ML17333A381
| ML17333A381 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/19/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17333A382 | List: |
| References | |
| NUDOCS 9603270305 | |
| Download: ML17333A381 (13) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION VJAS H INGTON, D.C. 20Ri5-0001 INDIANA MICHIGAN POWER COMPANY ILcKKT 5 15 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 ENDMENT TO F CILITY OPERATING LICENSE Amendment No. 209 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 December 19,
- 1995, and supplemented February 16,
- 1996, 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.
9b03270305 qb03i9 PDR ADQCK 050003i5 PDR
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:
ec nical S ecificatio s
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 209
, 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 issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 19, 1996 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 209 TO 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 vertical lines indicating the area of change.
HOVE 3/4 6-2 3/4 6-4 3/4 6-5 3/4 6-9 3/4 6-9a INSERT 3/4 6-2 3/4 6-4 3/4 6-5 3/4 6-9 3/4 6-9a
3/4 LIMH'INGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTLEAKAGE LIMITINGCONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of 6 La, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 12.0 psig, and b.
A combined leakage rate of E 0.60 La for all penetrations and valves subject to Types B and C tests when pressurized to Pa.
APPLICABILITY:
ACTION:
MODES 1, 2, 3 and 4.
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to 6 0.75 La and the combined leakage rate for all penetrations and valves subject to TyPes B and C tests to 6 0.60 La Prior to increasing the Reactor Coolant System temPerature above 200'F.
SURVEILLANCERE UIREMENTS 4.6.1.2 Perform leakage rate testing in accordance with 10 CFR 50 Appendix J Option B and Regulatory Guide 1.163, dated September 1995.
a.
Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
b.
The provisions of Specification 4.0.2 are not applicable.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 6-2 AMENDMENT48, 440, 4P, 406,209
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTAIR LOCKS LIMITINGCONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of 6 0.05 La at Pa, 12 psig.
APPLICABILITY:
ACTION:
MODES 1, 2, 3 and 4.
With an air lock inoperable, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCERE UIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
In accordance with 10 CFR 50 Appendix J Option B and Regulatory Guide 1.163, dated September 1995, and b.
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 64 AMENDMENT440, 209
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS This Page Intentionally Left Blank COOK NUCLEAR PLANT-UNITI Page 3/4 6-5 AMENDMENT440,209
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTSTRUCTURAL INTEGRITY LIMITINGCONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY:
MODES I, 2, 3 and 4.
ACTION:
With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCERE UIREMENTS 4.6.1.6 The structural integrity of the containment structure and steel liner shall be determined in accordance with 10 CFR 50 Appendix J Option B and Regulatory Guide 1.163, dated September 1995.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 6-9 AMENDMENTm,209
'0 3/4 LIMH'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTVENTILATIONSYSTEM LIMITINGCONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities.
No more than one purge supply path and one purge exhaust path shall be open at a time.
APPLICABILITY:
MODES I, 2, 3, and 4.
ACTION:
a.
With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either:
1)
Restore the inoperable valve to OPERABLE status, or, 2)
Deactivate the automatic valve secured in the closed position.
b.
Operation may then continue until performance of the next required valve test provided that Ae automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 3,1 days.
c.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCERE UIREMENTS 4.6.1.7.1 The surveillance requirements of Technical Specifications 3/4.6.1.2 and 3/4.6.3.1 apply.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 6-9a AMENDMENT66, 49$, 209
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UNITED STATES NUCLEAR REGULATORY COMMISSION V/ASHINGTON, D.C. 205M-0000 INDIANA M CHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 19,
- 1995, and supplemented February 16,
- 1996, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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 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 B,
as revised through Amendment No.
193
, 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 issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 19, 1996 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO. 193 FACILITY OPERATING LICENSE NO.
DPR-74 DOCK T 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 vertical lines indicating the area of change.
g~HOV 3/4 6-2 3/4 6-4 3/4 6-5 3/4 6-9 3/4 6-9a NSERT 3/4 6-2 3/4 6-4 3/4 6-5 3/4 6-9 3/4 6-9a
3/4 LIMINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTLEAKAGE LIMITINGCONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of ~ La, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P>> 12 psig, and b.
A combined leakage rate of 6 0.60 La for all penetrations and valves subject to Types B and C tests when pressurized to Pa.
APPLICABILITY:
ACTION:
MODES 1, 2, 3 and 4.
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L>> or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to S 0.75 La and the combined leakage rate for all penetrations and valves subject to TyPes B and C tests to E 0.60 La Prior to increasing the Reactor Coolant System temPerature above 200'F.
SURVEILLANCERE UIREMENTS 4.6.1.2 Perform leakage rate testing in accordance with 10 CFR 50 Appendix J Option B and Regulatory Guide 1.163, dated September 1995.
Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
b.
The provisions of Specification 4.0.2 are not applicable.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-2 AMENDMENTm, ~, 193
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTAIR LOCKS LIMITINGCONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
APPLICABILITY:
ACTION:
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and An overall air lock leakage rate of E 0.05 La at P>> 12.0 psig.
MODES I, 2, 3 and 4.
With an air lock inoperable, maintain at least one door closed; restore the air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCERE UIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
a.
In accordance with 10 CFR 50 Appendix J Option B and Regulatory Guide 1.163, dated September 1995, and b.
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 64 AMENDMENT 193