ML17331B411
| ML17331B411 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/01/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331B412 | List: |
| References | |
| NUDOCS 9406080215 | |
| Download: ML17331B411 (5) | |
Text
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+**g0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No.
DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated March 9,
- 1994, as supplemented April 13,
- 1994, 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; 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.
940608021S'94060f PDR ADDCK 050003f6
- 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-74 is hereby amended to read as follows:
Technical S ecifications 3.
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 162
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with
.the Technical Specifications.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Dune 1.
1994 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT N0.162 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below'nd inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
t REMOVE 3/4 6-3 3/4 6-4*
INSERT 3/4 6-3 3/4 6-4*
- Overleaf page provided to maintain document. completeness.
No changes contained on these pages.
CONTA NMENT SYSTEMS SURVEILLANCE RE UIREMENTS Co tinued b.
If any periodic Type A test fails to meet
.75 L the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. 'If two consecutive Type A tests fail to meet
.75 L~, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet
.75 L at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supple-mental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L 2.
Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the contain-ment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at P~, 12.0 psig.
d.
Type B and C tests shall be conducted at P 12.0 psig, at intervals no greater than 24 months except for tests involving air locks.f e.
Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
f.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
g.
The provisions of Specification 4.0.2 are not applicable.
One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO. 444 162
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION 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
< 0.05 L
at P, 12.0 psig, APPLICABILITY:
NODES I, 2, 3 and 4.
ACTION:
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 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 followinq 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SLRYEILLANCE REQUIREMENTS 4.6.1.3 a.
b.
Each containment air lock shall be demonstrated OPERABLE:
- After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by performing an air leakage test without a simulated pres-sure force on the door by pressurizing the volume between the door seals to 12 psig and verifying a seal leakage rate of no greater than 0.5 L
At least once per 6 months by performing an air leakage test without a simulated pressure force on the door per Specification 4.6.1.3.a; then by performing an air leakage with a simulated pressure force on the do~r--by pressurizing the volume between the door seals to 12 psig and verifying
~ seal leakage ra~e of no greater than 0.0005 L
a'Exempt Yon to Appendix "J" of 10 CFR 50.
D.
C.
COOK UNIT - 2 3/4 6-4