ML18051B075
| ML18051B075 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/28/1984 |
| From: | Bordine T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18051B076 | List: |
| References | |
| NUDOCS 8410020381 | |
| Download: ML18051B075 (3) | |
Text
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.'4 consumers Power company General Offices: 1945 West Parnall Road, 'Jack~n. Ml 49201 * *{517J 713El-0550 September 28, 1984
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST -
STEAM GENERATOR AUGMENTED INSERVICE INSPECTION PROGRAM Attached are three (3) originals and thirty seven (37) conformed copies of a Request for Change to the Palisades Technical Specifications.
The requested change replaces the existing Section 4.14 of the Palisades Technical Specifica-tions with a revised section that reflects the results of our 1983/1984 Steam Generator Evaluation and Repair Program.
NRC Safety Evaluation Report (SER) dated June 11, 1984 also identified the need for revised technical specifica-tions to reflect current inservice inspection techniques.
The enclosed*
incorporates those changes to our Inservice Inspection Program for Steam Generators.
The June 11, -1984 SER also identified our commitment of May 14, 1984 to limit primary to secondary leakage to 0.1 gpm during steady state operation greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
It was our intent that.this limit only apply through cycle 6 and will be lifted pending information of our confirmation regarding flow growth rate during the next inspection.
The SER concluded that our Standing Order No 41, ~ev 1, dated May 30, 1984 was "sufficient and no modifications to your Technical Specifications are necessary".
The limit for periods of startup and major load changes will remain the same as currently specified in section 3.1.5 of the Technical Specifications.
A check in the amount of $150.00 is enclosed as required by 10 CFR 170.21.
Thomas C Berdine Staff Licensing Engineer cc Admini~trator, Region HI, USNRC NRC Resident Inspector - Palisades Attachment
.'." B4too*2oae1 040920.
- PDR :ADO~K.. 05000255 p * *..
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_.* : - PQR OC0984-0011A-NL02
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CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I. CHANGE(s)
Revised Technical Specification pages are attached.
Replace the entire section 4.14 Augmented Inservice Inspection Program for Steam Generators with new section 4.14.
Proposed changes are shown by a vertical line in the right-hand margin.
II. DISCUSSION The above proposed Technical Specification changes are requested to update Section 4.14 to reflect the results of the most recent steam generator inspection.
A report entitled 1983/1984 Steam Generator Evaluation and Repair Program was submitted by letter dated April 19, 1984.
The lnspection program was reviewed by the NRC and found accept-able by Safety Evaluation Report dated June 11, 1984.
Accordingly, these revised Technical Specifications will provide assurance of continued integrity of the steam generator tubes as a result of the comprehensive evaluation and repair program.
BASIS FOR DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS:
This change is intended to define the requirements of the steam generator inservice inspection program.
The changes to the program are consistent with current industry practices and reflect inspection requirements, techniques, and criteria that provide for an improved ability to identify and isolate degraded tubes.
The specification change therefore provides for continued assurance of steam generator tube integrity.
In our review, we have used the guidance of example (ii) of 48FR14864.
It specifies that if a change constitutes an additional limitation, restriction, or control not presently included in the technical specifications then that change can be considered not likely to involve significatn hazards considerations.
Since this proposed change adds additional inspection control, we have determined that it falls within the scope of the example.
Therefore, the operation of the facility in accordance with the above change would not:
- 1) involve a significant increase in the probability or consequences of an accid~nt previously evaluated; or 2) create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in the margin of safety.
MI0984-0011A-NL02
Director, NRR 2
TSCR - S/G ISI September 28, 1984 III. CONCLUSION The Palisades Plant Review Committee has reviewed this Technical Specif i-cation Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no signifi-cant hazards consideration.
This change has also been reviewed under the cognizance of the Nuclear Safety Board.
A copy of this Technical Specifi-cation Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY By R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 28th day of September 1984.
fey, Notary County, Michiga My commission expires November 5, 1986.
SHERRY LYNN DURFEY Notary Public, Jackson County, Miclt.
My Commission Expires Nov. '5, 1986 MI0984-0011A-NL02