ML20236Y380
| ML20236Y380 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/07/1998 |
| From: | William Reckley Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236Y382 | List: |
| References | |
| NPF-06-A-192 NUDOCS 9808120157 | |
| Download: ML20236Y380 (6) | |
Text
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WASHINGTON, D.C. 20555 4001 EtEERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.192 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 19,1995, as supplemented by letters dated February 27 and September 30, 1996, complies with the standards and requirements, of the Atornic 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 rot be inimical to the common defense and sc:urity or to the health and safety of the public; and E.
The issuant af this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 9808120157 980807 PDR ADOCK 05000368 P
4
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendmerit, and Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Igchnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 192, 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 THE NUCLEAR REGULATORY COMMISSION g
c.
William Reckley, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 7, 1998
4
' TTACHMENT TO LICENSE AMENDMENT NO.192 A
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 verticallines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES '
INSERT PAGES 3/4 5-1 3/4 5-1 B 3/4 5-2 B 3/4 5-2 i
1
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1.Each reactor coolant system safety injection tank shall be OPERABLE withs a.
The isolation valve open, b.
A contained borated water volume of between 1413 and 1539 cubic feet (equivalent to an indicated level between 80.14 and 97.9%,
respectively),
c.
Between 2200 and 3000 ppm of boron, and d.
A nitrogen cover-pressure of between 600 and 624 psig.
APPLICABILITY: MODES 1, 2 and 3.*
ACTION:
a.
With one safety injection tank inoperable, due to boron concentration not within limits, restore the boren concentration to within limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in 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 reduce pressurizer pressure to <700 pain within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With one safety injection tank inoperable due to inability to verify level or pressure, restore the SIT to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in 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 reduce pressurizer pressure to ( 700 psia within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With one safety injection tank inoperable for reasons other than l
ACT10N a or b, restore the SIT to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in 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 reduce pressurizer pressure to <700 psia within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
4 1.
Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.
Verifying that each safety injection tank isolation valve (2CV-5003, 2CV-5023, 2CV-5043 and 2CV-5063) is open.
- With pressurizer p:: essure 2 700 psia.
l ARKANSAS - UNIT 2 3/4 5-1 A andment No. 44, MG,192 L _ _-
=
FMrWGENCY CORF COOLING SYSTEMR q
t RITVEff f ANCE REOUTPFMENTE (Continued) b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of 2 5% of indicated tank level that is not the result of addition from the RWT, by verifying the baron concentration of.the safety injection tank solution.
c.
At least once per 31 days when the RCS pressure is above 2000 pais, by verifying that power to the isolation valve operator is removed by maintaining the motor circuit breaker open under administrative control.
d.
At least once per 18 months by verifying that each safety
~~
injection tank isolation valve opens autoestically under each of the following conditions:
1.
When the RCS pressure escoeds 700 psia, and l'
2.
Upon receipt of a safety injection test signal.
f) 9 ARKANSAS - UNIT 2 3/4 5-2 Amendment No.152 NOV 8 1993
EMERGENCY CORE COOLING SYSTEMS EASES NUREG-1366, " Improvements to Technicti specifications surveillance Requirements," Section 7.4 discusses surveillance requirements for the instrumentation channels used in the measurement of water level and pressure in SITS.
It is the recommendation of the NUREG that when one SIT is inoperable due only to the inability to verify water level and pressure, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be allowed to restore SIT t; an OPERABLE status.
If one SIT is inoperable, for a reason other than boren concentration or the inability to verify level or pressure, the SIT must be returned to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In this condition, the total contents of the three remaining SITS cannot be assumed to reach the core during a LOCA, contrary to the assumptions of 10 CrR 50, Appendix K.
CEOG " Joint Applications Report for safety Injection Tank ACT/STI Extension,"
CE NPSD-994, provides a series of deterministic and probabilistic findings that support 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as being either " risk beneficial" or
- risk neutral" in comparison to shorter periods for restoring the SIT to OPERABLE status.- The report discusses best-estimate analysis that confirmed that, during large-break LOCA scenarios, core melt can be prevented by either operation of one LPSI pump or the operation of one HPSI pump and a single SIT.
l 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging fram the double-ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
The surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the accident anklyses 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 l
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 acceptance criteria specified in the surveillance Requirements for HPSI single pump flow, HPSI differential pressure, and LPSI differential pressure door not account for instrument error.
3/4.5.4 REFUELING WATER TANK (RNT)
The OPERABILITY of the RNT as part of the ECC8 ensures that a sufficient j
supply of borated water is available for injection by the ECC# ond Cs3 in the event of a LOCA. The limits on RNT minimum volume and borosa concentration ensure that 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain suberitical in the cold condition following mixing of the RNT and the RCS water vclumas with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
1 ARKANSAS - t/ NIT 2 3 3/4 5-2 Amendment No. 44,444,3%a.192
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