ML20202F183
| ML20202F183 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/01/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20202F188 | List: |
| References | |
| NUDOCS 8604140120 | |
| Download: ML20202F183 (7) | |
Text
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o UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
j WASHINGTON. D. C. 20555 s.,.
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DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) 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 (the licensee) dated January 21, 1986 and revised March 17, 1986, and further supported by related let-ters dated September 24, 1985 and February 14, 1986, complies with the standards and requirements 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 conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission, and the duly authorized exemption from Section III.C.2(a) of Appendix J,10 CFR Part 50, issued March 31,1986; 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, except as exempted from compliance with Section III.C.2(a) of Appendix J to 10 CFR Part 50 by exemption issued March 31,1986; 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.
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. 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.53, are hereby incorporated into the license, The licensee shall operate the facility in accordance with the i
Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION Ariginal aigned by:
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- p. Hood B. J. Youngblood, Director j
g PWR Project Directorate #4 l
l Division of PWR Licensing-A l
Attachment:
l Technical Specification Changes Date of Issuance: April 1, 1986 l
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WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
34 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 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated January 21, 1986, and revised March 17, 1986, and further supported by related letters dated September 24, 1985, and February 14, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth i
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 Comission, and the duly authorized exemption from Section III.C.2(a) of Appendix J,10 CFR Part 50, issued March 31,1986; 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, except as exempted from compliance with Section III.C.2(a) of Appendix J,10 CFR Part 50, by exemption issued March 31,1986; 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.
. 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)Technicti Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.34, 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 Original signed by:
/
D. Hood 6
Attachment:
Technical Specification Changes Date of Issuance: April 1, 1986 M if p5(f {rt-MD'u'nda/DpR-A PWR#,4 PWR#4/DPWR-A DELD PWR#4/DPWR-A n:kab DHood
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s ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE N0. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET N0. 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 6-3 3/4 6-4 i
3 I
l
I' CONTAINMENT SYSTEMS t
SURVEILLANCE REQUIREMENTS (Con'tinued)
Three Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at 40 1 10 month intervals during shutdown at either P, 14.8 psig, or' at P, 7.4 psig, during each 10 year service $eriod. Thethirdteltofeachsetshallbeconducted during the shutdown for the 10 year plant inservice inspection; b.
If any periodic Type A test fails to meet either 0.75 L or 0.75 L thetestschedulefor.subsequentTypeAtestsshallbefeviewedanb, approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L or 0.75 L, a Type A test shall be performed at s
least every 18 months until two consecutive Type A tests meet either 0.75 L resume 8;or0.75L at which time the above test schedule may be t
The accuracy of each Type A test shall be verified by a supplemental c.
test which:
1)
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within
- 0. 25 L,, o r 0. 25 LtI 2)
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and 3)
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25% of the total measured leakage at P,,
14.8 psig, or P 7.4 psig.
g d.
Type B and C tests shall be conducted with gas at P, 14.8 psig, at intervals no greater than 24 months except for testl involving:
1 1)
Air locks, 2)
Dual ply bellows assemblies on containment penetrations between the containment building and the annulus, and 3)
Purge supply and exhaust isolation val %es with resilient material seals.
4)
Type C tests performed on containment penetrations M372, M373" without draining the glycol-water mixture from the seats of their diaphragm valves (MF-228A, MF-2338, and MF-234A), if meet-ing a zero indicated leakage rate (not including instrument error) for the diaphragm valves. These tests may be used in lieu of tests which are otherwise required by Section III.C.2(a) of 10 CFR 50, Appendix J to use air or nitrogen as the test medium. The above required test pressure (Pa) and test interval are not changed by this exception.
Purge supply and exhaust isolation valves with resilient material e.
seals shall be tested and demonstrated OPERABLE by the requirem of Specification 4.6.1.9.3 or 4.6.1.9.4, as applicable; Amendment No.
(Unit 1)
McGUIRE - UNITS 1 and 2 3/4 6-3 Amendment No.
(Unit 2)
~
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) f.
The combined bypass leakage rate shall be determined to be less than 0.07 L,for penetrations which are not individually testable; penetra-by applicable Type B and C tests at least once per 24 months except tions not individually testable shall be determined to have no detect-able leakage when tested with soap bubbles while the containment is pressurized to P,, 14.8 psig, or P, 7.4 psig, during each Type A test; t
g.
Air locks shall be tested and demonstrated OPERABLE per Specification 4.6.1.3; h.
The space between each dual ply bellows assembly on containment penetrations between the containment building and the annulus shall be vented to the annulus during Type A tests.
Following completion of each Type A test, the space between each dual ply bellows assembly shall be subjected to a low pressure test at 3-5 psig to verify no detectable leakage or the dual ply bellows assembly shall be subjected to a leak test with the pressure on the containment side of the dual ply bellows assembly at P, 14.8 psig, or P '
t 7.4; psig, to verify the leakage to be wit $in the limits of Specification 4.6.1.2f. ;
i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced Integrated Leakage Measurement System; and i
j.
The provisions of Specification 4.0.2 are not applicable.
l i
Amendment No.
(Unit 1)
McGUIRE - UNITS 1 and 2 3/4 6-4 Amendment No.
(Unit 2)
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