ML20078R173
| ML20078R173 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/31/1983 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078R176 | List: |
| References | |
| TAC-48375, TAC-48376, NUDOCS 8311140408 | |
| Download: ML20078R173 (7) | |
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- UNITED STATES '
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',i NUCLEAR REGULATORY COMMISSION 5
8 WASHINGTON, D. C. 20555 WISCONSIN ~ ELECTRIC POWER COMPANY'
. DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT N0.,l_
~ AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
'A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedApril 27, 1982 as modified March 23, 1903, 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; 8.
The facility will operate in conformity with the-application, the provisions of the Act, and the rules and regulations of the Comission;
.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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon
. 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 satisfied.
831114o408 831031 hDRADOCK 05000;%4, PDR
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. 78
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.-
3.
This license amendment is. effective following installation of the new relays but no later than March 1984.
FOR THE NUCLEAR REGU,LATORY COMMISSION A.,f '
James R. Hiller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technial Specifications Date of Issuance: October 31, 1983 0
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UNITED STATES
),
NUCLEAR REGULATORY. COMMISSION 3
WASHINGTON, D. C. 20555 5
+
WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NUCLEAR PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 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 April 27, 1982 as modified March 23, 1983, complies with the standards and re i t
f the Atomic Energy
.Act of 1954, as amended (the Act) qu remen s o and the Commission's rules and regulations set forth in 10 CFR Cha,ter 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.
~
~
'-M 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'0perating License No.
OPR-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. uB2 are hereby incorporated in the license.-.The licensee shall operate the~ facility in accordance with the Technical Specifications.
3.
This-license amendment is effective following installation of the new relays but no later than November 1984.
FOR THE NUCLEAR REGULATORY COMMISSION 7
(
-w James R. Miller, Chief Operating Reactors Branch #3 b-Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 31, 1983
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'm ATTACHMENT TO LICENSE AMENDMENTS s
AMENDMENT N0. 78 T0' FACILITY OPERATING LICENSE N0. DPR-24
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AMENDMENT N0. 82 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET N0. 50-266 AND 50-301 Revise Appendix A as follows:
Remove Pages
- Insert Pages
- L Table 15.3.5-1 Table 15.3.5-1 page 2 of 2 page 2 of 2 Table 15.4.1-1 Table 15.4.1-1
-- (continued)
(continued) v.
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9 0
4 TABLE 15.3.5-1.(Continued)
(Page 2 off2) uo' NO.
FUNCTIONAL UNIT CHANNEL SETTING' LIMIT
'9.
Degraded Voltage (4.16 KV)
Disconnection of affected.
3875 volts i 2%
bus.from offsite power Time dela less than 60'sec g' y
'at 0-100%y:of voltage setting
.??
10.
Loss of Voltage to w
'3220 volts i'2%
a.
4.16 KV Disconnection of affected a.
-bus from offsite power Time delay:. <l. sec + 10%.
at 0-100% of voltage setting **
b.
480 V Load shedding
.b.
2.6 volts i 3%
Time delay:.<.75 sec i 10% l at 0 volts
< 3.5 sec + 20% at' 90% of
-voltage setting **
II
- This limit is effective upon installation of the associated relays but in no case later than II upon return to power from the Fall 1983 refueling outage for Unit 1 and the Fall 1984 refucling a$
outage for Unit 2.
)2):
ea.
TABLE 15.4.1-1 (pge 4 of 4)
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)'.
l 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 period.
Not required during periods of refueling shutdown if steam generator vessel temperature is greater than 70*F.
a.
Performance of a channel functional test on the' PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which thelP'RV is required operable O
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.
l l
76 38, 47, 55, 80 Unit 1 - Amendment No.
50, 55, 63, Unit 2 - Amendment No.
.