ML19254F183
| ML19254F183 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/15/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19254F181 | List: |
| References | |
| NUDOCS 7911070271 | |
| Download: ML19254F183 (9) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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.E WASHINGTON, D. C. 20555 a
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CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 52 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated July 26, 1979, as supplenented by letter dated September 11, 1979, 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 confomity with the application, the provisions of the Act, and the rules and reaulations 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 amendmerit 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 apolicable requirements have been satisfied.
1289 07'
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7911070
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment and paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 52, 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 Jr fd.m 4MYe Dennis L. Zieman Chief Operating Reactors Branch #2 Division of Operating Reactors Attachnent:
Changes to the Technical Specifications Date of Issuance:
October 15, 1979 1289 T
ATTACHMENT TO LICENSE AMENDMENT NO. 52 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by renoving the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
Pages 4-68 4-68a
- 4-68b 4 -68c
- 4-68d 4-69**
- There are no changes to these pages. The Technical Specifications provisions have merely been repositioned.
- This page is included only for the purpose of completing the Table Number.
1289 o7'
h.lk Augmented Inservice Insuection Program for Steam Generators Aculicability Applies to the tubes within both steam generators.
Objective To provide assurance of continued integrity of the steam generator tubes over their service lifetime.
Suecification h.14.1 Inspections vill be made at a frequency not less than 12 nor more than 2h calendar months after the previous inspection. Tube inspection requirements vill include inspection of all unplugged tubes with an ECT indication of greater than or equal to 30% in either of the previous two inspection periods.
If inspection of unplugged tubes with an ECT indication of greater than or equal to 30% (which are obstructed by ECT and repair equipment) leads to significant added personnel radiation exposure, alternate tubes may be selected for inspection.
In any event, unplu6ged tubes with ECT indicaticas of greater than or equal to 30$ vill be inspected at a frequency not to exceed two intervals specified in h.1k.1 above.
The conventional, circumferential1y wound ECT pull type probe shall be used to inspect unplugged tubes for which an ECT indication greater than or equal to 30% vas noted in either of the two previous ECT in-spections.
In addition, a random sa=ple of 2% of the tubes in the hot leg and 1% of the tubes in the cold leg of each steam generator vill be inspected using the conventional, circu=ferentially vcund ECT probe.
1289 091
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ECT = Eddy Current Test k-68 Amendment No g, 52
For the purposes of this Technical Specification, " tubes" refers to that portion of the steam generator U-tube from the point of entry on the cold-leg side to the top supporb of the cold leg, or from the point of entry on the hot-leg side completely around the U-bend to the top support of the cold leg.
h.lk.2 Inspection techniques, capable of detecting flaws in the presence of tube dents, shall be used to inspect ~ all accessible tube / tube support plate intersections where an ECT indication was present during the last inspection which was greater than or equal to h5% but cannot be interpreted in the current inspection due to the presence of dents.
In addition, the following shall apply for areas which could not be inspected due to dents in the last inspection. Additional intersections shall be selected for special examination to assure that all accessible crevious ECT indications are inspected when their last recorded ECT reading plus the approp-riate operating allowance from Table k lk.1 exceeds the Maximum Allowable Degradation specified in Table k.lk.2.
If such indications, regardless of accessibility, are not inspected, the repair criteris of h.lk.3 shall apply for sleeving or plugging.
k.lb.3 When inspection reveals that the tube degradation plus an NRC-approved appropriate operating allowance (for future degradation) is greater than the max 1=um allevable degradation specified in Table h.1k.2, the tube shall be declared to be defective and tube plugging or sleeving shall be perforned.
L-68a 1289 oo' Amendment No. 34f, 52
In determining that a defect exists at a given tube location, indications from several ECT's may be averaged during a given inspection, but such averaging shall be based on not less than three ECT's.
h.lk.h Operating allovances for future degradation are tabulated in Table h.14.1.
h.1k.5 Sleeves vill be installed such that, considering the axial location tolerances, svaging does not take place in an area of known degradation. A base line ECT inspection of all newly installed sleeves shall be performed.
