ML20210G148
| ML20210G148 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/17/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210G152 | List: |
| References | |
| TAC-59623, TAC-59624, NUDOCS 8609250343 | |
| Download: ML20210G148 (9) | |
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UNITED STATES
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- E WASHINGTON, D. C. 20555 g.....,o DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applTcations for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated August 30, 1985, as supplemented December 13, 1985; July 22, 1985, as supplemented June 12, 1986; and January 10, 1986, as supplemented May 12, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I;
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D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
8609250343 860717 DR ADOCK 05000369 PDR
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to.this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby ~
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 62, are hereby incorporated into the 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
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0 Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 17, 1986
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
Thelpplication for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated August 30, 1985, as supplemented December 13, 1985; July 22, 1985, as supplemented June 12, 1986; and January 10, 1986, as supplemented May 12, 1986, comply with the standards and req)uirements of the Atomic Energy Act of 1954, as amended (the Act and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the 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 Comission's regulations set forth in 10 CFR Chapter I;
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D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
4
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
43, are hereby incorporated into the 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 Y
\\
Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 17, 1986 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT N0.43 FACILITY OPERATING LICENSE N0. 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.
Amended Page 3/4 3-8 3/4 3-79 3/4 4-2 B 3/4 3-5 t
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TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, 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 />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.
ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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MCGUIRE - bdITS 1 & 2 3/4 3-8 AmendmentNo.j(Unit 2)
Amendment No.6 (Unit 1)
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPICABILITY:
MODE 1.
ACTION:
a.
With one stop valve or one governor valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead (s) or isolate thF fur 5ine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Spo.ification 4.0.4 are not applicable.
4.3.4.2 To assure operability of the above required Turbine Overspeed pro-t tection System, an inservice inspection of the various components of this system are carried out in accordance with the " Turbine Overspeed Reliability Assurance Prograa."
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l McGUIRE - UNITS 1 & 2 3/4 3-79 Amendment No.62 (Unit 2)
Amendment No.<43 (Unit 1)
HOT STANDBY
-LIMITING CONDITION FOR OPERATION 3.4.1.2 At least three of the reactor coolant loops listed below shall be OPERABLE and at least two of these reactor coolant loops shall be in operation:*
a.
Reactor Coolant Loop A and its associated steam generator and reactor coolant pump, b.
Reactor Coolant Loop B and its associated steam generator and reactor coolant pump, c.
Reactor Coolant Loop C and its associated steam generator and reactor coolant pump, and d.
Reactor Coolant Loop D and its associated steam generator and l
reactor coolant pump.
APPLICABILITY:- TCDE 3 ACTION:
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a.
With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 />.
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b.
With only one reactor coolant 1 cop in operation, restore at least two loops to operation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or open the Reactor Trip System breakers.
c.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant,
System and immediately initiate corrective action to return the required reactor coolant loop to operation.
SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.2.2 The required steam generators shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 12% at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.2.3 At least two reactor coolant loops shall be verified in operation l
and circulating-reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
"All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
McGUIRE - UNITS 1 and 2 3/4 4-2 Amendment No.62 (Unit 1)
Amendment No.43 (Unit 2)
BASES 3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the -
reactor system and avoid or mitigate damage to reactor system components.
The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentati,on and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessiy.e_overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles.
All Category I struc-tures except the new fuel vault at McGuire, are designed to withstand effects of turbine missiles without any adverse impact on the safety related equipment housed inside (FSAR Section 3.5.2.7 and 10.2.3).
To assure protection against turbine overspeed a " Turbine Overspeed Reliability Program" is implemented.
Tests and inspections associated with this program will be performed in accord-ance with station procedures, maintenance work requests and/or outage work schedules as appropriate. All deviations from the program or deficiencies identified through the specified maintenance, calibration or testing activities are evaluated by Duke Power Company to determine if operability of the system has been affected and appropriate action taken such as correcting the deviation or deficiency, performing compensatory action, or removing the turbine from service.
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McGUIRE - UNITS 1 and 2 B 3/4 3-5 Amendment No. 62 (Unit 1)
Amendment No. 43 (Unit 2)
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