicate that all i
j components have received the safety injection signal in the proper sequence and timing.
15.4.5 1 Unit 1 - Amendment No.
141 Unit 2 - AT.endment No.
145
.i 15.4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS Appl i c abil i t y l
i Applies to periodic testing and surveillance requirements of the emergency j
power system.
l Obiective To verify that the emergency power system will respond promptly and properly when required.
Specification l
The following tests and surveillance shall be performed as stated:
l j
A.
Diesel Generators i
l 1.
Manually-initiated start of the diesel generator, followed by j
manual synchronization with other power sources and assumption of i
load by the diesel oenerator shall not exceed 2850KW. This test
)
will be conducted monthly with a minimum running time of 30 minutes on each diesel generator. Normal plant operation will not be affected.
l 2.
Automatic start of each diesel generator, load shedding, and 3
restoration to operation of particular vital equipment, initiated by an actual interruption of normal AC station service power i
supplies to associated engineered safety systems busses together l
with a simulated safety injection signal.
In addition, after the l
diesel generator has carried its load for a minimum of 5 minutes,
)
automatic load shedding and restoration of vital loads are tested j
again by manually tripping the diesel generator output breaker.
l This test will be conducted during reactor shutdown for major i
fuel reloading of each reactor to assure that the diesel generator will start and assume required load in accordance with the timing l
sequence listed in FSAR Section 8.2 after the initial starting signal.
i 1
I 15.4.6-1 i
Point Beach Unit 1 Amendment No. /7,91,772,141 Point Beach Unit 2 Amendment No. E2,95,726,145 i
d
l 3.
The proper operation of Emergency Lighting, including the automatic transfer switch for DC lights, will be demonstrated during each reactor shutdown for a major fuel reloading.
4.
Each diesel generator shall be given an inspection, at least annually, following the manufacturer's recomendations for this class of stand-by service.
5.
Each fuel oil transfer pump shall be run monthly.
The above tests will be considered satisfactory if all applicable equipment operates as designed.
B.
Safety-Related Station Batteries These surveillance specifications are applicable to all four safety-related station batteries: DOS, D06, DIOS, and D106; and the safety-related statf or, swing battery D305.
1.
Every month the voltage of each cell (to the nearest 0.05 volt),
the specific gravity and temperature of a pilot cell in each battery and each battery voltage shall be measured and recorded.
2.
Every 3 months the specific gravity, the height of electrolyte, and the amount of water added, for each cell, and the temperature of every fifth cell, shall be measured and recorded.
3.
At each time data is recorded, new data shall be compared with old to detect signs of abuse or deterioration.
4.
Each Safety-Related Station Battery shall be demonstrated OPERABLE:
a.
At least once per 18 months (SERVICE TEST) by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle.
l l
15.4.6-2 Unit 1 - Amendment No. 3,JJD,735.J36,141 Unit 2 - Amendment No. 2 JJ3,J39.J40,145 l
3 I
b.
At least once per 60 months (PERFORMANCE TEST) by verifying that the battery capacity is at least 80% of the manufacturer's rating. This performance discharge test may be performed in lieu of the battery service test.
l c.
Annual performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for_ the l
&;.;:lication. Degradation is indicated when the battery capacity drops more than 10% of rated capacity form its 3
previous performance test, or is below 90% of the manufacturer's rating. When performance tests are required, they may be performed in lieu of the battery service test.
Basis 4
I The tests specified are designed to demonstrate that the diesel generators l
will provide power for operation of equipment. They also assure that the emergency generator system controls and the control systems for the safeguards i
equipment will function automatically in the event of a loss of all normal AC station service power.
The testing frequency specified will be often enough to identify and correct any mechanical or electrical deficiency before it can result in a system failure.
The fuel supply and starting circuits and controls are continuously j
monitored and any faults are alarm indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators 4
themselves on test.
"j Station batteries will deteriorate with time, but precipitous failure is extremely unlikely. The surveillance specified is that which has been
)
demonstrated over the years to provide an indication of a cell becoming i
unserviceable long before it fails.
If a battery cell has deteriorated or if a connection is loo:e, the voltage under load will drop excessively indicating replacement or maintenance.
I 15.4.6-3 l
Unit 1 - Amendment No. DE.141 Unit 2 - Amendment No. H 0,145
l A
d h Service Test, performed at least every 18 months, demonstrates adequate battery capacity to supply power to loads required during the most demanding duty cycle. This design duty cycle occurs upon an actuation of safeguards loads in one unit coincident with a loss of off-site power. The design duty cycle is defined further in FSAR, Section 8.2.
A Performance Test will also be conducted at least every 60 months. The Performance Test is a constant discharge rate capacity test which allows comparison with the manufacturer's rating of the battery. This test is the best indicator of the effects of aging on battery capacity.
Provisions are made in these specifications to change the test periodicity to annual when the battery is degraded or when the battery reaches that point in its service life at which capacity degradation with time is accelerated. Operability is satisfactorily demonstrated by achieving a capacity of at least 80% of the manufacturer's rating.
Since the Performance Test entirely bounds the battery loads applied during a Service Test. when a Performance Test is conducted, the Service Test for that battery's current test cycle may be omitted.
These surveillance specifications are applicable to all five of the safety-related station batteries: 005, D06, DIOS, D106, and the swing battery D305.
DC emergency lights are provided in certain safeguards equipment areas which must be attended to during a loss of all AC power. The emergency lighting test verifies that the automatic transfer switch operates properly and provides DC power to the DC emergency lights.
Reference FSAR, Section 8.2 15.4.6-4 Unit 1 - Amendment No. 126, 141 Unit 2 - Amendment No. J/0,145