ML20217G488
| ML20217G488 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/30/1997 |
| From: | Robert Schaaf NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G493 | List: |
| References | |
| NUDOCS 9710100230 | |
| Download: ML20217G488 (6) | |
Text
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UNITED STATES e=
0 NUELEAR REEULATCRY COMMISSIIN P
j' WASHINGTON, D.C. 3046Ho01
/
CONSUMERS ENERGY COMPANY QOCKET NO. 50 255 PALISADES PLANT AEEEDMENT TO FACILITY OPERATING LICENSE Amendment No.171 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) dated January 10,1996, as supplemented Febrary 20,1997, 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 1:
B.
The facltity 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; 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 satis'ied.
9710100230 970930 PDR ADOCK 05000255 Y
2-2.'
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 Lloonse No. DPR 20 is hereby amended to res.d as follows:
The Technical Specifications contained in Appendix A, as revised through Amendment No.177, 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.
3.
This license amendm
, effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert G. Schaaf, Project Manager Project Directorate lil-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: September 30, 1997 e. _
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ATTACHMENT TO LICENSE AMENDMENT NO.177 FACILITY GPERATING LICENSE NO. DPR 20 DOCKET NO. 50 255 Re' vise Appendix A Technical Specifications by removing the pages identified below and inserting the attachea pages. The revised pages are identified by amendr --* number and contain vertical lines i
- Indicating the areas of change.
l i
f REMOVE INS 1fLI 1
l 4-10 4 19 4-20 4 20 4-23 4 23 i
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4.4 Deleted
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4.5 CONTAINMENT TESTS 4.5.1 Intearated Leakaoe Rats Tesig The containment integrated leak late testing shall be performed in accordance with the Containment Leak Rate Testing Program.
4.5.2 Local Leak Detection Tests a.
Iqui (1)
Localleak rate tests, other than Personnel Airlock doors between the seals tests, shall be performed at h 55 psig.
qjp; (2)
Localleak rate tests for checking air lock door seats within 3
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each door opening shall be performed as follows:
(a)
A between the seals test shall be performed on the Personnel Airlock at h 10 psig.
(b)
A full pressure test shall be performed on the Emergency Escape Airlock at 2 55 psig, A seal contact check shall be perfonned on the Emergency Escape Airlock following each full pressure test.
Emergency Escape Airlock door opening, solely for the purpose of strongback removal and performance of the seal contact check, ooes not necessitate additional pressure testing.
(3)
Acceptable methods of testing are halogen gas detection, soap bubble, pressure decay, or equivalent.
(4)
The local leak rate shall be measured for each of the following components:
(a)
Containment penetrations that employ resilient seal gaskets, sealant compounds, or bellows:
(b)
Air lock and equbment door seals.
(c)
Fuel transfer tube.
(d)
Isolation valves on the testable fluid systems' lines penetrating the containment.
(e)
Other containment components which require leak repair in order to meet the acceptance criterion for any integrated leak rate test.
a 4-19 Amendment No. 446,474,177
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-4.5 CONTAINMENT TESTS 4.5.2 Local Leak Detection Tests (continued) b.
Acceotance Criteria (1)
The totalleakage from all penetrations and isolation valves shall not exceed 0.60 L,.
(2)
Th i leakage for a Personnel air lock door seal test shall not ey :eed 0.023 L,.
(3)
/1 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 and conformance to the acceptance criterion 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 l
t 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 shsli 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 sealleakage is greater then 0.023 L, or if the Emergency Escape !.ock door sea' cor; tact check fails to meet its acceptance criterion, 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 c( mpleted within 7 days, the Plant shall be brought to a not shutdown condition within the next six (6) hours and cold shutdown within the following thirty (30) hours.
If a:r lock door sealleakage results in one (1) door causing total containment leakage to exceed 0.60 L,, the door shall be declared inoperable and the remaining operable door shall be immediately locked closed and tested within four (4) hours. As long as the rema;ning door is found to be operable, the provisions of 4.5.2.c(2) w 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 />.
4-20 Amendment No. -146, W4,177
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I 4.5
" CONTAINMENT TESTS Basis (centinutd) 1Second is the more' frequent testing, at the full accident pressure, of'those portions _of the containment envelope that are most likely to develop leaks I
during reactor operation (penetrations and isolation valves) and the low value
-(0.60L ) of the total leakage that is specified as acceptable from penetrations and isolation valves. - Third is the Containment Structural Integrity Surveillance Program which provides assurance that an important part, of the structural integrity of the containment is maintained.
The basis for specification of a total leakage rate of 0.60 L, from penetrations and isolation valves is specified to provide assurance that the integrated leak rate would remain within tha specified limits during the intervals between l Integrated leak rate tests.- This value allows for possible deterioration in the i
intervals between tests.
L The basis for specification of a Personnel airlock door sealleakage rate of 0.023 Lg is to provide assurance that the failure of a single airlock door will not result in the total containment leakage exceeding 0.6 L,. - Due to its i
IL
- design, a seal contact check is used on the Emergency Escape Airlock. The i
seal contact chuk is intended to provide assurance that the Emugency Escape Airlock doors will not leak excessively. The seven (7) day LCO-specified for exceeding the airlock door leakage limit is acceptable since it
- requirs = that the total containment leakage limit is not exceeded.
A reduction in prestressing force and change in physical conditions are
-expected for the prestressing system. Allowances have been made in the_ _
reactor building design for the reduction and changes. The inspection results for each tendan inspected shall be recorded on the forms provided for that purpose and comparison will be made with previous test results and the initial
_ quality control records.
Force timo records will be established and maintained for each 'of the tendon groups, dome, hoop and vertical if the force measured for a tendon is less than the lower bound curve of the force time graph, two adjacent tendons will be tested. If either of the adjacent or more than one of the nriginal sample populatbn falls below the lower bound of the force-time graph, an inves.igation will be conducted before the next scheduled surveillance. The bvestigation shall be made to determine whether the rate of force reduction is indeed occurring for other tendons. If the rate of reduction is confirmed, the investigation shall be extended so as to identify the cause of the rate of force reduction. The extension of the investigation shall determine the needed changes in the surveillance inspection schedule and the criteria and initial planning for corractive action.
If the force measured for a tonos. a any time exceeds the upper bound curve of the band on the force time graph, an investigation shall be made to
'determ:ne the cause.
If the comparison of corrosion conditions, including chemical tests of the corrosion protection material, indicate a large-than expected change in the conditions from the time of installation or last surveillance inspection, an l
-investigation shall be made to detect and correct the causes.
4-23 Amendment No.136,-1-74,177 h