ML20138J952
| ML20138J952 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/07/1997 |
| From: | Kalman G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138J955 | List: |
| References | |
| NUDOCS 9705090215 | |
| Download: ML20138J952 (5) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C.~20066-0001
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l ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 189 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendmen' by Entergy Operations, Inc. (the licensee) dated April 11, 1997, as supplemented by letter dated May 2,1997, complies with the standards and requirements of the l
Atomic Energy Act of 1954, as amended (the Act), and the Commission'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; 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 license amendment will not be inimical 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 Commission's regulations and all applicable requirements have been satisfied.
i 9705090215 970507 PDR ADOCK 05000313 P
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I 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, I
l and Paragraph 2.C.(2) of Facility Operating License No. DPR-51 is hereby t
amended to read as follows:
l 2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. ~189, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
I 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George Kalm or Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7,1997
j ATTACHMENT TO LICENSE AMENDMENT NO.
189
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4 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 1
i Replace the following page of the Appendix "A" Technical Specificctions with the attached page. The revised page is identified by Amendment number and contains a vertical line to indicate the area of change.
REMOVE PAGE INSERT PAGE 27 27 110ml 110ml i
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3.1.6 Le:kcga l
Sp;cifiestien 3.1.6.1 If the total reactor coolant leakage rate exceeds 10 gpm, the reactor shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.2 If unidentified reactor coolant leakage (exceeding normal evaporative losses) exceeds 1 gpm or if rny reactor coolant leakage is evaluated as unsafe, the reactor shall be shut-down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.3.a If it is determined that any reactor coolant leakage exists through a non-isolable fault in a reactor coolant system strength boundary (such as the reactor vessel, piping, valve body, etc., except steam generator tubes), the reactor shall be shutdown and a cooldown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.3.b If the leakage through the tubes of any one steam generator equals or exceeds 500 gallons per day (0.347 gpm)*, a reactor l
shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shall be in the cold shutdown condition within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- This limit has been reduced to 144 gallons pe; Jay (0.1 gpm) for the remainder of cycle 14.
3.1.6.4 Deleted 3.1.6.5 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detection. The nature, as well as the magnitude of the leak, shall be considered in this evaluation. The safety evaluation shall assure that the exposure of offsite personnel to radiation is within the guidelines of 10CFR20.
3.1.6.6 If reactor shutdown is required per Specification 3.1.6.1, 3.1.6.2, or 3.1.6.3 the reactor shall not be restarted until the leak is repaired or until the problem is otherwise corrected.
3.1.6.7 when the reactor is at power operation, three reactor cool-ant leak detection systems of different operating principles shall be in operation. One of these systems is sensitive to radioactivity and consists of a radioactive gas detector and an air particulate activity detector. Both of these instru-ments may be out-of-service simultaneously for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided two other means are available to detect leakage and reactor building air samples are taken and analyzed in the laboratory at least once per shifts other-wise, 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 />.
3.1.6.8 Loss of reactor coolant through reactor coolant pump seals and system valves to connecting systems which Amendment No. M, cM,M4,H4,189 27
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Unsnrvic-rblo describes th3 c:nditien of a tube if it lonks er cantains a defcct 1crga cntugh to offset its structurcl integrity in the event of an operating Basis F.arthqusk3, o loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.18.4.c.
I 9.
Tube Inspection means an inspection of the steam generator i
J tube from the point of entry completely to the point of exit.
j b.
The steam generator shall be determined operable after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.18-2 with the following exceptions j
Tubes with intergranular attack indications within the upper tube sheet with the potential of through-wall depths greater than the plugging limit may remain in service for the remainder of cycle 14.
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i 1.mendment No. 44,4,44,M6,M4,189 110ml 1