ML20115B422
| ML20115B422 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/04/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115B425 | List: |
| References | |
| NUDOCS 8504170662 | |
| Download: ML20115B422 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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- a WASHINGTON, D. C. 20555 1.....j WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-24 1.
- The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated November 9, as modified November 14, 1984 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 confonnity 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; I
l 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Comission's regulations and all applicable requirements have been satisfied.
l I
8504170662 850404 l
PDR ADOCK 05000266 l
P PDR I
L.
. 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. 90, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION 4
1 James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 4,1985
ATTACHMENT TO LICENSE AMENDMENT NO. 90 TO FACILITY OPERATING LICENSE NO. DPR-24 DOCKET NO. 50-266 Revise Appendix A as follows:
Remove Pages Insert Pages 15.2.3-2 15.2.3-2 15.2.3-3 15.2.3-3 PLEASE NOTE:
There are two sets of TS pages attached.
One set is effective as indicated on this amendment and it is so indicated on a cover sheet.
The second set is effective upon implementation of Amendnent No. 86 on or about May 30, 1985. This set incorporates the changes made by Amendment No. 86 and this Amendment - No. jg!, This is indicated on the cover sheet for the second set of pages.
1
These pages are effective as indicated on amendment No. 90 They do not reflect the changes made by Amendment No. 86 which is to be effective upon completion of the next refueling outage which ends approximately May 30, 1985.
r M
- (3) Low pressurizer pressure - 11865 psig for operation at 2250 psia primary system pressure 1
1 790 psig for operation at 2000 psia primary system pressure (4) Overtemperature AT ( p 3) 1+tjS 1aTo (K; - K (T(j 3)-T')(j 3)+K3 (P-P') - f(al)).,
90 2
where ATo = indicated AT at rated power, OF T
= average temperature, OF 0
s -
T'
= 574.2 F P
= pressurizer pressure, psig P'
= 2235 psig
-*K
<1.117 for operation at 2250 psia primary system pressure j
<1.30 for operation at 2000 psia primary system pressure K
= 0.0150 2
'K
= 0.000791 3
tj
= 25 sec-
= 3 see t 2 3
= 2 sec for Rosemont or equivalent RTD 1
= 0 see for Sostman or equivalent RTD 4
= 2 sec for Rosemont or equivalent RTD 90 T
= 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 startup tests, where qt and qh are the percent power in the top and bottom halves of the core respectively, and qt + 9b is total core power in percent of rated power, such that:
(a) for qt " 9b with-17,+9 percent,f(AI)=0.
(b) for each percent that the magnitude of q
-q exceeds +9 percent,theATtripsetpointshallbelutomIticallyreduced by an equivalent of two percent of rated power.
- Appropriate safety analyses shall be performed prior to shifting opera-tion from one primary system pressure to the other.
15.2.3-2 Unit 1 - Amendment No. AA, 81, 90
(c) for each percent that the magnitude of qfly rhduced by an equivalent
-q exceeds -17 percent, the AT trip setpoint shall be automatica of two percent of rated power.
(5) Overpower AT (
3)
TSS 1
1
<aTo (K4-KIS 7)(Q)T-K6 [T(3,1 3)-M- %
4 90 where indicated aT at rated power, OF aTo
=
T
= average temperature, OF T'
= 574.2 K
= <1.089 of rated power 4
i K
= 0.0262 for increasing T 5
= 0.0 for decreasing T K'
= 0.00123 for T 1 T' 6
= 0.0 for T < T' 5
.= 10 see
.t f(41)asdefinedin(4)above, r3
= 2 sec for Rosemont or equivalent RTD 90
= 0 sec for Sostman or equivalent RTD T
= 2 sec for Rosemont or equivalent RTD 4
= 0 see for Sostman or equivalent RTD (6) Undervoltage - >75 percent of normal voltage (7) Low indicated reactor coolant flow per loop - >90% of normal indicated loop flow (8) Reactor coolant pump motor breaker open l
(a) Low frequency set point > 57.5 cps j
(b) Low voltage set point > 75% of normal voltage l
l t
i 15.2.3-3 Unit 1 - Amendment No. 3, 28,90 l
l L
,y Upon implementation of Amendment No. 86 on completion of the next refueling outage which ends approximately May 30, 1985, these pages are to replace those issued with Amendment No. 90 on April 4.1985.
These attached pages incorporate changes from both Amendment No. 86 x
and Amendment No. 90.
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T
'l g s W
N
't
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r s7 y
- (3) Low pressurfrer pressure - >1865 psig for operation at 2250 psia
- g. primary system pressure
>1790 psig for operation at 2000 psia primary system pressure
~(4) %Overtemperature AT ( p,j 3) j 1 +r S 90 laTo (K q K (T(
3)-T')(),j3)+K3 (P-P') - f(AI))
j 2
where w
ATo = indicated AT at rated power, OF T
= average temperature, OF 0
T'
= 574.2 F P
= pressurizer pressure, psig P'-
= 2235 psig s
- Kj ' 1 117 for operation at 2250 psia primary system pressure 1
1 K ~
1 30 for operation at 2000 psia primary system pressure
= 0.0150 2
K
= 0.000791 3
tj
= 25 sec
= 3 sec J2
't
= 2 sec for Rosemont or equivalent RTD 3
= 0 sec for Sostman or equivalent RTD 4
= 2 sec for Rosemont or equivalent RTD 90 T
= 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 du>ing. plant startup tests, where qt and qb are the percent power in the. top and bottom halves of the core respectively, and qt + 9 s
is total core power in percent of rated power, such that:
b s
(a) for qt - 9b with-17,+5 percent,f(aI)=0.
l86 1
(b) for each percent, that the magnitude of q q exceeds +5 186 percent, the AT trip set point shall be ku omItically reduced t
by an equivalent o.f 2.0 percent of rated power.
l86
+ = '
- Appropriate sa ty analyses shall be performed prior to shifting opera-tion from one' primary system pressure to the other.
c.
J 15.2.3-2 Unit 1 - Amendment No. (A, SJ, 84 90 v
s.
m.
m
(c) for each percent that the magnitude of q, - qs exceeds -17 percent, the AT trip setpoint shall be automaticaTly reduced by an equivalent of 2.0 percent of rated power.
186 (5) Overpower AT ()
3) 3 5S T
1 1
4-K( 7 )(l+t saTo {K 4)T-K (1+'4h-5 S
6
~
90 where ATo = indicated AT at' rated power, OF T
= average temperature, OF 0
T'
=-574.2 F l86 K
1
= $.089 of rated power 4
K
= 0.0262 for increasing T 5
= 0.0 for decreasing T K
= 0.00123 for T 1 T' 6
= 0.0 for T < T' T
= 10 sec 5
f (aI) as defined in (4) above, 3
= 2, sec for Rosemont or equivalent RTO T
= 0 sec for Sostman or equivalent RTD s
4
= 2 sec for Rosemont or equivalent RTD t
90
= 0 sec for Sostman or equivalent RTD (6) Undervoltaget-175 percent of normal voltage I
(7)
Indicated reactor coolant flow per loop - >90 percent of normal l86 j
indicated loop flow (8) Reactor coolant pump motor breaker open (a) Low frequency set point g 57.5 cps (b) Low voltage set point t 75% of normal voltage 15.2.3-3 Unit 1 - Amendment No. 3, 28,86, 90
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