ML20056D732
| ML20056D732 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-24-A-140, DPR-27-A-144) |
| Issue date: | 07/28/1993 |
| From: | Gody A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D733 | List: |
| References | |
| NUDOCS 9308170391 | |
| Download: ML20056D732 (10) | |
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- t UNITED STATES E
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2DEIIM1001
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WISCONSIN ELECTRIC POWER' COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 140 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Wisconsin Electric Power Company (the licensee)- dated January 17, January 29, 1992, and April 16, 1992 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 applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities-authorized b/
this amendment can be conducted without endangering the health and safety of the public, and -(ii) that such activities wil' be-conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be irimical to th<! common-defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance witti 10 CTR Part 51.
of the Commission's regulations and all applicable requirements have been satisfied.
9308170391 930728 DR ADOCK 05000266
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Accordingly, the license is amended by changes to the Technical i
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:
i B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Anthony T. Gody, Jr...Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 28, 1993 6
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- t UNITED STATES i
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j NUCLEAR REGULATORY COMMISSION i
WA3HINGTON. D.C. 20EI50001 I
i WISCONSIN ELECTRIC POWER COMPANY i
DOCKET NO. 50-301
-l POINT BEACH NUCLEAR PLANT. UNIT NO. 2 I
AMENDMENT TO FACILITY OPERATING LICENSE 3
Amendment No.144 License No. DPR-27
)
1.
The Nuclear Regulatory Commission (the Commission)- has found that:.
A.
The applications for amendment by Wisconsin Electric Power Company' (the licens'ee) dated Jar-iary 17, January 29, 1992, and April.16, _
1992 complies with the standards and requirements of the Atomic i
Energy Act of 1954, as amended (the Act), and the Commission's rules l
and regulations set forth in 10 CFR Chapter I;
.I B.
The facility will operate in conformity with the applications, the -
provisions of the Act, and the rules and regulations _ of the Commission; C.
There is reasonable assurance (i) that the -activities' authorized by ;
i this amendment can be conducted without'eidangering the health'and safety of the - public, and (ii) _that - s'ach _ activities wi_11 be-conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment 'will not be. 'nimical to thef common
. defense and security or to the health and saftdy of the public;;and E.
The. issuance of this amendment is in accordance with 10 CFRLPart. 51-of the Commission's. regulations and all applicable requirements have-been satisfied, t
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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-27 is hereby amended to read as follows:
l B.
Technical Soecifications The Technical Specifications contained in Appendices A and_ B, as revised through Amendment No. 144, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Anthony T. Gody, Jr., Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 28,1993 1
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ATTACHMENT TO LICENSE AMENDMENT NOS.lan AND 144 TO FACILITY OPERATING LICENSE N05. DPR-24 AND 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 marginal lines indicating the area of change.
REMOVE INSERT Table 15.4.1-1 Table 15.4.1-1 (Pages I through 4)
(Pages 1 through 5)
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MINIMUM FREQUENCIES FOR CillCKS. CAllBRA110NS AND TEST Of INSTRUMENT CilANNELS.
' No.
Channel Description Check
[alibrate Test Remarks F, F l
a 1.
Nuclear Power Range Sjl)'*
Dj'l ) **
Q(2)*'
(1) lleat Balance
- R&
M (3),,(4)
Q 3) (4)
(2)
Sianal to AT; bistable action (rod stops, trips) l (3)
Upper and lower chambers for axial off-EE set (4)
Compare incore to excore axial flux
@O difference.
Recalibrate if the absolute difference is greater than or equal to 3 mw
"{
percent.
'w
- 2.
Nuclear Intermediate Range S ( 1 )..
N.A.
P(2)
(1)
Once/ shift when in service w
OM (2)
Log level; bistable action (rod stop, l
-g'g trips) w~
, g 3.
Nuclear Source Range S(l)
N.A.
P(2)
(1)
Once/ shift when in service go (2)
Bistable action (alarm, trips) 4.
Reactor Coolant Temperature 5
R Q ( 1 )** (2 )** (1)
Overtemperature - AT (2)
Overpower - AT 5.
Reactor Coolant Flow S**
R Q**
6.
Pressurizer Water Level S**
R Q
7.
Pressurizer Pressure S**
R Q"
8.
4 XV Voltage N.A.
R M"
Reactor protection circuits only 9.
Analog Rod Position S ( l ) *****
R N.A.
(1)
With step counters By means of the moveable incore detector system.
Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
Tests of the low power trip bistable setpoint which cannot be done during power operations shall be conducted prior to startup if not done in the previous surveillance interval.
- Not required during periods of cold and refueling shutdowns, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
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}y" TABLE 13.4.1-l'(2 of 5) q.
1 1'
-No.
Channel-Description Check Calibrate
}f
~ Test Remarks
- s s.10. - -Rod Position Bank Counters:
'S(l)*****
N.A.
N.A.
(1)
With analog rod position
- o. a
_!!11.
Steam Generator level-S**
R Q(1)**
@ @ 12.
' Steam Generator Low level S*****
R Q**
Coincident with Steam Flow /
EO Feed Flow Mismatch ma-
. ] 13.-
Charging Flow N.A.
R N.A.
