ML20059G754
| ML20059G754 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/28/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059G757 | List: |
| References | |
| NUDOCS 9009130135 | |
| Download: ML20059G754 (7) | |
Text
{{#Wiki_filter:O ~, 1 i ' einao, f n ]d UMTE D STATES I a- [* / NUCLE AR REGULATORY COMMISSION -{ r,. nswiwotow. o. c. rosso I%....*+! l ) DUKE POWER COMPANY DOCKET NO. 50-369 l McGUIRE NUCLEAR STATION UNIT 1 l AMENDMENT TO FACILITY OPERATING LICENSE I l t Amendment No. 111 License No. NPF-9 l
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The Nuclear Regulatory Comission (the Comission) has found that: l. } A. The app (lication for anendment to the McGuire hoclear Station,the facility) F Unit 1 by the Duke Power Company (the licensee) dated February 20, 1990, complies with the standards and requirenents of the Atomic Energy Act -of 1954, as amended (the Act), and the Commission's rules and - i regulations as set forth in 10 CFR Chapter I; 1 1 l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Consnission; C. There is reasonable assurance (1) that the activities authorized by t this anendment can be conducted without endangering the health and safetyofthepublic,and(ii)thatsuchactivitieswillbeconducted in compliance with the Commission's regulations set forth in 10 CFR r ' Chapter I, D. The issuance of this arendment will not be inimical to the consnon defense and security or to the health and safety of the public; and i E. The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. ? ? 9009130135 900928 ADOCK0500gg9 DR
l - l 2. Accordingly, the license is hereby amendeo by page changes to the Technical l Specifications as indicated in the attachment to this license amendnent, 6r.d Paragraph 2.C.(2) of Facility Operating License No. NPF-g is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 111, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the i Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION l ht c u David D. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Rtgulation
Attachment:
Technical Specification Changes i Date of Issuance: August 28, 1990 i L l-I 1 i
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%.....l ii ,,D DUKE POWER COMPANY DOCKET NO. 50-370 c l McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 i i License No. NPF-17 1 1 1. The Nuclear Regulatory Comission (the Comission) has found that: The app (lication for amendment to the McGuire Nuclear Station,the faci; A. Unit 2 by the Duke Power Company (the licensee) dated February 20, 1990, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and i regulations as set-forth in 10 CFR Chapter I; j B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 q Chapter I; L - 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 i E. The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all epplicable requirements have been satisfied, j i t il a v... ,,,-.m., ._,._m. _, _ ____ __ __.__ _. _ _ _ _ _. _ _ _ _ _ _ _ __ _ _ _
l ..s 2-1 2. Accordingly, the licenser is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, i and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby j anended to read as follows: i ) Technical Specifications l The Technical Specifications contained in Appendix A, as revised j through Amendnent No. 93 are hereby incorporated into the license. The licensee shall operate the facility in accordance with the .'i Technical Specifications and the Environmental Protection Plan. ) 3. This license amendnent is effective as of its date of issuance. ] FOR THE NUCLEAR REGULATORY COMMIS$10N l j 'te ? l David B. Matthews, Director Project Directorate !!-3 Division of Reactor Projects-1/II l Office of Nuclear Reactor Regulation
Attachment:
p Technical Specification j Changes 1 Date of Issuance: August 28, 1990 j i I e 1 l I l l. i l __- 1 l: I 1 l j
-1 i ATTACHPENT TO LICENSE AMENDMENT NO. 111-FACILITY OPERATING LICENSE NO. NPF i DOCKET NO. 50-369 A3E TO LICENSE AMENDMENT NO. 93 ~ FACILITY OPERATING LICENSE NO. NPF-17 D0CKET NO. 60-370 - Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contain vertical lines indicating the areas of change. i Remove'Page Insert Page 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 f f f t i P 7 .m .--e.---.
1 p ' CONTAINMENT SYSTEMS-j,. SURVEILLANCE REQUIREMENTS (Continued) [' a. Three Type A tests (Overall Integrated Containment Leakage Rate) 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 1 t service $eriod. Thethirdtektofeachsetshallbeconducted L during the shutdown for the 10 year plant inservice inspection;* l b. -If.any periodic Type A test fails to meet either 0.75't or 0.75 L i thetestscheduleforsubsequentTypeAtestsshallbefeviewedanb, 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 leastevey18monthsuntiltwoconsecutiveTypeAtestsmeeteither 0.75 L resume 8;or0.75L at which time the above test schedule may be g c. The accuracy of each Type A test shall be verified by a supplemental 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 O.25 L,, or 0.20 L ; g 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, t d. Type B and C tests shall be conducted with gas at P, 14.8 psig, at intervalsnogreaterthan24monthsexceptfortestlinvolving: 1) Air locks, 2) Dua'-ply bellows assemblies on containment penetrations be; ween the containment building and the annulus, and 3) Purge supply and exhaust isolation valves 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 (NF-228A, NF-233D, and NF-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 othc wise required by Section III.C.2(a) s D of 10 CFR 50, Appendix J to use air or nitrogen as the test l
- They Type A test on Unit I which is scheduled for the 10 year ISI outage (EOC 7, 1991) will be performed instead during the E00 6 outage (1990).
The 40~1 10 month interval will be maintained. This constitutes an exemption to + 10 CFR 50, Appendix J Paragraph III.D.1.(a). I Amendment No.111(Unit 1) McGUIRE - UNITS 1 and 2 3/4 6-3 Amendment No. 93(Unit 2) i s
9 . i I CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i medium. The above required test pressure (Pa) and test interval are not changed by this exception. e. Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.9.3 or 4.6.1.9.4, as applicable; 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; l g g. Air locks shall be tested and demonttrated 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 i 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 benows assembly at P, 14.8 psig, or P ' i t 7.4; psig, t:0verifytheleakagetobewit81nthelimitsof Specificativa 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 j. The provisions of Specification 4.0.2 are not applicable. i i i Amendment No.111 (Unit 1) McGUIRE - UNITS 1 and 2 3/4 6-4 Amendment No. 93 (Unit 2) y}}