ML20069Q676
| ML20069Q676 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/09/1991 |
| From: | Gwynn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069Q678 | List: |
| References | |
| NUDOCS 9101170015 | |
| Download: ML20069Q676 (5) | |
Text
'
[ goo os e h UNITED $TATES
['
',g NUCLE AR REGULATORY COMMISSION i*,.
5 W AsmNOToN, D. C,70t.%
\\..ss.../
ENTERGY OPERATIONS. INC, DOCKET NO. 50-382 l
MTERFORD STEAM ELECTRIC STATION, UNIT 3 AHpDMENTTOFACILITYOPERATINGLICENSE Amendment No. 65 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc.
(the licensee) dated July 25, 1990, as supplemented by letter dated November-7, 1990, 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, I
the provisions of the Act, and the rules and regulations of the Commission; C..
There is reasonable assurance (i) that the activities authorized 1
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 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 j
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
a 1
i 4
4 E
9101170015 910109 PDR ADOCK 05000302 P
PDR u-
. _..... _ _ _ _ _. _ _. _ ~ _. _... _..,. _ _ _. _ _. _. _., _.
,1
{
o' I
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 Ko, NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plea The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license, j
- The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
4 4?rd Thomas = P. Gwynn, Acting Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes.to the Technical
- Specifications Date of Issuance:
January 9,1991 1.
I t'
k
.-.I-'s.w, mi---emy w w -e-e
,y,.,,-4,
-v.m.,,
---=en
,.re--e,---uapz..
- -,m,..,.,w--.-,,w.,,..w.rm-r9-ew.w.-...,
,-myrsw,,-,--,,,....-y-.p-9-.9.w.-m..,-w.e.,
y ww g,y p g y + ~.-, y -+cirm a-+ yye wmep. y w y -
l ATTACHMENT TO LICENSE AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO, 50-382 Replace the following pages of the Appendix A Ter.hnical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 5-3 3/4 5-3*
3/4 5-4 3/4 5-4 s
- overleaf page; no change.
.,-_--_-----.-.-a--------__----.----a---_.--
l
)
i EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - MODES 1, 2, AND 3
[
LIMITING CONDITION FOR OPERATION L
3.5.2 Two independent emergency core cooling system (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:
l a.
One OPERABLE high pressure safety injection pump, l
b.
One OPERABLE low pressure safety injection pump, and c.
An independent OPERABLE flow path capable of taking suction from the refueling water storage pool on a safety injection actuation signal j'
and automatically transferring suction to the safety injection system f-
. sump on a recirculation actuation signal.
i APPLICABILITY:
MODES 1, 2, and 3*#.
ACTION:
(
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 at least HOT STANDBY within the next-6 hours and in HOT SHUTDOWN within the following i
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
In.the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 190 days des-cribing the circumstances of the actuation and the total accumulated actuation cycles to date..The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.-70.
"With pressurizer pressure greater than or equal to 1750 psia,
- With RCS average. temperature greater than or equal to 500'F.
l-WATERFORD - UNIT:3 3/4 5 --we-m w,*,,
ww.,-r-rv.-nw'_,w.sw,.v--
,eMmm r,,-,,x,,-yxw,w.--w,r
$- r' ee e :-r + v 4 v e t
-~v
-' e -ytw,-+w-e e-v--
-+-+-F+%'w-=-+i45
- 'e--*
w-r*f um,-,r-*
w r-
-- = c m-v-ens y
EMERGENCY CORE C00;ING SYSTEMS SU,RVEILLANCE REQUIREMENTS F
4.5.2 Each ECCS subsystem 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 verifying that the following valves are in the indicated positions with the valves key-locked shut:
Valve Number Valve Function Valve Position a.
2SI-V1556 a.
Hot leg Injection a.
SHUT (SI-506A) b.
2SI-V1557 b.
Hot Leg Injection b.
SHUT (SI-502A) c.
2SI-V1558 c.
HotLegInjection c.
SHUT (SI 502B) d.
2SI-V1559 d.
Hot Leg Injection d.
SHUT (SI-506B) 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, sealed, or otherwise secured in position..is in its correct position.
c._
By a visual inspection which verifies that no loose debris (rags, i
trash, clothing, etc.) is present in the containment which could be transported to the safety injection system sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
'I.
For all accessible areas of the containment prior to establishing CONTAINMENT-INTEGRITY, and 2..
Of.the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established, d.
At.least once per 18 months by:
- 1..
Verifying the action of the _open permissive interlock (OPI) and isolation-valve position alarms of the shutdown cooling system when the reactor coolant system pressure (actual or simulated) i is between 392 psia and 422 psia, j
)
l
- WATERFORD UNIT 3 3/4 5-4 AMENDMENT NO. 65 E -
~.s _._._ _ _ _ _ -,.., _., _.. _
m..
_