ML20093M023
| ML20093M023 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/18/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093M026 | List: |
| References | |
| NPF-06-A-170 NUDOCS 9510260164 | |
| Download: ML20093M023 (6) | |
Text
..
,eP*%,1 UNITED STATES p
g j
NUCLEAR REGULATORY COMMISSION
%o*****+l$
o WASHINGTON. D.C. enana mani ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368
^
ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) t.n found that:-
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated March 17, 1935, complies with the standards ano 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;
f 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 tt'e 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
cosumon defense and security or to the health and safety of the public; i
l 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 j
j satisfied.
i l
f 4
4 l
a 9510260164 951019 PDR ADOCK 05000368 P
i.
i,
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.170, 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 to be implerranted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
George Kalman%or Project Manager
, Seni Project Directorate IV-1 4
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: October 18, 1995 i
i i.
I J
4 4
t ATTACHMENT TO LICENSE AMENDMENT NO. 170 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following page of the Appendix "A" Technical Specifications with the attached page.. The revised page is identified by Amendment number and contains 1
vertical lines indicating the area of change. The corresponding overleaf page
- is also provided to maintain document completeness.
REMOVEPEifS INSERT PAGES a
j 3/4 5-5 3/4 5-5 4
4 i
1 1
ft 4
. - =*
DERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS -(Continued) f.
By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant te 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.
At least once per 18 months by verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
LPSI System Valve Number a.
2CV-5037-1 b.
2CV-5017-1 c.
2CV-5077-2 d.
2CV-5057-2 h.
By performing a flow balance test, during shutdown, following i
completion of modifications to the ECCS subsystem that alter the subsystem flow characteristics and verifying the following flow rates:
HPSI System - Single Pump LPSI System - Single Pump 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
)
j l
l 4
i i
i l
1 l
. UNIT 2 3/4 5-5 Amendment No. 44,444,4M,17C i
i.
t r.
i EMERGENCY CORE COOLING $YSTEMS f
4 ECC$ $U85YSTEMS - T,,, < 300*F.
i j
LIMITING' CONDITION POR OPERATION-l L
3.5.3 As a minim e. one ECCS subsystem comprised of the following shall p
be OPERA 8tE:
j a.
'One OPERA 8LE high-pressure safety injection pop. And e
b.
An OPERA 8LE flow path capable of taking suction'from the refueling water tank on a Safety Injection Actuation Signal t
and automatically transferring suction to the containment sep 4
~on a Recirculation Actuation Signal.
i APPLICABILITY: MODES 3* and 4.'
f i
ACTION:-
\\
a.
With no ECCS subsystem OPERA 8LE, restore at least one ECCS
' subsystem to 0PERABLE 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 SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.-
t-t b.
.In the event the ECCS is actuated and injects water into the j.
Reactor Coolant System, a Special Report shall be~ prepared and i
submitted to the Comission pursuant ta Specification 6.9.2 within 90 days describing the ciremstances of the actuation i
and the total accoulated actuation cycles to date.
~
SURVEILLANCE REQUIREMENTS i:
4.5.3 The ECCS subsystem sha?1'be demonstrated CPERA8LE per the applicable
~
Surveillance Requirements of 4.5.2.
t
.Nith pressurTrer pressure 4.1700 psia.
b 4
ARKANSAS.- UNIT 2
.3/4 5-6
.