ML20244C983
| ML20244C983 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/09/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244C984 | List: |
| References | |
| NUDOCS 8906160013 | |
| Download: ML20244C983 (9) | |
Text
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. UNITED STATES '
[
g NUCLEAR REGULATORY COMMISSION j
E ij WASHINGTON, D. C. 20555 -
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i WISCONSIN ELECTRIC POWER COMPANY
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DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 j
1 AMENDMENT-T0. FACILITY OPERATING LICENSE l
j Amendment No.122
]
License No. DPR-24 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 9, 1988 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 i
CFR Chapter I; B.
The facility will operate in conformity with the applicatica, the provisions of the Act, and the rules and regulations of the j
Comission; i
l C.
Thereisreasonableassurance(1)thattheactivitiesauthorized i
by this amendment can be conducted without endangering -the health and safety cf the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;
.i l
l D.
The issuance of this amendment will not be inimical to the common defense and secbrity or to the health and safety of the public;
]
and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 f
of the Comission's regulat!ons and all applicable requirements have been satisfied.
8906160013 890609 PDR ADOCK 05000266 P
PDC 1
t
-2 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 Specifications
~
The Technical Specifications contained in' Appendices A and B, as revised through Amendn.ent. No.122, are hereby incorporated in the license..The licensee shall operate the facility in l
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 John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 9, 1989 E_-__________.--___.________z____-----___
k
, NUCLEAR REGULATORY COMMISSION.
UNITED STATES
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j WASHINGTON, D C.20E55 l
WISCONSIN ELECTRIC POWER COMPANY' 1
DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT N0_. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. ~125~
License No. DPR-27 1.
The Nuclear Regulatory Comission -(the Comission),has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 9,'1988 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 j
Comission; 1
C.
'There is reasonable assurance (1) that the activities authorized j
by this amendment can be conducted without endangering the health
']
and safety of the public, and (ii) that such~ activities will be--
conducted in compli6nce with the Comission'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 Comission's regulations and all applicable requirements have been sattsfied.
i
~
~2-2.
Accordingly, the license is 6 mended by changes to the Technical
'l Specifications as indicated in the attachment to this license -
j amendment, and paragraph 3.B of facility Operating License No.
]
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications
)
The Technical Specifications contqiaed in Apper. dices A and B, as revised through Amendment No. 2O, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical-Specifications.
3.
This license amendment is effective insnediately upon issuance. The i
Technical Specifications are to be implemented within 20 days from the date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION l
Nm t John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y ano Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 9, 1989 1
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I j
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1
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ATTACHMENT TO LICENSE AftENDMENT NOS. 122 AND 125 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below ard inserting the enclosed pages.. The revised pages are. identified by amendment number and contain marginal lines indicating. the a.rea of change.
REMOVE.
INSERT 15.3.8-2 15.3.8-2 Table 15.7.3-2 Table 15.7.3-2 Table 15.7.4-2 Table'15.7.4-2 Table 15.7.6-2 Table 15.7.6-2
q 6.
Direct communication between the control 7oom and th'e operating floor-of the containment shall be available whenever changes in core geometry are taking place.
7.
The Containment Purge and Vent System shal1~be operable. The Contain-ment Purge and Vent SystemLshall be demonstrated operable within 4 days prior to the start of and at least once per 7 days during refueling operations by verifying that Containment Purge and. Vent isolation occurs on manual initiation and on high radiation test signal.
8.
With the Containment Purge and Vent System inoperable, close the Purge and Vent containment penetrations.
9.
If any of the specified limiting conditions lin se tions 1, 2, 3, 4,; 5, and 5 are not met, refueling of.the reactor shall cease. Work shall be, initiated to correct the violated conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.
Basis The equipment and general procedures to be' utilized during ' refueling are discussed in the Final Safety Analysis Report.
Detailed-instructions, the above specified precautions, and the design of the fuel handliag equipment incorporating built-in interlocks and safety features, provide assurance that -
no incident could occur during the refueling operations that would result in a hazard to public health and safety.II) l Whenever changes are not being made in core geometry one s'ux monitor is' sufficient. This permits maintenance of the instrumentation.~ Continuous i
monitoring of radiation levels (A2.above) and neutron flux provides immediate indication of an unsafe condition. The residual heat pump is used to maintain a uniform boron concentration.
I The shutdown margin indicated in Part A5 will keep the core subcritical, i
even if all control rods were withdrawn from the core.
During refueling, i
the reactor refueling cavity is fill N with approximately 275,000 gallons i
15.3.8-2
~ Unit 1 - Amendment No. 35,B6,9J.96,122 l
Unit 2 - Amendment No. A2,90,95,J00, 125 i
)
TABLE 15.7.3-2 7 ^
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum
. Channels Instrument Operable Action 1.
Gas Decay Tank System a.
RE-214, Noble Gas (Auxiliary 1
Note 1 Building Vent Stack), or RE-315 Noble Gas (Auxiliary Building Vent
]
SPING) b.
Gas Decay Tank Flow-1-
Note 4 i
Measuring Meter
- 2..
Auxiliary Building Ventilation System a.
RE-214, Noble Gas (Auxiliary 1
Note 6 Building Vent Stack) or RE-315, Noble Gas (Auxiliary Building Vent SPING) b.
Isokinetic Iodine and Particulate -
1 Note 5 Continuous Air Sampling System 3.
Condenser Air Ejector System a.
RE-225, Noble Gas (Combined Air 1
Note 6 1
Ejector Discharge Monitor); or RE-215, Noble gas (Air Ejector Monitors - 1 per unit); or RE-214, Noble Gas (Auxiliary Building Vent Stack); or RE-315, Noble Gas j
(Auxiliary Building Vent SPING) b.
Flow Rate Monitor - Air Ejectors 1
Note 9 i
4.
Containment Purge and Vent System l
a.
RE-212, Noble Gas Monitors 1
Note 6
~
(1 per unit); or RE-305, Noble Gas (Purge Exhaust SPING - 1 per unit) i b.
30 cfm Forced Vent Path Flow Indicators 1
Note 9 t
4 15 7.3-4 Unit 1 - Amendment No. 77, 122 Unit 2 - Amendment No'.-J0J,125.
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