ML20092J090
| ML20092J090 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/15/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092J092 | List: |
| References | |
| NPF-06-A-162 NUDOCS 9509210321 | |
| Download: ML20092J090 (5) | |
Text
,
a mer ug\\ :
UNITED STATES y
s j
NUCLEAR REGULATORY COMMISSION
' ~
WASHINGTON, D.C. 20565-0001 i
..... yo l
l
{}[IERGY OPERATIONS. INC.
DOCKET NO. 50-368 i
i ARKANSAS NUCLEAR ONE. UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. NPF-6 1
\\
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the
-licensee) dated March 17, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission;
\\
C.
There is reasonable assurance:
(1) 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 Comission'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 CF?. Part 51 of 1
the Comission's regulations and all applicable requirements have been 1
satisfied.
i 1
)
l l
9509210321 950915" PDR ADOCK 05000368 p
--..--...-.-- -L
.--. ---J.
-,~
..~
. _ ~
4
)
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 Soecifications The Technical Specifications contained in Appendix A, as revised
-through Amendment No. 162, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the
' Technical Specifications.
I 3.
The license amendment is effective as of the date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION SVa George Kaled enior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation 4-
Attachment:
Changes to the Technical Specifications 3
Date of Issuance: September 15, 1995 i
i 2
1 1
d '
4 m
r
ATTACHMENT TO LICENSE AMENDMENT NO.
162 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 a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 5-4 3/4 5-4 1
- 1..
EMERGENCY CORE COOLING SYSTEMS i
ECCS. SUBSYSTEMS - T,yg > 300'F 1
LIMITING' CONDITION FOR OPERATION l
\\
)
3.5.2 Two independent ECCS subsystems shall be OPERABLE with each sub-system comprised of:
a.
10ne OPERABLE high-pressure safety injection pump,
- b.
One OPEllABLE low-pressure safety injection pump, and l
c.
An independent OPERABLE flow path capable of taking suction.
F from the refueling water tank on a Safety Injection Actuation.
1.
Signal and automatically transferring suction to the containment
[
sump on a Recirculation Actuation Signal.
l APPLICABILITY: MODES 1, 2 and 3*..
dCTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 l*
SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
k b.
In the everft the ECCS is actuated and injects water into the l'
Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 l
within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
r SURVEILLANCE REQUIREMENTS V
l 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
O 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 verifying that the following i,
valves are in the indicated positions with power to the
{
. valve operators removed:
Valve Number-Valve Function Valve Position
'2CV-5101.
HPSI Hot. Leg Injection Closed l
Isolation U
.2CV-5102 HPSI Hot Leg Injection
. Closed
~
Isolation 2BS26' RWT Return Line Open n
- With pressurizer pressure > -1700 psia..
v
~
~
ARKANSAS - UNIT-2,
'3/4 5-3 i
1h. s
.... :. % ;.,.4.n 7....
_= -
i EMERGENCY CORE COOLING SYSTEMS
. SURVEILLANCE REQUIREMENTS (Continued)
.i
~
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, i
sealed, or otherwise secured in position, is in its correct 4-position.
c.
By a visual inspection which vecifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could t
be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and i
2.
At least once daily of the areas affected with'n containment if i
containment has been entered that day, and during the final entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
Verifying automatic isolation and interlock action of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System pressure is above 300 psia.
i e
4 i
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by 4
j debris and that the sump components (trash racks, screens, i
etc.) show no evidence of structural distress or corrosion.
t e.
At least once per 18 months, during shutdown, by:
i 1.
Verifying that each automatic valve in the flow path actustes to its correct position on SIAS and RAS test signals.
i i
2.
Verifying that each of the following pumps start l
automatically upon receipt of a safety Injection Actuation Test signal:
f a.
High-Pressure safety Injection pump.
b.
Low-Pressure Safety Injection pump.
]
l i
f.
i-b ARKANSAS - UNIT 2-3/4 5-4 Amendment No. 49, 162 4
.