ML20149F448
| ML20149F448 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/02/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149F452 | List: |
| References | |
| NUDOCS 9408100253 | |
| Download: ML20149F448 (11) | |
Text
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n UNITED STATES l'
NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555-0001
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DUKE POWER COMPANY DOCKET NO. 50-369 1
McGUIRE NVCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 146 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed i
by the Duke Power Company (licensee) dated May 5,1994, as supplemented June 13, 1994, complies with the standards and i
requirements of the Atomic Energy Act of 1954, as amended (the Ac.t), and the Commission's rules and regulations as 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 f
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be canducted in compliance with the Commission's regulations set i
forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common i
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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I 9408100253 940002 PDR A00CK 05000369 P
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 146, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection P1an.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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H r ert N. Berkow, Director roject Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
August 2, 1994
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UNITED STATES 5 %[@ f 2 NUCLEAR REGULATORY COMMISSION
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wassisorow, o.c. ross5-oooi DUKE POWER COMPANY l
DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT T0.7ACILITY OPERATING LICENSE 1
Amendment No. 128 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated May 5, 1994, as supplemented June 13, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the i
Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rulen and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conductect without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuar.ce 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 i
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-17 is hereby amended to read as follows:
Technical Specifications 1
The Technical Specifications contained in Appendix A, as revised through Amendment No.128
, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Her rt N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 2, 1994
r ATTACHMENT TO LICENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 t
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TO LICENSE AMENDMENT NO.128 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8 3/4 7-1 3/4 7-1 3/4 7-3 3/4 7-3 8 3/4 4-2 B 3/4 4-2 B 3/4 7-1 B 3/4 7-1 4
i l
o REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer Code safety valve shall be OPERABLE with a lift setting of 2485 psig + 3%, - 2%.
- l APPLICABILITY: MODES 4 and 5.
ACTION:
With no pressurizer Code safety valve OPERABLE, immediately suspend all opera-tions involving positive reactivity changes and place an OPERABLE RHR loop into operation in the shutdown cooling mode.
SURVEllLANCE RE0VIREMENTS 4.4.2.1 No additional requirements other than those required by Specification 4.0.5.
Following testing, lift settings shall be within i 1%.
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- The lift setting pressure shall correspond to ambient conditions of the valve
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at nominal operating temperature and pressure.
McGUIRE - UNITS 1 and 2 3/4 4-7 Amendment No.146 (Unit 1)
Amendment No.128 (Unit 2)
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REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig + 3%, - 2%.
- l APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.2 No additional requirements other than those required by Specification 4.0.5.
Following testing, lift settings shall be within i 1%.
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- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
McGUIRE - UNITS I and 2 3/4 4-8 Amendment No.146 (Unit 1)
Amendment No.128 (Unit 2)
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1 PLANT SYSTEMS i
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE l
SAFETY VALVES l
LIMITING CONDITION FOR OPERATION t
3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-3.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With four reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that l
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i b.
With three reactor coolant loops and associated steam generators in j
operation and with one or more main steam line code safety valves i
associated with an operating loop inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-2; other-wise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.
Following testing, lift settings shall be within i 1%.
McGUIRE - UNITS 1 and 2 3/4 7-1 Amendment No. 146 (Unit 1)
Amendment No. 128 (Unit 2)
TABLE 3.7-3 M
E STEAM LINE SAFETY VALVES PER LOOP 5
VALVE NUMBER LIFT SETTING (t 3%)*
ORIFICE SIZE E
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Loop A Looo B Loop C Loop D 2
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1.
SV 20 SV 14 SV 8 SV 2 1170 psig 12.174 in 2
2.
SV 21 SV 15 SV 9 SV 3 1190 psig 12.174 in 2
3.
SV 22 SV 16 SV 10 SV 4 1205 psig 16.00 in 2
4.
SV 23 SV 17 SV 11 SV 5 1220 psig 16.00 in z
5.
SV 24 SV 18 SV 12 SV 6 1225 psig 16.00 in R.
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w FE 8e RR 88 ee CZ co m EE E. S.
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- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
BASES 3/4.4.2 SAFETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.
Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at the valve Setpoint.
The relief capacity of a single safety valve is adequate to relieve any overpres-sure condition which could occur during shutdown.
In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides i
overpressure relief capability and will prevent RCS overpressurization.
In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.
During operation, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.
The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no Reactor trip until the first Reactor Trip System Setpoint is reached (i.e., no credit is taken for a direct Reactor trip on the loss of load) and also assuming no operation of the power-operated relief valves or steam dump valves.
Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
Specifications 3.4.2.1 and 3.4.2.2 allow a + 3% and - 2% setpoint tolerance for OPERABILITY; however, the valves are reset to i 1% during surveillance testing to allow for drift.
3/4.4.3 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady-state envelope of operation assumed in the SAR. The limit is consistent with the initial SAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation.
The maxi-mum water volume also ensures that a steam bubble is formed and thus the RCS is j
not a hydraulically solid system. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.
I McGUIRE - UNITS 1 AND 2 B 3/4 4-2 Amendment No.146 (Unit 1)
Amendment No.128 (Unit 2)
l 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the Secondary Coolant System pressure will be limited to within 110% of its design pressure of 1185 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a Turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. Table 3.7-3 allows a i 3% setpoint tolerance for OPERABILITY; however, the valves are reset to i 1% during surveillance testing to allow for drift.
The total relieving capacity for all valves on all of the steam lines 6
is15.9xj0 lbs/hr which is 105% of the total secondary steam flow of 15.14 x 10 lbs/hr at 100% RATED THERMAL POWER.
A minimum of two OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Tables 3.7-1 and 3.7-2.
1 STARTUP and/or POWER OPERATION is allowable with safety valves inoperable l
within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the reduced Reactor Trip Settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived nn the following bases:
For four loop operation:
3p, (X) - (Y)(V) x (109).
For three loop operation:
SP - (X) - (Y)(U) l x F).
Where:
SP = Reduced Reactor Trip Setpoint in percent of RATED THERMAL POWER, V - Maximum number of inoperable safety valves per steam line, V - Maximum number of inoperable safety valves per operating, steam line McGuire - UNITS 1 and 2 B 3/4 7-1 Amendment No. 146 (Unit 1)
Amendment No. 128 (Unit 2)
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