ML19350D332
| ML19350D332 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/31/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350D333 | List: |
| References | |
| TAC-12955, TAC-12956, TAC-47404, TAC-47405, NUDOCS 8104150267 | |
| Download: ML19350D332 (10) | |
Text
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UNITED STATES y
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g NUCLEAR REGULATORY CCMMISSION
...E WASHINGTON, D. C. 20555 DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. DPR-24 1.
The Nuclear Reglatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated July 28, 1977, as modified August 24, 1979, January 17, April 17 and September 22, 1980, 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 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 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 Comission's regulations and all applicable requirements have been satisfied.
810.4150 flat
. 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. 47, 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.
Final implementation shall be not later than 60 days following the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION G
obert A. Clark, Chief Operating Reacters Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1981
'o UNITED STATES
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-306 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 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 July 28, 1977 as modified August 24, 1979, J anuary 17, April 17 and September 22, 1980, 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 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 j
conducted in conpliance 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 l
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.
l
j
- 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 ho. DPR-27 is hereby amended to read as follows:
(B) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical i
Specifications.
i 3.
This license amendment is effective as of the date of its issuance.
Final inplementation shall be no later than 60 days following the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing A tachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1981 i
1
l ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 52 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301
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Revise Appendix A as follows:
Remove Pages Insert Pages Table 15.3.5-1 Table 15.3.5-1 Table 15.3.5-3 Table 15.3.5-3 Table 15.4.1-1 Table 15.4.1-1 Table 15.4.1-1 (continued)
Table 15.4.1-1 (continued) 15.4.6-1 15.4.6-1 s
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TABLE 15.3.5-1 ENGINEEEED SAFETY FEATURES INITIATION INSTRUMENT SETTING LIMITS yy NO.
FUNCTIONAL UNIT CitANNEL SETTING LTHIT
-m m
1 liigh Containment Pressure (111)
Safety Injection
- 1 6 psig
{[
er :r 2
liigh Containment Pressure (111-111)
- a. Containment Spray 1 30 psig pp
- b. Steam Line Isolation of 1 20 psig pp Both Lines ne 3
Pressurizer Low Pressure Safety Injection
- 1 1715 psig 4
Low Steam Line Pressure Safety Injection *
> 500 psig Lead Time Constant
> 12 seconds Lag Time Constant 1 2 seconds 5
liigh Steam Flow in a Steam Line Steam Line Isolation of d/p corresponding to 1 0.66 x Coincident with Safety injection and Affected Line 106 lb/hr at 1005 psig
> 540 F avs 6
6 liigh-high Steam Flow in a Steam Line Steam Line luolation sc d/p corresponding to 4 x 10 Coincident with Safety Injection of Affected Line Ib/hr at 806 psig
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Degraded Voltage (4.16KV)
Disconnection of affected
> 3675 volta 12%
bus from offsite power Time delay: 13.6 sec. 15% at 0-95% of voltage setting 8
Loss of Voltage a.
4.16 KV Disconnection of affected
- a. 2450 volts 13%
bus from offsite power Time delay: 0.3 sec. 15% at start Diesel 0 volts i
((
1.2 sec. 15% at 90% of gg voltage setting l
cp b.
480V Load Shedding
- b. 256 volts 13%
@E Time delay: 0.75 sec. 15% at 0 voltu UU 3.5 uee. 35% at 90% of volingo nel l ing
'" N s
- InleInten also contalomont luolatlim. f oo.lwas or l i n..
luolasson anil niartinn of nii cons a lnment lano.
i l
d/p means differential pressure I
TABLE 15.3.5-3 EMERGENCY COOLING gs gs rr OPERATOR ACTION NN NO. OF MIN.
MIN.
PERMISSIBLE 1F CONDITIONS OF g' gs NO. OF CllANNELS OPERABLE DEGREE OF BYPASS COLUMN 3 OR 4 gg p' D-NO.
FUNCTIONAL UNIT CilANNELS TO TRIP CllANNELS REDUNDANCY CONDITIONS CANNOT BE MET I e g:g:
1 SAFETY INJECTION N'$
a.
Manual 2
1 1
1 Ilot Shutdown ***
gg b.
liigh Containment Pressure 3
2 2
1 Ilot Shutdown ***
c.
Steam Generator Low Steam Pressure / Loop 3
2 2
1 Primary Pressure is llot Shutdown ***
Less than 1800 psig d.
Pressurizer Low Pressure 3
2 2
1 Primary Pressure is llot Shutdown ***
Less than 1800 psig 2.
Manual 2
2 2
Hot Shutdown ***
b.
111-111 Containment Pressure 2 sets 2 of 3 2 per 1/ set ilot Shutdown ***
(Containment Spray) of 3 in each set set f( [
3.