..~
L b 14.
' Residual Heat Removal Pump-N.A.
R N.A.
- "J.
Flow 40'
~ M
- 15.
Boric. Acid Tank Level' D
R N.A.
Q ~' 16.
g.$
Refueling Water Storage N.A.
R N.A.
Tank level 17.
Volume Control Tank level N.A.
R N.A.
18.
Reactor Containment Pressure S'
R Q(1)**
(1)-
Isolation valve signal 19.-
Radiation Monito' ring System D
R M
(1)
Radioactive Effluent Monitoring Instrumentation Surveillance Requirements are specified in 15.7.4.
20.
Boric Acid Control N.' A.
R N.A.
I 21.
Containment. Water Level M
R N.A.
22.-
Turbine Overspeed Trip *-
'N A '
R-M(1)**
(1)'
Block trip 23.
Accumulator. Level,and S
R N.A.
Pressure o
Overspeed: Trip.. Mechanism, and independent Turbine Speed Detection and Valve Trip System oo-Not-required dur.ing periods of refueling shutdown, but must be performed prior to starting up~ if it has not been performed during the, previous surveillance period.
'ooo** Not required during' periods'of cold and refueling shutdowns, but mustjbe performed prior to starting up if it has pt not been performed.during the previous surveillance period.
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a TABLE 15 4.1-1L(3 of 5)-
y.
-NA Channel Descrio' tion Check-Calibrate Test Remarks 24.:
Containment Pressure
- S R
Q**
Narrow range containment pressure
(-3.0, +3 psig excluded) 25.
Steam Generator Pressure S***
R Q"
26.
Emergency Plan Radiation Q
R Q
Survey Instruments 27.
Environmental Monitors M
N.A.
N.A.
28.
Overpressure Mitigating S
R
.29.
PORV Position Indicator:
S R
R 30.
PORV Block Valve Position Q-R N.A.
Indicator-31.
Safety Valve Position M
R N.A.
Indicator.
t 32.
PORY Operabil.ity N.A.
R Q
Performance of a channel functional test but excluding valve operation 33.
Subcooling Margin Monitor-M R.
N.A.
34.
Undervoltage on-4 KV Bus N. A.'
- R M**
For Auxiliary Feedwater Pump Initiation 35.
Auxiliary Fe'edwater Flow-See R
N.A.
Flow Rate indication will be checked at Rate
- Remarks-each unit startup and-shutdown ~
-36.
Degraded 4.16 KV Voltage
- S'-
R M**
37.
a.
loss of Voltage (4.16 KV). S R
M[..
t b.
. loss'of Voltage (480 V)"
S-R
-H 38.
4160 V Frequency-N.A.
R
. N.A.
Unit.1 - Amendment No.- 38,47,55,59,JJ3,140
-Unit 2. Amendment No. 56,55,66,64,JJ6,144 m.-..
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TABLE 15.4.1-1 (Page 4 of 5)
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Channel Description Check Calibrate Test Remarks 39.
Containment High Range S**
R M'*
Calibration to be verification of response to a !
Radiation source.
40.
Containment Hydrogen Monitor D R/Q N.A.
Gas Calibration - Q.
Electronic Calibration - R Sample gas for calibration at 2% and 6%
41.
Reactor Vessel Fluid level M
R N.A.
System 42.
In-Core Thermocouple M
R N.A.
Calibration to be verification of response to a (
source.
- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
- During cold or refueling shutdown, a check of one pressure channel per steam generator is required when the steam generator could be pressurized.
Performance of a channel functional test on the PORV actuation channel, but excluding valve a.
operation,~within 31 days prior to entering a condition in which the PORV is required operable and at least once per 31 days.thereafter when the PORV is required operable.
b.
Testing valve operation in accordance with the inservice test requirements of the ASME Boiler and Pressure Vessel Code,Section XI.
Unit 1 - Amendment No./38,47,55,76,92,JJ3,140 Unit 2 - Amendment No. 50,55,50,E0,96,116,144 i
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TABLE 15.4.1-1 (Page 5 of 5)
No.-
Channel Description-Check Calibrate Test Remarks 43.
N.A.
N.A.
M**
Each train tested at least every 62 days on a and Emergency Safety Feature staggered basis.
Actuation System logic Reactor Trip on' loss of reactor coolant flow in both loops shall be performed each refueling interval.
44..
Reactor Trip System' interlocks a.
- Intermediate Range N.A.
R R
Neutron detectors excluded from Neutron Flux, P-6 calibration b.
Power Range N.A.
R R
Neutron detectors excluded from Neutron Flux, P-8 calibration c.
Power Range N.A.
R R
Neutron detectors excluded from Neutron Flux, P-9 calibration d.
Power Range N.A.
R R
Neutron detectors excluded from Neutron Flux, P-10 calibration e.
1st Stage Turbine S**
R R
. Impulse Pressure S - Each Shift M - Monthly D - Daily P - Prior to each startup if not done previous week.
W - Weekly R - Each Refueling interval (But not to exceed 18 months).
B/W - Biweekly N.A. - Not applicable.
_Q - Quarterly
- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance interval.
Unit 1 - Amendment No.140 Unit 2 - Amendment No.144
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