ML20073E195
| ML20073E195 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/23/1994 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073E196 | List: |
| References | |
| NUDOCS 9409280292 | |
| Download: ML20073E195 (8) | |
Text
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y-UNITED STATES y Y.
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f WASHINGTON, D.C. 205W0001 9.....,o WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.153 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 August 9, 1994, as supplemented on August 19, 1994, 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 O.
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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9409280292 940923 PDR ADOCK 05000266 P
PDR 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:
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 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g./,
c Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 23, 1994 l
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UNITED STATES j. kit (), j NUCLEAR REGULATORY COMMISSION N1 t
WASHINGTON, D.C. 2055HK101 o
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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 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 August 9, 1994, as supplemented on August 19, 1994, complies with the standards and requirements of the 3
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 i
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.
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Accordingly, the license is amended by changes to the Technical
. Specifications as indicated in the attachment to this license l
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.157, 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 M
j Allen G. Hansen, Project Manager Project Directorate III-3 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachment.
Changes to the Technical Specifications Date of issuance:
September 23, 1994 l
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A ATTACHMENT TO LICENSE AMENDMENT NOS.153 AND 157 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 marginal lines indicating the area of change.
REMOVE INSERT TS 15.3.3-6 TS 15.3.3-6 TS 15.3.4-2a TS 15.3.4-2a 15 15.3.7-3 TS 15.3.7-3
a.
Four service water pumps are operable.*
l b.
All necessary valves, interlocks and piping required for the func-tioning of the Service Water System during accident conditions are also operable.
2.
During power operation, the requirements of 15.3.3.D-1 may be modified to allow one of the following components to be inoperable at any one time.
If the system is not restored to meet the conditions of 15.3.3.0-1 within the time period specified, both reactors will be placed in the hot shut-down condition.
If the requirements of 15.3.3.D-1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, both reactors shall be placed in the cold shutdown condition.
a.
Oca of the four required service water pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
One of the two loop headers may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A valve or other passive component may be out of service provided c.
repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Basis The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature, by running the reactor coolant pumps.
The reactor is then made critical by withdrawing control rods and/or diluting boron in the coolant.* With this mode of start-up, the energy stored in the reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore to be conservative most engineered safety system components and auxiliary cooling systems, shall be fully operable.
During low temperature physics tests there is a negligible amount of stored energy in the reactor coolant, therefore an accident comparable in severity to the Design Basis Accident is not possible, and the engineered safety systems are not required.
During the Unit 2 1994 refueling outage, one train B service water pump operating with power supplied by the Alternate Shutdown System, B08/B09 480 volt buses, may be considered operable from a normal (offsite) power supply, under the provisions of Technical Specification 15.3.0.C.
Unit 1 - Amendment No.),9),153 15.3.3-6 Unit 2 - Amendment No.3,P5,157
2.
Single Unit Operation - One of the three operable auxiliary feedwater pumps associated with a unit may be out-of-service for the below specified times. The turbine driven auxiliary feedwater pump may be out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine driven auxiliary feedwater pump cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> f rie period, the reactor shall be in hot shutdown within the next' 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Either one of the two motor driven auxiliary feedwater pumps may be_ out-of-service for up to 7 days.* If the motor driven i
j auxiliary feedwater pump cannot be restored to service within that 7 day period the operating unit shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t D. The main steam stop valves (MS-2017 and MS-2018) and the non-return check-valves (MS-2017A and MS-2018A) shall be operable.
If one main steam stop valve or non-return check valve is inoperable but-open, power operation may
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continue provided the inoperable valve is restored to operable status I
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise the reactor shall be placed in a hot shutdown
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condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With one or more main steam stop valves or non-return check valves inoperable, subsequent operation in the hot shutdown condition may proceed provided the inoperable valve or valves are maintained closed. An inoperable main steam stop valve or non-return check valve may however, be opened in the hot shutdown condition to cool down the affected unit and to perform testing to confirm operability.
E. The crossover steam dump system shall be operable.
If the crossover steam dump system is determined to be inoperable, reduce power to less than 480_
'j MWe (gross) within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
i F. During power operation, at least one of the turbine overspeed protection systems that trip the turbine stop valves or shut the turbine governor valves shall be operable.
If all three systems are determined to be inoperable, isolate the turbine from the steam supply within the next six l
t hours.
i During the Unit 2 1994 refueling outage, P-388, the Train B motor driven auxiliary feedwater pump, may be out-of-service for up to 12 days.
Unit 1 - Amendment No.J33,Jf3,7f7, 15.3.4-2a dNt2-AmendmentNo.J37,Jf7,J3J, 157 i
associated diesel generator.
The applicable Limiting Conditions for Operation of the equipment removed from service shall be entered for the operating unit.
- 2) A single train of spent fuel cooling is adequate to cool the spent fuel pool.
- 3) The required redundant shared engineered safety features for the other unit are operable.
f.
The normal power supply or standby emergency power supply to Unit 1 A05/B03 or Unit 2 A06/B04 may be out-of-service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or.after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter. If the normal power supply is out-of-service, an operable emergency diesel generator is supplying the' affected 4160/480 Volt buses. After 7 days, both units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
g.
The normal power supply or standby emergency power supply 's Unit 1 A06/B04 or Unit 2 A05/B03 or both may be out-of-service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.
If the normal power supply is out-of-service, an operable emergency diesel generator is supplying the affected 4160/480 Volt buses. After 7 days, the affected unit or units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
h.
The normal power supply or standby emergency power supply to Unit I A05/B03 and Unit 2 A05/B03, or Unit 1 A06/B04 and Unit 2 A06/B04 may be out-of-service for a period not exceeding 7* days'provided the required
(
redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j
before or after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.
If j
the normal power supply is out-of-service, an operable emergency diesel During the Unit 2 1994 refueling outage, standby emergency power to Unit 1
1 A06/B04 and Unit 2 A06/B04 may be out-of-service for up to 12 days.
Unit 1 - Amendment No. 84,87,J34,136,15.3.7-3 lb' [ 'Nmendment No. 88,92,138,140, JEZ,156,157
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