ML17331A510
| ML17331A510 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/06/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A511 | List: |
| References | |
| NUDOCS 8011060222 | |
| Download: ML17331A510 (13) | |
Text
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UNtTED STATES NUCLEAR REGULATORY COMMtSSION MfASklNGTON,D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY
~ DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE '
Amendment No. 42 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Th'e application for amendment by Indi ana and Michigan Electric Company (the licensee) dated February 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 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 by changes to the Technical Specifications as indicated in the attachm'ent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
I 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 6, 1980 5
Steven A.
arga, Ch Operating Reactors Branch Pl Division of Licensing
h
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 42 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-3l5 Revise Appendix A as follows:
Remove Pa es 3/4 7-5 3/4 7-e t
P 3/4 7-5 3/4 7-6
PLANT SYSTEMS AUXILIARYFi EDWATER SYSTEM LIMITING CO!lDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
b.
Two feedwater
- pumps, each capable of being oowered from separate emergency
- busses, and
'ne feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABIL!:Y:
MODES 1, 2 and 3.
ACTION:
With one auxiliary fcedwater pump inoperable, restore at least three auxiliary i=edwater pumps (two capable of being powered from separate emergency busses and one capable of being powered by an OPERABLE st~am supply system) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
A; least once per 31 days by:
1.
Starting each pump from the control room.
2.
Verifying that:
a
~
b.
Each motor driven pump develops a discharge pressure of >
1375 p'sig on recirculation flow, and The steam turbine driven pump develops a discharge pressure of";> 1285 psig at a flow of 700 gpm when the secondary steam pressure is greater than 310 psig.
D C ~
COOK-UNIT 1
3/4 7-5 Amendment No. 42, Unit 1
PLRNT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.
Verifying that each pump operates for at least 15 minutes.
0.
Cycling each=testable power operated or automatic valve in
~ the flow path through at least one complete cycle of full travel.
5.
Verifying that each valve (manual, power operated or automatic) in the flow path, incl'uding valves which are locked, sealed, or otherwise secured in position, is in its correct pos ition.
At least once per 18 months during shutdown by:
1.
Cycling each power operated valve in the flow path that is not testable during plant operation, through at least once complete cycle of full travel.
2.
3.
V rifying that each motor driven pump starts automatically upon receipt of each of the following signals:
a}
Loss of m<".in feedwater pumps.
b)
Safety Injection.
c)
Steam Generator Water Level--Low-Low from one steam generator, 2 out of 3 channels.
Verifying that the steam turbine driven pump starts auto-matically upon receipt of each of the following signals:
a)
Steam Generator Water Level Lov -Low from two steam generators, 2 out of 3 channels.
b)
Reactor Coolant Pump Bus Undervoltage.
D.C.COCK-UNIT 1
4.cnd.";,ont No. 42, Unit 1
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UNlTEO STATES NUCLEAR REGULATORY COMMfSS(ON WASHINGTON, O. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
24 License No. DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 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 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; I
I 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 sat isfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.{2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 24, 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
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 6,
1980 a
e
.ara, ef te Operating 'React Branch 0'1 Division of Lice sing
)
ATTACHMENT TO LICENSE 'AMENDMENTS AMENDMENT NO.
~4 TO FACILITY'OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:
'PP 3/4 7-5 3/4 7-6 Insert Pa es 3/4 7-5 3/4 7-6
PLANT SYSTEMS AUXILIARYFF EDWATER S YSTER, LIHITINR CONDITION'FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two feedwater
- pumps, each capable of being powered from separate emeraency
- busses, and h
b.
One feedwater pimp capable of beina powered from an OPFRABLE steam supply system.
APPLICABILITY:
MODES 1, 2 and 3.
ACiION:
Hith one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps,(two capable of beina powered from separate emergency busses and one capable of beina powered by an OPERABLE steam supply system) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUT00>!N within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVE ILLANC REQUIREMENTS 4.7.l.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
Verifying ',that each motor driven pump develops a discharae pressure
> 1375 psia on recirculation flow.
2 ~
3.
b.
At D. C."COOK-Verifying th t the steam turbine driven pump develops a
discharqe "pr".ssure of > 1285 psig at a flow of > 700 aDm when the sec-ndarV steam supply'~>>"essure'is'oeeater
+ban 310 psia.
lhe provisions o
Specification 4.0.4 are not applicable for entry into HODE 3.
Verifying 'that each valve (manual, power operated or automatic) in the flow path including va1ves which are locked, sealed, or otherwise secured in position, is in its correct position.
least once per 18 months by..
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
UNIT 2 3/4 7-5 Amen iment
"!o 2"
Unit 2
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS Continued 2.
Yerifying that each motor driven pump starts automatically upon receipt of each of the following si gnal s:
a)
Loss"*of main feedwater pumps.
b)
Sa,ety Injection.
c)
Steam G nerator Water Level--Low-Low from one steam generator, 2 out of 3 channels.
3.
Yerifying tha. the steam turbine driven pump starts auto-matically upon receipt of each of the following signals:
a)
Steam Generator Mater Level Low-Low from two ste m
'generators, 2 out of 3 channels.
b)
Reactor Coolant Pump Bus Undervoltage.
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D. C.
COOK - UNIT 2 3/4 7-6 Amendment No. 24, Unit 2