ML20099H682
| ML20099H682 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/11/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099H685 | List: |
| References | |
| NUDOCS 9208190155 | |
| Download: ML20099H682 (8) | |
Text
-
. gatog%
y"
,j UNITED STATES g,377, ;
NUCLEAR REGULATORY COMMISSION o
g WASHINGTON. D.C= 205S5
....+
NORTHERN STATES POWER COMPANY QQCKET NO. 50-282 PRAIRJE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.100 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated August 3, 1992, 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 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.
2.
Accordingly, the license is amended l'y changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-
. graph 2.C.(2) of facility Operating License No. DPR-42 is hereby amended to read as follows:
4 9208190155 920811 PDR ADOCK 05000282 P
r.;
2 Technical SDecifications The Technical Specifications contained in Appe'.ix A, as revised through-Amendment No.100, 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 COMMISSION
\\
r-s.,
c) /
s LL yard B.rflarsh, Director '
Project Di/ectorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance. August 11, 1992 t
L l
j.;
e L
l l
L
ATTACHMENT TO LICENSE AMENDMEhi NO. 100
[E1LITY OP_ERATING LICENSE NO. OPR-42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
ELMQYL INSERT TS.4.6-2 TS.4.6.2
TS.4.6 3 4
4.6.A.2. At least once each 6 months, for each diesel generator:
a.
Verify the diesel generator starts and accelerates to at least 900 rpm in less than or equal to 10 seconds, b.
Verify the generator voltage and frequency to be 4160 1 420 volts and 6011.2 Hz within 10 seconds after the start signal, c.
Manually synchronize the generator, load to at least 1650 kW in less than or equal to 60 seconds and operate for at least one hour.
d.
This test should be conducted in accordance with the manufacturer's recommendations regarding engine prelube and shutdown procedures where possible.
3.
At least once each 18 months:
a.
Subject each diesel generator to a thorough inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service.
b.
For each unit, simulate a loss of offsite power in conjunction with a safety injection signal, and:
1.
Verify de energiration of the emergency buses and load l
shedding from the emergency buses.*
2.
Verify the diesels start on the auto start signal and energize the emergency buses f' one minute.
This test should be conducted in accordance with the manufacturer's l
recommendations regarding engine prelube and shutdown procedures where possible.
3.
Verify that the auto connected loads do not exceed 3000 kv.
4.
Verify that the diesel generator system trips, except those for engine overspeed, ground fault, and generator differential current, are automatically bypassed, c.
Verify the capability of each generator to operate at least one hour while loaded to 3000 kw.
d.
Verify the capability of each generator to reject a load of at least 650 kw without tripping.
e.
During this test, operation of the emergency lighting system shall be ascertained.
Demonstration of the proper tripping of the main supply and tie breakers on.
the emergency buses may be delayed, on a one time basis, until the Unit 1 and 2 outages scheduled for the Fall of 1992.
Prairie Island Unit
- Amendment No.- 25 )J,100 Preirie Island Unit 2 - Amendment No J),EA,93 CL
i ynoug
.s d' '
y%
UNITED STATES 3
) E NUCLEAR REGULATORY COMMISSION
[
WASHINGTON. D.C 20%5 o
%,'...+/
NORTHERN STALES POWER COMPANY DOCKET N0m'iO-306 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 Licensa No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated August 3, 1992, 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;
8.
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 endt.ngering 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(?) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
.. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.93, are hereby incorporated in the license.
Tl.e 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 L. dyard B arsh, Director,~,
c Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 11, 1992 9
~
ATTACHMENT TO LICENSE AMENDMENT N0, 93 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Revise Appendix A Technical S>ecifications by removing the page identified below and inserting the attacled page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
REMOVE INSERT TS.4.6.2 TS.4.6.2 e
i TS.4.6 2
[ E
' 4.s i 4 b ast once each 6 months, for each diesel generator:
)
a.
Verify the diesel generator starts and accelerates to at least 900 rps in less than or equal to 10 seconds, b.
Verify the generator voltage and frequency to be 4160 1 420 volts and 60 1 1.2 Hz within 10 seconds after the start signal.
c.
Manually synchronize the generator, load to at least 1650 kW in less than or equal to 60 seconds and operate for at least one hour.
d.
This test should be conducted in accordance with the manufacturer's recommendations regarding engine prelube and shutdown procedures where possible.
3.
At least once each 18 months:
a.
Subject each diesel generator to a thorough inspect.,
accordance_ with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service.
b.-
For each unit, simulate a loss of offsite power in conjunction with a safety injection signal, and:
1.
Verify de energization of the emergency buses and load l
shadding from the emergency buses.*
2.
Verify the diesela start on the auto start signal and energize the emergency buses in one minute. This test should be conducted in accordance with the manufacturer's l
recom:nendations regarding engine prelube and shutdown proceoures where possible.
3.
Verify that the auto connected loads do not exceed 3000 kw.
4.
Verify that the diesel generator system trips, except those for engine _overspeed, ground fault, and generator differential current, are automatically bypassed, c.
Verify the capability of each generator to operate at least one hour while loaded to 3000 kv.
d.
Verify the capability of each generator to reject a load of at least 650 kw without tripping.
e.
During this test, operation of the emergency lighting system shall be ascertained.
- Demonstration of the proper tripping of the main supply e.nd tie breakers on the emergency buses may be delayed, on a one time basis, until the Unit 1 and 2 outages scheduled for the Fall of 1992.
Prairie Island Unit l'- Amendment No. 25,92,100 Prairie Island Unit. 21-Amendment No. 2),8A,93,
,