ML17328A408
| ML17328A408 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/22/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A409 | List: |
| References | |
| NUDOCS 9008310105 | |
| Download: ML17328A408 (8) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No."4" License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated January 31, 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.
9008310i0~
900822 PDR ADOCK 050003i5 PDC 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-58 is hereby amended to read as follows:
Techni cal S ecificati ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 147
, 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:
August 22, 1990 Robert C. Pierson, Director Project Directorate III-I Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation
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ATTACHYENT TO LICENSE At1ENDYIENT NO. 147 FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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.
RENOVE 3/4 3-28 3/4 3-29 3/4 7-10 INSERT 3/4 3-28 3/4 3-29 3/4 7-10
l
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATINGSIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 3.
Pressurizer Pressure-Low a.
Ce e.f.
g Safety In)ection (ECCS)
Reacto~, Trip. (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
< 27.0 /13.0¹
< 3.0
< 8.0
< 18.0¹ Not Applicable Not Applicable
< 48.0 /13.0¹ 4.
Differential Pressure Between Steam Lines-Hi h a.
b.
Ce d.
e.f.
ge Safety In)ection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
< 13.0¹/23.0¹¹
< 3.0
< 8.0
< 18.0¹/28.0¹¹ Not Applicable Not Applicable
< 13.0¹/48.0¹¹ 5.
Steam Flow in Two Steam Lines - Hi h Coincident with T
--Low-Low a.
b.
c
~
d.
e.f.
ge h.
Safety In5ection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Steam Line Isolation
< 15.0¹/25.0¹¹
< 5.0
< 10.0
< 20.0¹/30.0¹¹ Not Applicable Not Applicable
< 15.0¹/50.0¹¹
< 13.0 COOK NUCLEAR PLANT - UNIT 1 3/4 3-28 AMENDMENT NO ~
gg 147
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 6.
Steam Flow in Two Steam Lines-Hi h Coincident With Steam Line Pressure-Low a.
b.
co d.
e.f.
g ~
h.
Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Steam Line Isolation
< 13.0a/23.0M
< 3.0
< 8.0
< 18.08/28.0M Not Applicable Not Applicable
< 14.08/48.0M
< 11.0 7.
Containment Pressure--Hi h-Hi h
& ~
b.
Co Containment Spray Containment Isolation-Phase "B"
Steam Line Isolation Containment Air Recirculation Fan
< 45.0 Not Applicable
< 10.0
< 660.0 8.
Steam Generator Water Level--Hi h<<Hi h a.
Turbine Trip b.
Feedwater Isolation
< 2.5
< 11.0 9.
Steam Generator Water Level--Low-Low a.
Motor Driven Auxiliary Feedwater Pumps b.
Turbine Driven Auxiliary Feedwater Pumps
< 60.0
< 60.0 10.
4160 volt Emer enc Bus Loss of Volta e a.
Motor Driven Auxiliary Feedwater Pumps
< 60.0 ll. Loss of Main Feedwater Pum s
a.
Motor Driven Auxiliary Feedwater Pumps
< 60.0
- 12. Reactor Coolant Pum Bus Undervolta e
a.
Turbine Driven Auxiliary Feedwater Pumps
< 60.0 COOK NUCLEAR PLANT - UNIT 1 3/4 3-29 AMENDMENT NO. gg,
- ging,
] P7
PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3,7.1,5 Each steam generator stop valve shall be OPERABLE.
APPLICABILITY; MODES 1, 2 and 3.
ACTION:
MODE 1 - With 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,POWER 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 - With 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 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 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by:
a.
b.
Part-stroke exercising the valve at least once per 92 days, and f
Verifying full closure within 8 seconds on any closure actuation 0
signal while in HOT STANDBY with T greater than or equal to 541 F
during each reactor shutdown excepr.
nat verification of full closure avR.
within 8 seconds need not be determined more often than once per 92 days.
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 1 3/4 7-10 AMENDMENT NO ging, f'g7.