ML20198F019
| ML20198F019 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/06/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198F023 | List: |
| References | |
| NUDOCS 9708110148 | |
| Download: ML20198F019 (10) | |
Text
a ttauq g-t UNITED STATES
- j.
,j NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. - **1 G
4....
4 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 1.icense 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 February 12, 1997, as supplemented on March 11. 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 (1) 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, 97o8110148 970806 PDR ADOCK 05000266 P
' -o; 2,
Accordingly. Facility Operation License No. DPR-24 is hereby amended to approve the relocation of the turbine overspeed protection-specifications, limiting conditions for o)eration, surveillance requirements, and associated bases into tie FSAR by June 30, 1998, as described in the licensee's application dated February 12, 1997, as supplemented on March 11, 1997, and evaluated in the staff's safety evaluation dated August 6, 1997. This license is also hereby 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 Soecifications The Technical Specifications contained in Ap>endices A and B as revised through Amendment No.176, are here)y incorporated in the license.
The licensee shall operate the facility in accordance with Technical Specifications.
3, This license amendment is effective immediately upon issuance and shall be implemented by June 30, 1998.
Implementation of this amendment is the relocation of the turbine overspeed protection specifications, limiting conditions for operation, surveillance requirements, and associated bases into the FSAR as described in the licensee's application dated February 12, 1997, as supplemented on March 11, 1997, and evaluated in the staff's safety evaluation dated August 6,1997.
FOR THE NUCLEAR REGULATORY COMMISSION NL k su n Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 6, 1997
sa tt:0 y
UNITE) STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON D.C. SpeeHopi l
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j WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-27 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated February 12, 1997, as supplemented on March 11. 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 activitie:: 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 regalations and all applicable requirements have been satisfied.
i l 2.
According'ly, Facility Operation License'No. DPR-27 is hereby amended to I
approve the relocation of the turbine overspeed protection specifications, limiting conditions for o)eration, surveillance requirements, and associated bases-into tie FSAR by June 30. 1998, as described in the licensee's application dated February )?.1997, as supplemented on March 11. 1997. and evaluated in the staff's safety evaluation dated August
- 6. 1997. This license is also hereby 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 Soecifications The Technical Specifications contained in Ap)endices A and B. as revised through Amendment No.180. are here)y incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective imediately upon issuance and shall be implemented by June 30. 1998.
Implementation of this amendment is the relocation of the turbine overspeed protection specifications, limiting conditions for operation, surveillance requirements, and associated bases into the FSAR as described in the licensee's application dated February 12. 1997, as supplemented on March 11. 1997.
and evaluated in the staff's safety evaluation dated August 6.1997.
FOR THE NUCLEAR REGULATORY COMMISSION 15 batchtuvv Linda L. Gundrum.-Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office-of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 6, 1997
ATTACHMENT TO LICENSE AMENDMENT NOS.176 AND 180 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical #pecifications 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 15.3.4-2a 15.3.4-2a 15.3.4-2b 15.3.4-2b 15.3.4-2c Table 15.4.1-1 (Page 4 of 6) Table 15.4.1-1 (Page 4 of 6)
Table 15.4.1-2 (Page 2 of 5) Table 15.4.1-2 (Page 2 of 5)
Table 15.4.1-2 (Page 3 of 5) Table 15.4.1-2 (Page 3 of 5)
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 /> time 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 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 />.
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 continue provided the inoperable valve is restored to operable status 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 scutdown 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 operatien 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.
Basis A reactor shutdown from power requires removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the' steam bypass to the condenser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the concenser as feedwater in the steam generator is converted to steam by. heat absorption.
Normally, the capability to return feedwater flow to the steam generators is provided by operation of the; turbine cycle feedwater system.
Unit 1 - Amendment No, MB, M1.176 Unit 2 - Amendment No M7. M5.180 15.3.4-2a
e The eight' main steam safety valves have a total combined rated capability of 6,664,000 lbs/hr, The total full power steam flow is 6,620,000 lbs/hr, therefore eight (8) main steam safety valves will be able to relieve the total full-power steam flow if necessary, In the unlikely event of complete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the availability of either the steam driven auxiliary feedwater pump or one of the two motor-driven auxiliary steam generator feedwater pumps, and steam discharge to the atmosphere via the main steam safety valves or atmospheric relief valves. One motor-driven auxiliary feedwater pump can supply sufficient feedwater for removal of decay heat from 6 unit.
The minimum amount of water in the condensate storage tanks ensures the ability to maintain each unit in a hot shutdown condition for at least one hour concurrent with a loss of all AC power.
An unlimited supply is available from the lake via either leg of the plant service water system for an indefinite time period, Each of the AFW pumps possesses a low suction pressure trip that will protect it should a loss of feedwater occur. Additionally, should a steam generator tube rupture occur. the motor-operated steam admission valves for the turbine-driven AFW pumps serve as isolation boundaries for the affected steam generator.