SAFETY RELATED ELECTRICAL g
BUSES 0
W n, Degraded Voltage (4.16KV) 3/ bus 2/ bus 2/ bus 1/ bus aogg a.
f f b.
Loss of Voltage (4.16KV) 2/ bus 1/ bus 1/ bus 1
wU ja =
c.
Loss of Voltage (480V) 3/ bus 2/ bus 2/ bus 1
Ilot Shutdown ***
tn u
- Must actuate 2 switches simultaneously.
- If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the unit in cold shutdown conditions.
- Normal operation provided both diesel generators are available, and the associated diesel generator is operating and providing power to the affected safeguards bus.
If minimum conditions are not met within 7 days, affected unit shall be placed in hot shutdown.
TABLE 15.4.1-1 MINIMUM FREQUENCIES FOR CllECKS, CALIBRATIONS AND TEST OF INSTRUMENT CitANNELS mm 0-Channel N
Description Check Calibrate Test Remarks ww E$
1.
Nuclear Power Range S (1) *
- D (1)**
B/W (2)**
(1) lleat Balance O 0-M*(3)**
Q*(3)**
(2) Signal to AT; bistable g:g:
action (permissive, rod stop, trips) rr (3) Upper and lower chambers for axial off-set 2.
Nuclear Intermediate Range S (1)**
N.A.
P (2)
(1) Once/ shift when in service (2) Log level; bistable action (permissive, rod stop, trips) 3.
Nuclear Source Range S (1)
N.A.
P (2)
(1) Once/ shift when in service (2) Bistable action (alarm, trips) 4.
Reactor Coolant Temperature S
R B/W (1)**
(1) Overtemperature-Delta T (2)
(2) Overpower - Delta T 5.
Reactor Coolant Flow S**
R M**
6.
Pressurizer Water Level S**
R M**
7.
Pressurizer Pressure S**
R M**
gg am 8.
4 Kv Voltage N.A.
R MA*
Resctor protection circuits only 3S 9.
Analog Rod Position S (1) *
- R M**
(1) With step counters By means of the movablo in-core detector system.
% 3.
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- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not heen performed during the previous surveillance period. Tents of perminutve and low power trip hintable net-en w points which cannot be done during power operations shall be conducted prior to startup if not done in the previous two wecku.
4 TABLE 15.4.1-1 (continued)
Channel Description Check Calibrate Test Remarks E$
g.g.
24.
Containment Pressure S
R M**
Narrow range containment pressure
(-3.0, +3 psig excluded) ae EE nn 25.
Steam Generator Pressure 3***
R M***
uw 26.
Turbine First Stage Pressure S**
R M**
27.
Emergency Plan Radiation Instruments M
R M
28.
Environmental Monitors M
N.A.
N.A.
29.
Overpressure Mitigating System S
R 30.
Degraded 4.16KV Voltage S
R M**
31.a Loss of Voltage (4.16KV)
S R
M**
b Loss of Voltage (480V)
S R
MA*
32.
4160 V. Frequency N.A.
R N.A.
S
- Each Shift M - Monthly ff D
- Daily P - Prior to each startup if not done previous week hh W
- Weekly R - Each Refueling Shutdown (But not to exceed 20 months, gm except for first core cycle)
B/W - Biweekly NA - Not applicable oo Not required during periods of refueling shutdown, but must be performed prior to starting up if it has yy not been performed dtsing the previous surveillance period.
Nog required during periods of refueling shutdown if steam generator vessel temperature is greater than ma 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 the PORV is required operable 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 IX.
15.4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS Apolicability Applies to periodic testing and surveillance requirements of the emergency power system.
Obiective To verify that the emergency power system will respond promptly and properly when required.
Specification The following tests and surveillance shall be performed as stated:
A.
Diesel Generators 1.
Manually-initiated start of the diesel generator, folicwed by =anual synchronization with other power sources and assumption of load by the diesel generator shall not exceed 2850 KW.
This test will be conducted monthly with a mini =um running time of 30 minutes on each diesel generator. Normal plant operation will not be affected.
2.
Automatic start of each diesel generator, load shedding, and restora-tion to operation of particular vital equip =ent, initiated by an actual interruption of normal A-C station service power supplies to associated engineered safety systems busses together with a si=ulated safety injection signal.
In addition, after the diesel generator has carried its load for a minimum of 5 minutes, automatic load shedding and restoration of vital loads are tested again by manually tripping the diesel generator output breaker. This test will be conducted during reactor shutdown for major fuel reloading of each reactor to assure that the diesel-generator will start and assume
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required load in less than the time periods listed in the FFDSAR Section 8.? af ter the initial starting signal. During this test a checkout of emergency lighting will be performed, including the i
l changeover relay for DC lights.
I Foint Beach Unit 1 Amendment No. 47 Point Beach Unit 2 15.4.6-1 A=endnent No. 52
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