ML20074A335
| ML20074A335 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/03/1983 |
| From: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20074A336 | List: |
| References | |
| DPR-51-A-079, NPF-06-A-046 NUDOCS 8305120506 | |
| Download: ML20074A335 (9) | |
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UNITED STATES (pp e
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 79 License No. DPR-51 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Company
'j (the licensee) dated September 17, 1981, as supolemented March 16, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission's rules and regulations 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; i
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimic'al to the I
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 Conmission's regulations and all applicable requirements have been satisfied.
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8305120506 830503 PDR ADOCK 05000313 p
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. OPR-51 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
l F. Stolz, Chief - >1 J
ND erating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1983
ATTACHMENT TO LICEfiSE AMENDMEriT ?!0. 79 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Page 110z e
4.26 REACTOR BUILDING PURGE VALVES APPLICABILITY This specification applies to the reactor building purge supply and exhaust isolation valves.
OBIECTIVE-To assure reactor building integrity.
SPECIFICATION 4.26.1 The reactor building purge supply and exhaust isolation valves shall be determined closed at least once per 31 days when containment integr,ity is required by TS 3.6.1.
4.26.2 Prior to exceeding conditions which require establishment of reactor building integrity per TS 3.6.1, the leak rate of the purge supply and exhaust isolation valves shall be verified to be within acceptable limits per TS 4.4.1, unless the test has been successfully completed within the last three months.
BASES
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Determination of reactor building purge valve closure will ensure that reactor building integrity is not unintentionally breeched.
As a result of Generic Issue B-20, " Containment Leakage Due to Seal Deterioration," it was concluded that excess leakage past valve resilient seals is, typically caused by severe environmental conditons and/or wear due to use.
Recommended leak test frequencies of three months are deemed to be acequate to detect seal degradation of resilient seals.
The three month test need not be conducted with the precision of the Type C 10CFR50, Appendix J criteria, however the test must be sufficient to detect degradation.
110Z Amendnent flo. 55, 79 r
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.t WASHINGTON, D. C. 20555 ARKANSAS POWER & LIGHT COMPANY DOCKET N0. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by Arkansas Power & Light Company (the' licensee) dated March 12, 1982, as supplemented March 16, 1983, complies with the standards and requirements of the Atomic Enercy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
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 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; D.
The issuance 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.
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2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. HPF-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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_yf-Robert A. Clark, Chief c
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Operating Reactors Branch #-3 L
Division of Licensing Attachnent:
Changes to the Technical SDecifications Date of Issuance: May 3, 1983 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE N0. NPF-6 DOCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The i
corresponding overleaf page is provided to maintain document completeness.
1 Page 3/4 6-17 a#
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CONTAINMENT _ SYSTEMS i
SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 E'ach isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position.
4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.1.4 Prior to exceeding conditions which require establishment of reactor building integrity per TS 3.6.1.1, the leak rate of the contain-ment purge supply and exhaust isolation valves listed in Table 3.6-1 Part B shall be verified to be within acceptable limits per TS 4.6.1.2, unless the j
test has been successfully completed within the last three months.
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l ARKANSAS-UNIT 2 3/4 6-17 Aacndment llo. 4G l
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l TABLE 3.6-1 g
h CONTAINMENT ISOLATION VALVES s
m PENETRATION ISOLATION E
NUMBER VALVE NUMBER FUNCTION TIME (SEC)
--i ro A.
CONTAINMENT ISOLATION 2P7 2CV-5852-2#
"A" S/G Sample Isolation (outside)
< 20 2CV-5859-2#
"B" S/G Sample Isolation (outside)
{ 20 2P8 2SV-5833-1 RCS & Pressurizer Sample Isolation (inside) 102 2SV-5843-2 RCS & Pressurizer Sample Isolation (outside) 10 2
2P9 2CV-6207-2 II.P. Nitrogen to SI Tanks (outside) 1 20 2P14 2CV-4821-1 CVCS L/D Isolation (inside) 1 35 2CV-4823-2 CVCS L/D Isolation (outside) 1 20 2P18 2CV-4846-1 RCP Seal Return Isolation (inside)
< 25 M
2CV-4847-2 RCP Seal Return Isolation (outside) 7 20 l
2P31 2CV-2401-1 Containment Vent Ileader (inside) 7 20
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2CV-2400-2 Containment Vent Header (outside) 7 20 E
2P37 2SV-5878-1 Quench Tank Liquid Sample (inside) 5 20 2SV-5871-2 Quench Tank Liquid Sample (outside) 1 20 2SV-5876-2 SI Tanks Sample Isolation (outside) 1 20 2P39 2CV-4690-2 Quench Tank Makeup & Demin Water Supply R
Isolation (outside)
< 20 2P40 2CV-3200-2 Fire Water Isolation (outside) 7 20 R
2P41 2CV-6213-2 L.P. Nitrogen Supply Isolation (outside) 5 20 2P51 2CV-3852-1 Chilled Water Supply Isolation (outside) 1 20
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2P52 2CV-5236-1 CCW to RCP Coolers Isolation (outside) 1 20'
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Er 2P59 2CV-3850-2 Chilled Water Return Isolation (inside) 1 20 2CV-3851-1 Chilled Water Return Isolation (outside) 1 20 2
2P60 2CV-5254-2 CCW from RCP Coolers Isolation (inside) 1 20 2CV-5255-1 CCW from RCP Coolers Isolation (inside) 1 20.
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