ML20082V107
| ML20082V107 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/02/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19268E518 | List: |
| References | |
| TAC-52390, TAC-52391, NUDOCS 8312190402 | |
| Download: ML20082V107 (7) | |
Text
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DUKE POWER COMPANY DOCKFT NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 27 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 by the Duke Power Company (licensee) dated September 22 and supplemented October 26, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commis-sion'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 Commission; C.
Thers 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be ininical to the common defense and security or to the health and safety of the public; 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 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:
8312190402 831202 PDR ADOCK 05000369 P
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! (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment was effective October 26, 1983.
l FOR THE NUCLEAR REGULATORY COMMISSION f2 Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Change Date of Issuance: December 2, 1983
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e DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 8 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 i
(the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated September 22 and supplemented October 26, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comis-sion'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: (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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public;-
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.
- 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. 8, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment was effective October 26, 1983.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Change Date of Issuance: December 2, 1983 i
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l-ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET N0. 50-369 AND TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 l
i Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and l
contain a vertical line indicating the area of change. The corresponding over-leaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4. 6-13 3/4 6-14' t
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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall be maintained:
a.
Between 75* and 100*F in the containment upper compartment, and b.
Between 100* and 120*F*** in the containment lower compartment.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the containment average air temperature not conforming to the above limits, restore the air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 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 />.
SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The primary containment upper compartment average air temperature shall be the weighted average ** of ambient air temperature monitoring stations located in the upper compartment.
Temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the elevation of 826 feet at the inlet 7f each upper containment ventilation unit.
4.6.1.5.2 The primary containment lower compartment average air temperature shall be the weighted average ** of ambient air temperature monitoring stations located in the lower compartment.
Temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the elevation of 745 feet at the inlet of each lower containment ventilation unit.
^ Lower limit may be reduce'd to 60*F in MODES 2, 3, and 4.
- The weighted average is the sum of each temperature multiplied by its respective containment volume fraction.
In the event of inoperative tem-perature sensor (s), the weighted average shall be'taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of service.
- Containment lower compartment temperature may be between 120 and 125*F for up to 90 cumulative days per calendar year provided the lower compartment temperature average over the previous 365 days is less than 120*F.
Amendment No. 8 (Unit 2)
McGUIRE - UNITS 1 and 2_
3/4 6-13 Amendment No27 (Unit 1)
CONTAINMENT SYSTEMS l
CONTAINMENT VESSEL STRUCTURAL INTEGRITY 1
LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel.
This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other abnormal degradation.
Any abnormal degra-dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission pursuant to Specification 6.9.1.
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McGUIRE - UNITS I and 2 3/4 6-14