ML20207D562
| ML20207D562 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/01/1999 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207D567 | List: |
| References | |
| NUDOCS 9903100008 | |
| Download: ML20207D562 (8) | |
Text
-
O ne:o g
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 300eH001
' CV,/
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No.186 1
License No. DPR 24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the I
licensee) dated September 28,1998, 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 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.
1 l
9903100008 990301 PDR ADOCK 05000266 P
... j
j 1
I i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR 24 is hereby amended to read as follows:
)
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 186, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
l 3.
This license amendment is effective immediately upon issuance. The Technical -
)
Specifications are to be implemented within 45 days from the date of issuance.
i I
FOR THE NUCLEAR REGULATORY COMMISSION l
l Beth A. Wetzel, Senior Project Manager Project Directorate 111-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 1, 1999
)
._---______-_L_
- i
j j#"'%k UNITED STATES p
- 5 -
]-
NUCLEAR REGULATORY COMMISSION -
j WASHINGTON, D.C. 30006 0001
%,*****/
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.191 License No. DPR 27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 28,1998, 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 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.
1 l
1 i
o _
2.
Accordir gly, the license is amended by changes to the Technical Specifications as indicated in the aitachment to this license amendment, and paragraph 3.B of Facility Operating Licenso No. DPR-27 is hereby amended to read as follows:
3.
Technical Soetfications The Technical Specifications contained in Appe. t. 's A and B, as revised l
}
through Amendment No. 191, are hereby inco;;.s.ated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
m 3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
h FOR THE NUCLEAR REGULATORY COMMISSION i
s&A d as Beth A. Wetzel, Senior Project Manager l
Project Directorate 111-1 Division of Licensing Project Manageniont
[
Office of Nuclear Reactor Regulation j
1
Attachment:
Changes to the Technical l
Specifications Date of issuance: March 1, 1999 l
l l
E 5
m F
l i
I
ATTACHMENT TO LICENSE AMENDMENT NO 186 TO FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO.191 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
REMOVE INSERT Table 15.4.1-1 (Pages 3-5)
Table 15.4.1-1 (Pages 3-5)
)
4 4
i i
I t
i
=
- y..
- e
-C TALLE 15.4.1-1 (cxmtinued).
PLANT CONDITIONS 4
'E QIANNEL DEf.SCRIPTION CHECK CALIBRATE TEST WHEN REOUIRED
' 20.
Auxiliary Feedwater Flowra e (13)
R a
ALL 21.
Boric Acid Contrcl System R
ALL 22.
Boric Acid TankImel D
R ALL 23.
Charging Flow R
ALL 24.
Conrie==ee Storage Tank Level S(l)
R ALL
[25.
Contmansent High Range Raimbon M(1)
R(14)
ALL 26.
Contenment Hydrogen Monitor D
ALL
-Gas Calibranon Q(15)
'ALL
-Electronse Calibrahon R
ALL 27.
Contmament Pressere S
R Q(1,3,9)
ALL 28.
Contmanient WaterInct M
R ALL
. 29.
E.-.
-y Plan Radinuon
'l Surveylastruments Q
A Q
ALL
~ 30.
Environniental Monitors M
ALL
'3L In-Core Thermocouples M
R(14)
AIL 32.
. tow Temperature Cmy.-..
Prosecuan System S(12)
R (10)
ALL.
33 PORV Block Valve -
Posioon ladicator Q
R ALL 34.
PORVOperability R
Q(11) -
ALL
- 35.
- PORV Possuoa Indicator S(21)
.R R
AtL l
Unit 1 - Amendment No. 186 Page 3 of 6 -
Unit 2 - Amendment No. 191
i
+
TABLE 15.4.1-1 (continued)
PLANT CONDITIONS
- HQ CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REOUIRED
~. 36.
Radiation Monitoring System
- RE-218 WDS Liquid Monitor (7)
R(14)
Q' ALL
- RE-223 Waste Distillate Overboard Monitor (7)
R(14)
Q ALL
- RE-231 A Steam Line Release Monitor M(1)
R(14)
ALL
- RE-232 B Steam Line Release Monitor M(1)
R(14)
ALL
-RE-101 Control Roorr; Monitor S
R(14)
Q ALL
- RE-235 Control Room Noble Gas Monitor S
R(14)
Q ALL
-RE-215 AirEjectorMonitor D(1)
R(14)
ALL
-37.
Reactor Vessel Fluid Level System M
R
.ALL 38.
Refueling Water Storage Tank Level R
ALL 39.
Residual Heat Removal Pump Flow R
ALL 40.
_ Safety Valve Position Indicator, M
R ALL-41.
Subcooling Margin Monitor M
R ALL 42.
Deleted l43.
Volume ControlTank Level A
ALL 44.
Reactor Protection System and M(1,23)
ALL-Emergency Safety Feature Actuation System Logic 4
45.
Reactor Trip System Interlocks
-Intermediate Range Neutron Flux, P-6 R(24)
R ALL
-Power Range Neutron Flux, P-8 R(24)
R ALL
-Power Range Neutron Flux, P-9 R(24)
- R ALL
-Power Range Neutron Flux, P-10 R(24)
.R ALL
-1st Stage Turbine Impulse Pressure R(24)
R ALL'
~
l-Unit 1 - Amendment No.186 Page 4 of6 Unit 2 - Amendment No.191
-x..-.z--.- -
- ---2-.~
a-m,
- ~
NOTATION USED IN TABLE 15.4.1-1 l A-Annually (12 months) c S-Each shiA D-Daily
- W-Weekly
% Quarterly M-Monthly P-Prior to reactor enocality if not performed during the previous weest.
- l R-Each refueling interval (18 rnanths)
PWR-Power and Imr Power Operation, as defined in Specifications 15.1.h. and 15.1.m.
HOT S/D-Hot Shutdown, as defined in E,- 7-:r-:-315.1.g.l.
COLD S/D-Cold Shutdown, as defined in Specifx:ation 15.I.g.2.
REF S/D-Refueling Shutdown, as defined in SA.oon 15.1.g.3.
All - All conditions ofoperation, as defined in S --- ~--ek-w 15.1.g, h, and m i
NOTES USED IN TABLE 15.4.1-1 (1)
Not required during penods of refueling shutdown, but must be perforened prior to reactor criticality ifit has not been W v M dunng the previous surveillance.
i Period.
(2)
~ Tests of th low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to reactor enticality if not done in the previous surveillancx; interval.
(3)
Perform test of the isolacon valve signal.
(4)-
Perform by nicans of the moveable incere detector sym.
(5)
Recalibrate if the absolute difference is 23 percent.
- (6)
Verificahon of proper breaker alignment and that the 120 Vac instrument buses are energized.
(7)
Source check is required prior to imuanon of a release. Source check is an assessment of channel response by exposing the detector to a source ofincre Channel check is required shiAly during a release. If monitor or isolation function is discovered inoperable, discontinue release inunedsately.
. Verify that the associated rod insertson limit is not being violated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whcnever the red insertion limit alarm for a con (8) l (9)'
Test of Nanow Range Pressure,3.0 psig, -3.0 psig excluded.
I l
Unit 1 - Amendment No.186 Page 5 of 6 L
Unit 2 - Amendment No.191
-.