ML20058N005
| ML20058N005 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/27/1993 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058N009 | List: |
| References | |
| NPF-06-A-150 NUDOCS 9310070270 | |
| Download: ML20058N005 (7) | |
Text
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UNITED STATES 3.I!.L[~]
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20556-0001 o
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated May 7, 1993, complies with the standards and requirements of the 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 common defense and security or to the health and safety of the public; and j
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.
1 9310070270 930927 PDR ADOCK 0500 8
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' 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 150, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fy1%
Harry Roo, Acting Director Project Directorate IV-I Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 27, 1993 1
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ATTACHMENT TO LICENSE AMENDMENT NO.150 FACILITY OPERATING LICENSE NO NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 7-2 3/4 7-2 B 3/4 7-1 B 3/4 7-1 B 3/4 7-2 B 3/4 7-2 l
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1 i
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITTON FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 3.7-5.
APPLICABILITY:
MODES 1, 2 and 3*.
ACTION:
With both reactor coolant loops and associated steam generators a.
in operation and with one or more main steam line code safety valves inoperable. operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Linear Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, 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 />.
b.
With one reactor coolant loop and associated steam generator in operation and with one or more main steam line code safety valves associated with the operating steam generator inoperable, operation in MODES 1, 2 and 3 may proceed provided:
1.
That at least 2 main steam line code safety valves on the non-operating steam generator are OPERABLE, and 2.
That within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Linear Power Level-High trip setpoint is reduced per Table 3.7-21 otherwise 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 SHUTDOVN 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 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
- Except that during hydrostatic testing in Mode 3 eight of the main steam line code safety valves may be gagged and two (one on each header) may be reset for the duration of the test to allow the required pressure for the test to be attained.
The Reactor Trip Breakers shall be open for the duration of the test.
ARKANSAS - UNIT 2 3/4 7-1 Amendment No. 83,134
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TABLE 3.7-1 7
MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGli TRIP SETPOINT WITH INOPERABLE E
STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS ti N
Maximum Allowable Linear Maximum Number of Inoperable Safety Power Level-High Trip Setpoint Valves on Any Doeratine Steam Generator (Percent of RATED THERMAL POWER) 91.0 67.7 45.0 M>
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l 3/4.7 PLANT SYSTEMS 0
i BASES 3/4.7.1 TURBINE CYCLE t
3/4.7.1.1 SAFETY CYCLES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1100 psia during the most severe anticipated system l
operational transient.
The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an E
assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. The "as-found" requirements are conservative with respect to Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition, and Addenda through 1987. The total relieving capacity for all MSSVs is 14,804,000 lb/hr. The ANO-2 full power (100%) steam flow plus 2% for conservatism is 12,950,000 lb/hr.
Therefore, the total relieving capacity of the MSSVs is 114.32% of the 102% power steam flow through each main steam header. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of-the Power Level-High channels. The reactor trip setpoint reductions are derived on the following bases:
~
SP =
x (114.32%)
l where:
=
reduced reactor trip setpoint in percent of RATED THERMAL POWER ARKANSAS - UNIT 2 B 3/4 7-1 Amendment No. 144h,150
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l PLANT SYSTEMS BASES 114.32% =
Total maximum safety valve relieving capacity of 102% power steam flow X
Total relieving capacity of all safety valves per steam
=
line in 1bs/ hour Y
=
Total Maximum relieving capacity of the inoperable safety valve (s) in Ibs/ hour.
In each case, the valves with the greatest relieving capacity were assumed inoperable.
3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM The OPERABILITY of the emergency feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a total loss of off-site power, Each emergency feedwater pump is capable of delivering a total feedwater flow of 485 gpm at a pressure of 1100 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F when the shutdown cooling system may be placed into operation.
3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for one hour with steam discharge to atmosphere with concurrent with total loss of off-site power. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
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t ARKANSAS - UNIT 2 B 3/4 7-2 Amendment No.'150
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