2 The atmospheric steam dump lines are required to be operable because they are relied upon, following a steam generator tube rupture coincident with a loss of A.C. power, to cool down the Reactor Coolant System to RHR entry
- conditions. An atmospheric steam dump line is considered operabb if it is capable of providing the controlled relief of main steam flow necessary to perform the RCS cooldown.
Isolating an atmospheric steam dump line does not render it inoperable if the line can be unisolated and the RCS can still be cooled down to RHR entry conditions, through local or remote operation, within the time period required by the applicable FSAR accident analyses.
Unit 1 - Amendment No. 443, 447,176 Unit 2 - Amendment No. 447, 4&l.180 15.3.4-2b l
TABLE 15.4.1-1.(continued)
PLANT CONDITIONS-NO. CHANNEL DESCRIPTION CHECK CALIBRATE
_T5T WHEN REQUIRED.
- 36. Radiation Monitoring System D(7)
R(7)
M(7)
ALL 37.
Reactor Vessel Fluid Level System M
R ALL
- 38. - Refueling Water Storage Tank Level R
ALL 39.
Residual Heat. Removal Pump Flow R
ALL
- 40. Safety Valve Position Indicator M
R ALL
- 41. Subcooling Margin Monitor M
R ALL
- 42. Deleted.
43.
Volume Control Tank Level R
ALL
- 44. Reactor. Protection System and' M(1.23)-
ALL Emergency Safety Feature Actuation System logic
- 45. Reactor Trip System Interlocks
-Intermediate Range Neutron Flux. P-6. -
R(24)
R ALL
-Power Range Neutron Flux. P-8 R(24)
R ALL
-Power Range Neutron Flux. P-9 R(24)
R ALL
-Power. Range' Neutron Flux. P-10 R(24)
R ALL
-1st Stage Turbine Impulse. Pressure R(24)
R ALL.
Unit 1 - Amendment No. E5. 49,176 Unit 2 - Amendment No. M9. M1.180 Page 4 of 6 1
__ _ _=_
l ~,
L TABLE 15.4.1-2 (Continued) lest Freauency
- 7. Spent Fuel Pit a) Boron Concentration Monthly b) Water Level Verification Weekly
- 8. Secondary Coolant Gross Beta-gamma Weekly ("
Activ1ty 6r gamma isotopic analysis Iodine concentration Weekly when gross Beta-gamma activity equals or exceeds 1.0 pC1/g("
- 9. Control Rods a) Rod drop times of,)all Each refueling or full length rods after maintenance that could affecg) proper functioning b) Rodworth measurement Following each refueling shutdown prior to commencing power operation
- 10. Control Rod Partial movement of Every 2 weeks""
all rods
- 11. Pressurizer Safety Valves Set point Every five years""
- 12. Main Steam Safety Valves Set Point Every five years""
- 13. Containment Isolation Trip Functioning Each refueling shutdown-
- 14. Refueling System Interlocks Functioning Each refueling-shutdown 15,. Service Water System Functioning Each refueling shutdown-
- 16. Primary System Leakage -
Evaluate Monthly ("
- 17. Diesel Fuel Supply Fuel inventory Daily
- 18. Deleted
- 19. Deleted
- 20. Boric Acid System Storage Tank and Daily""
piping temperatures a tem)erature required by Taale 15.3.2-1 Unit 1 - - Amendment No. 4-74. U3.176
- Unit 2 - Amendment No. -14. -1#,180 Page 2 of 5
TABLE 15.4.1-2 (Continued) lest.
Frecuency
- 21. PORV Block Valves
- a. Complete Valve Cycle Quarterly"3'
- b. Open position check Every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />"*)
- 22. Integrity of Post Accident Evaluate Each refueling cycle Recovery Systems Outside Containment'
- 23. Containment Purge Supply Verify valves are Monthly "'
and Exhaust Isolation locked closed Valves
- 24. Reactor Trip Breakers
- a. Verify independent Monthly ")
operability of automatic shunt and undervoltage trip functions.
- b. Verify independent Each refueling operability of manual shutdown trip to shunt and undervoltage trip functions.
- 25. Reactor Trip Bypass
- a. Verify operability Prior to Breakers of the undervoltage breaker use trip function.
- b. Verify o)erability Each refueling of the slunt trip shutdown functions.
- c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip functions.
26, 120 VAC Vital Instr.
Verify Energizeduri Shiftly Bus Power
- 27. Power Operated Relief Operate"
Each shutdown"5' Valves (PORVs).
PORV Solenoid Air Control Valves, and Air System Check
- 28. Atmospheric Steam Dumps Complete valve cycle Quarterly
- 29. Deleted Unit 1 - Amendment No. %8. 4M 176 Unit 2 - Amendment No. MB. 4Ml180 (Page 3 of 5)