ML17328A456
| ML17328A456 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/18/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A457 | List: |
| References | |
| NUDOCS 9009280151 | |
| Download: ML17328A456 (8) | |
Text
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$ y*yW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO.
50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that The application for amendment by Indiana Michigan Power Company (the licensee) dated May 14,
- 1990, 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.
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2-2.
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:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 135
, are hereby incorporated'n 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 Robert C. Pierson, Director Project Directorate III-1 Division of Reactor Projects - III,
'V, V, 8 Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1990
ATTACHMENT TO LICENSE AMENDMENT NO.
) 35 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by. removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 3/4 3-27 3/4 3-28 3/4 7-10 INSERT 3/4 3-27 3/4 3-28 3/4 7-10
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS
,3.
Pressurizer Pressure-Low a.
b.
C.
d.
e.
Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Motor Driven Auxiliary Feedwater Pumps Essential Service Pater System Less than or equal Less than, or equal Less than or equal Less than or equal to 24.0*/12.0~
to 2.0 to 8.0 to 18.0¹ Not Applicable Less than or equal to 60.0 Less than or equal to 48.0*/13.0" 4.
Differential Pressure Between Steam Lines-Hi h a.
b.
C.
d.
e.
Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containmen" Purge and Exhaust Isolation Motor Driven Auxiliary Feedwater Pumps Essential Service Vater System Less than or equal Less than or equal Less than or equal Less than or equal to 12.0¹/24.0¹¹ to 2.0 to 8.0 to 18.0~/28.0¹¹ Not Applicable Less than or equal to 60..0 Less than or equal to 13.0¹/48.0 5.
S earn Flow in Two Steam Lines
- Hizh Coincident with Tave.--Low-Low a.
b.
C.
d.
e.
f.
gh.
Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containmen" Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Mater System Steam Line Isolation Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Less than or equal to 13.0 COOi',."i%CLEAR PLEAT
- UNIT 2 3/4 3-27 AMENDMENT NO. P5, NS, 135
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION 6.
Steam Line Pressure--Low
RESPONSE
TIME IN SECONDS a.
b.
C.
d.
e.
gh.
Safety In)ection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Motor Driven Auxiliary Feedwater Pumps Essential Service Mater System Steam Line Isolation Less than or equal Less than or equal Less than or equal Less than or equal Not Applicable to 12.0¹/24.0¹¹ to 2.0 to 8.0 to 18.0¹/28.0¹¹ Less than or equal to,60.0 Less than or equal to 14.0¹/48.0¹¹ Less than or equal to 11,0 7.
Containment Pressure--Hi h-High a.
b.
C.
Containment Spray Containment Isolation-Phase "B"
Steam Line Isolation Il Containment Air,Recirculation Fan Less than or equal Not Applicable Less than or equal Less than or equal to 45.0 to 10.0 to 600.0 S.
S-earn Generator Vater Level--Hi h-Hi h a.
Turbine Trip b.
Feedwater Isolation Less than or equal to 2.5 Less than or equal to 11.0 9.
S:earn Generator Vater Level--Low-Low a.
Motor Driven Auxiliary Feedwater Pumps b.
Turbine Driven Auxiliary Feedwater Pumps lt Less than or equal to 60.0 Less than or equal to 60.0 10.
4160 volt Emer enc 'us Loss of Volta e a.
Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 11.
Loss of Main Feedwater Pum s
a.
Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0
- 12. Reactor Coolant Pum Bus Undervolta e
a.
Turbine Driven Auxiliary Feedwater Puli.ps Less than or equal'to 60.0 COOK NiCLEAR PLANT - UNIT 2 3/4 3-28 AMENDMENT No. gg, f07, 135
"I
PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3 '.1.5 Each steam generator stop valve shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
MODE 1 -
Vith one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POKER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
MODES 2
- Vith one steam generator stop valve inoperable, subsequent and 3
operation in MODES 2 or 3 may proceed provided:
a.
The stop valve is maintained closed.
b.
The provisions of Specification 3.0.4 are not applicable.
Otherwise, be in HOT SHUTDOWN ~ithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEiLLANCE RE UZREMENTS 4.7.1.5.1 Each steam generator stop valve shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.
4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.
COOK NUCLEAR PLANT - UNIT 2 3/4 7-10 AMENDMENT NO. 82,
I9