ML20216C568
| ML20216C568 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/08/1998 |
| From: | Robert Schaaf NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216C574 | List: |
| References | |
| NUDOCS 9804140491 | |
| Download: ML20216C568 (5) | |
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UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 30666 4001 o*%
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l CONSUMERS ENERGY COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.179 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Energy Company (the licensee) i dated March 26,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules i
and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the i
Act, and the rules and regulations of the Commission; l
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;
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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; 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 attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
The Tenical Specifications contained in Appendix A, as revised through Amendment No.179, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Consumers Energy Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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9804140491 980408
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PDR ADOCK 05000255
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This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Eb -
Robert G. Schaaf, Project Manager Project Directorate lll-1 Division of Reactor Projects. Ill/IV Omce of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: April 8,1998 I
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4 ATTACHMENT TO LICENSE AMENDMENT NO.179 FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-255 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 verticallines indicating the areas of change.
REMOVE INSERT 340 340 4-20 4-20 I
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3.6 CONTAINMENT SYSTEM Anolicability Applies to the reactor containment building.
Obiective To assure the integrity of the reactor containment building.
Soecifications 3.6.1 Containment Intearitv*
l Containment integrity as defined in Specification 1.0 shall not be a.
violated unless the reactor is in the cold shutdown condition.
9 b.
Containment integrity shall not be violated when the reactor vessel head is removed unless the boron concentration is greater than refueling concentration.
Except for testing one rod at a time, positive reactivity changes c.
shall not be made by CONTROL ROD motion or boron dilution unless the containment integrity is intact.
ACTION:
l With one or more containment isolation valves inoperable (including during performance of valve testing), maintain at least one isolation valve operable in each affected penetration that is open and either:
Restore the inoperable valves to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or a.
b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
Be in at least hot shutdown 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 />.
E8HI The operability of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or i
pressurization of the containment.
- Entry and exit is permissible through a " locked" air lock door to perform repairs on other air lock components.
l 3-40 Amendment No. RS', MT,'
179
4.5 COfLTAINMENT TESTS 4.5.2 Local Leak Detection Tests (r,ontinued) b.
Accentance Criteria (1)
The tutalleakage from all penetrations and isolation valves shall not exceed 0.60 L,.
(2)
The !eakage for a Personnel air lock door seal test shall not exceed 0.023 L,.
(3)
An acceptable Emergency Escape Airlock door seal contact check consists of a verification of continuous contact between the seals and the sealing surfaces, c.
Corrective Action (1)
If at any time it is determined that 0.60 L,is exceeded, repairs shall be initiated immediately, if repairs are not completed end conformance to the acceptance criterirm of 4.5.2.b(1) is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the Plant shall be placed in at least hot shutdown 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 at least 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 /> (2)
If at any time it is determined that total containment leakage exceeds L,, within one hour action shall be initiated to bring the Plant to hot shutdown within the next six (6) hours and cold shutdown within the following thirty (30) hours.
(3)
If the Personnel airlock door seal leakage is greater than 0.023 L., or if the Emergency Escape Lock door seal contact check fails to meet its acceptance critenon, repairs shall be initiated immediately to restore the door seal to the acceptance criteria of specification 4.5.2.b(2) or 4.5.2.b(3).
In the event repairs cannot be completed within 7 days, the Plant shall be brought to a hot shutdown condition within the next six (6) hours and cold shutdown within the following thirty (30) hours, if air lock door seal leekage results in one (1) door causing total containment leakags to exceed 0.60 L., the door shall be decbred inoperable and the remaining operable door shall j
be immediately locked closecfand tested within four (4) hours. As lang as the remaining door is found to be operable, the provisions of 4.5.2.c(2) do not apply. Repairs shall be initiated immediately to establish conformance with specification 4.5.2.b(1). In the event conformance to this specification cannot be established within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the Plant shall be brought to a hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
Entry and exit is permissible through a " locked" air lock door to perform repairs on the affected air lock components.
4-20 mg No.J2fr, JK,