ML20100F893
| ML20100F893 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/16/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100F896 | List: |
| References | |
| NUDOCS 8412070068 | |
| Download: ML20100F893 (5) | |
Text
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weeg,h UNITED STATES
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NUCLEAR REGULATORY COMMISSION h (-
WASHINGTON, D. C. 20555
'+,..... $
t WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 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 November 9, as modified. November 13, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and 4
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 Comission; C.
There is reasonable assurance (1) 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 common defense and security or to the health and safety of the public; s
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.
i 8412070068 841116 PDR ADOCK 05000301 l
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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:
B.
Technical Specifications The Techn! cal Specifications contained in Appendices A and B, as revised through Amendment No. 91, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-M&
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 16, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-301 Revise Appendix A as follows:
Remove Page Insert Page 15.2.3-2 15.2.3-2 15.2.3-3 15.2.3-3 I
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l (3)* Low pressurizer pressure - >1865 psig for operation at 2250 psia
_primary system pressure
>1790 psig for operation at 2000 psia
_primary system pressure (4)
Overtemperature AT (l 5}
3
- K (T(1+r4S)-T')( W 3) + E3 (P-P') - f(AI))
I
-<aTo (K1 2
2 where indicated AT at rated power, *F ATo
=
average temperature, F T
=
574.2*F T'
=
P pressurizer pressure, psig
=
P' 2235 psig
=
1 117 for operation at 2250 psia primary system pressure
- K) 1 1 30 for operation at 2000 psia primary system pressure 1
0.0150 K
=
2 K
0.000791
=
3 25 sec
=
Tj 3 sec r
=
2 2 sec for Rosemont or equivalent RTD r
=
3 0 sec for Sostman or equivalent RTD
=
2 sec for Rosemont or equivalent RTD T
=
4 0 sec for Sostman or equivalent RTD
=
and f(aI) is an even function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant start-up tests, where q,and qh are the percent power in the top and bottom is total core power in halves of the core respectively, and qt + 9b percent of rated power, such that:
with -17, +5 percent, f(AI) = 0.
(a) for qt ~9b (b) for each percent that the magnitude of q
-q exceeds +5 percent, theATtripsetpointshallbeautomatickilyheducedbyanequiva-lent of 2.0 percent of rated power.
- Appropriate safety analyses shall be performed prior to shifting opera-tion from one primary system pressure to the other.
Unit 2 - Amendment No. 49, 90, 91 15.2.3-2
i exceeds -17 (c) for each percent that the magnitude of qt -9b percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of rated power.
1 (5) Overpower AT ( g )
3 1aTo {K4 - K (1 3 I} (I 5
6 S)- D - M 5
5 4
4 where aTo = indicated AT at rated power, *F T
= average temperature, *F T'
= 574.2*F K
1 1.089 of rated power 4
K 0.0262 for increasing T 5
for decreasing T
.123 for T 1 '
T ror T < T' c
's defined in (4) above,
' Rosemont or equivalent RTD sr Sostman or equivalent RTD
=
4 or Rosemont or equivalent RTD
=
T
= 0 i.c for Sostman or equivalent RTD (6) Undervoltage
>75 percent of nomal voltase (7)
Indicated reactor coolant flow per loop - 190 percent of normal indicated loop flow (8)
Reactor coolant pump motor breaker open (a)
Low frequency set point 157.5 cps (b) Low voltage set point 175 percent of normal voltage.
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Unit 2 - Amendment No. 32, 90 91 15.2.3-3 l
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