In addition, all previously installed sleeves shall be inspected or plugged during subsequent steam generator tube inspections.
h.lk.6 A steam generator inspection report shall be submitted to the IIRC within 30 days of ec=pletion of the inspection and any re-quired repairs.
Basis _
Consumers Power has concluded that the change from coordinated phosphate to volatile chemistry control for the secondary side of the steam gener-ators has reduced the presi.ous corrotion -at, to etaentially zero.
Palisades has not observed any tube leakage since June 197h.
Furthermore,
=ean vastage increase has been essentially zero since February 1976. The continuing inspection program provides for verd.fying that the corrosion has been arrested, i
1289 e"'
h-68b AmendmentNo.)4,52
The inspection program is also consistent with current industry practices and includes appropriate measures to identify additional degradation of the Palisades steam generators. The operating allowance vill be and the repair criter.s has been developed based on comparative results between steam generator inspections with consideration giver. to defect type, location, past corrosion rate observed, etc.
Calculations have been perfor=ed to demonstrate that a tube unifomly thinned to 36% of its original nominal vall thickness (6h% degradation) can withstand a differential pressure of 1380 psi.
Likewise, a sleeved tube can wit l.tand the saue different,ial pressure when the limits in Table h.lk.2 are observed. Ccmbustion Engineering, Inc Report No CEN-59(P) " Palisades Steam Generator Tube Repair by Sleeving," dateT August 26, 1977, contains the analytical and test results of tube sleeving.
In dented regions when the presence of a tube support plate tends to cause interference in the eddy current signals, the standard ECT inspection technique vill not be able to detect flaws embedded in these regions.
However, there are several advanced inspection probes under develop =ent unich have been shown to be effective in detecting flaws by screening out the interference signals caused by the presence of the tube support plates or den %.
1209 3,
h-68e Amendment No, pf, 52
TABLE h.lk.1 Operating Allowances ECT Indications Other Than Multiple Multiple Affected Tubes ECT Indications ECT Indications Tubes Inspected During 1978(1;and Future ECTs 6%
35,,
Tubes Last Inspected During 1976 ECT 10%
- NA Tubes Last Inspected During 1975 ECT 20%
- NA
- Not Applicable (1)
If the mean vastage increase over the p< died since the previous steert generator inspection is less than +1 percent (essentially no vastage) the operating allowances listed above shall be applicable.
If the
=ean vastage increase is greater than or equal to +1 percent, new operating allowances shall be subnitted to NRC for approval prior to return to operation.
1289 c'
h-68d Amendmentt'o.)g 52
TABLE h.1h.2 Mavimm Allovable Degradation Location Mav4== Allovable Degradation Unsleeved Sections Degradation = 6k%
Sleeved Section Region 1(
Sleeve degradation = 3k% and tube degradation exceeding the "av4m m allotable degradation for an unsleeved section.(4)
Region 2(
Either (a) sleeve degradation = 25% when tube degradation in Region 1 exceeds the =azinum allowable de6radation for an unsleeved section; y (b) tube degradation to Region 2 equal to the mavimum allowab e degradation for an unsleeved tube. ( 4 Region 3(3)
Tube degradation equal to the navimum allovable degradation for an unsleeved section.
Footnotes:
The undefor=ed region of the tube / sleeve assembly containing the original imperfection requiring sleeving-(
The region containing the expansion, joint. Specifically, the region of the tube / sleeve assembly bounded by lines approxi=ately 1/k inch and 2 inches inboard from the sleeve ends.
(3)The region of the tube / sleeve an'sembly containing approximately 1/4 inch of each end of the assembly.
(h) Degradation occurring in the parent tube at any location in a Region and degradation occurring in the sleeve at any location in the same Region that exceeds the applicable maximum allowable degradation vill require tube plugging.
(5) Subtracted fron these Maximum Allowable Degradation values shall be an appropriate allowance for future degradation as approved by the NRC as identified in h.lk.3 h-69 lgg n-s AmendmentNo,g,52