ML20054E550
| ML20054E550 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/28/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054E551 | List: |
| References | |
| TAC-47838, TAC-47839, NUDOCS 8206110340 | |
| Download: ML20054E550 (8) | |
Text
E
/
Io UNITED STATES g
EE NUCLEAR REGULATORY COMMISSION p,
g.
.cj WASHINGTON. D. C. 20555 t
DESIG D ORIGINff Certified B 1
V
~
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amerdment No. 60 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 licensee) dated April 30,1982, e.1 plies 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 confonnity 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 I
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 r
51 of the Commission's regulations and all applicable requirements have been satisfied.
r i
I 8206110340 820528 PDR ADOCK 05000266 P
9
, 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 Amendment No. 60, are hereby incorporated in the licerise. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION "g%Y
'a4
?
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical i
Specifications Date of Issuance: May 28, 1982 I
L
{
i E
l l
l l
e
h.:
. ;.7 ).;, ( ' g. w
'o USHTED STATES
-(
~
y g
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 s/
^j gg Certified f
a WISCONSIN ELECTRIC POWER C0f1PANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The anplication for amendment by Wisconsin Electric Power Company (the licensee) dated April 30, 1982, 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 confomity 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.
t I
l l
)
fl 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMf11SSION c;
?}i~ 4.
^^ :'
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
t Changes to the Technical Specifications Date of Issuance:
May 28, 1982 t
t
c-
.w p
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 60 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 s
Revise Appendix A as follows:
Remove Pages Insert Pages 15.3.3-3 15.3.3-3 15.3.3-3a 15.4.5-2 15.4.5-2 1
6 i
t J
4 lt
- s ll r;
i.
i!':
l
- i 1
i 4
e'-
..s B.
Containment Cooling and Iodine Removal Systems 1.
A reactor shall not be made critical, except for low temperature r
physics tests, unless the following conditions associated with that reactor are met:
The spray additive tank contains not less than 2675 gal, a.
of solution with a sodium hydroxide concentraticn of not less than 30% by weight.
b.
Two containment spray pumps are operable.
c.
Four accident fan-cooler units are operable, d.
All valves and piping, associated with the above components and required to function during accident conditions, are operable.
2.
During power operation, the requirements of 15.3.3.B-1 may be modified to allow any one of the following components to be inoperable at any one time. If the system is not restored to meet the requirements of 15.3.3.B-1 within the time period specified, the reactor shall be placed in the hot shutdown condition. If the requirements of 15.3.3.B-1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold shutdown condition.
~
One accident fan cooler may be out of service provided that cooler a.
is returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The accident t
fan coolers shall be tested to demonstrate operability before initiating maintenance on the inoperable accident fan cooler and shall be tested once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until all accident fan coolers are in an operable status or the reactor is shut down, or 15.3.3-3 Unit 1 - Amendment No. 60 Unit 2 - Amendment No. 65
4
~
9 b.
One conta hment spray pump may be out of service provided the pump is restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The remaining containment spray pump shall be tested to demonstrate operability before initiating maintenance on the inoperable pump and shall be tested once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until both pumps are in an operable status or the reactor is shut 4
down, or
'l i
,A h
i i
1 Unit 1 - Amendment No. 60 Unit 2 - Amendment No. 65 i
15.3.3-3a ms
V R
That is, the appropriate pump motor breakers shall have opened and closed, and all valves shall have completed th'eir travel.-
B.
Containment Spray Svstam System tests shall be performed during reactor shutdowns for major 1.
fuel reloading. The test shall be performed with the isolation valves in the spray supply lines at the containment blocked closed.
Operation of the system is initiated by tripping the normal actuation instrumentation. The motor breakers for the pumps shall be placed in the " test" position for this test.
2.
The test will be considered satisfactory if visual observations indicate all components have operated satisfactorily.
3.
The spray nozzles shall be checked to verify that they are not ob'structed at intervals not exceeding five years.
- C.
Containment Fan Coolers 1.
Each fan cooler unit shall be tested at each refueling to verify proper operation of the backdraft dampers and the service water bypass valves.
2.
Containment fan cooler accident fans shall be tested monthly to verify operability. Acceptable performance shall be that the accident fan starts and running current is verified.
II.
Component Tests s
A.
Pumps 1.
The safety injection pumps, residual heat removal pumps, and 15.4.5-2 Unit 1 - Amendment No. 60 Unit 2 - Amendment No. 65 l
-.-