ML20045G238
| ML20045G238 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/28/1993 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045G239 | List: |
| References | |
| NPF-06-A-148 NUDOCS 9307130081 | |
| Download: ML20045G238 (5) | |
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UNITED STATES
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 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 February 24, 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 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.
9307130081 930628 PDR ADOCK 05000368 P
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. 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. NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.148, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR JHE, NUCLEAR REGULATORY COMMISSION
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Terence L. Chan, ActiYg' f 6
f DirecEo7 Project Directorate IV-I Division of Reactor Project.c - III/IV/V Office of Nuclear Reactor Regit ation fttachment:
Changes to the Technical Specifications Date of Issuance: June 28, 1993 2
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ATTACHMENT TO LICENSE AMENDMENT NO. 148 FACILITY OPERATING LICENSE NO NPF-6 DOCKET N0. 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 5-5 3/4 5-5 8 3/4 5-2 8 3/4 5-2 i
i EMERGENCY CQRE COOLING SYSTEMS SURVEIf1ANCE REOUIRF,ggiTS (Continued)
- f. By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:
)
- 1. High-Pressure Safety Injection pump 2 1360.4 paid with 90*F water.
- 2. Low-Pressure Safety Injection pump 2 156.25 psid with 90'F water.
- g. By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
- 1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
- 2. At least once per 18 months.
HPSI Systgm LPSI Systgm Valve Number Valve Number a.
2CV-5035-1 a.
2CV-5037-1 b.
2CV-5015-1 b.
2CV-5017-1 c.
2CV-5075-1 c.
2CV-5077-2 d.
2CV-5055-1 d.
2CV-5057-2 e.
2CV-5036-2 f.
2CV-5016-2 g.
2CV-5076-2 h.
- h. By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystem that alter the subsystem flow characteristics and verifying the following flow rates:
HPSI System - Sinele Pump LPSI System - Sinele Pumo The sum of the injection line a.
Injection Leg 1, 2 1059 gpm flow rates, excluding the b.
Injection Leg 2, 2 1059 gpm highest flow rate is greater c.
Injection Leg 3, 2 1059 gpm than or equal to 570 gpm.
d.
Injection Leg 4, 2 1059 gpm ARKANSAS - UNIT 2 3/4 5-5 Amendment No. #A,148
s EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tava < 300'F LIMITING CONDITION FOR OPERATION' 3.S.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
One OPERABLE high-pressure safety injection pump, and b.
An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sunp on a Recirculation Actuation Signal.
APPLICABILITY: MODES 3* and 4.
ACTION:
a.
With no ECCS subsystem OPERABLE. restore at losst one ECCS subsystem te OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTOOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
In the event the ECCS is actuated and injects water inte the Reactor Coolant System, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycle > to date.
SURVEILLAN R,EQUIREMENTS 4.5.3 The ECCS subsystem shall'be demonstrated OPERABLE per the applicable 1
Surveillance Requirements of 4.5.2.
- With pressurizer pressure < 1700 psia.
EMERGENCY CORE COOLING SYSTEMS BASF.S The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained.
Surveillance requirements of throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. The acceptanco criteria specified in the Surveillance Requirements for HPSI single pump flow, HPSI differential pressure, and LPSI differential pressure does not account for instrument error.
3/4.5.4 REFUELING WATER TANK (RWT)
The OPERABILITY of the RWT as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS and CSS in the event of a LOCA.
The limits on RWT minimum volume and boron concentration ensure that 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWT and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These asr smptions are consistent with the LOCA analyses.
The contained water volume limit includes an au,, e ce. for water not c
usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWT also ensure a pH value of between 8.8 and 11.0 for the solution recircelated within containment aftar a LOCA. This pH band mininizes the evolution cf ladine and minimizes the effect of chloride and caustic stress corrx,d.on on mechanical systems and components.
ARKANSAS - UNIT 2 B 3/4 5-2 Amendment No. $2,148
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