ML20077Q706
| ML20077Q706 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/09/1983 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8309160183 | |
| Download: ML20077Q706 (3) | |
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Mtsconsm Beefhe-co-w 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 September 9, 1983 Mr. H.
R. Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. J.
R. Miller, Chief Operating Reactors Branch 3 Gentlemen:
DOCKET NO. 50-266 STEAM GENERATOR REPLACEMENT POINT BEACH NUCLEAR PLANT, UNIT 1 This letter provides information regarding minor revisions which have been made to the plans and procedures to be used during the course of the Point Beach Unit 1 steam generator replacement project.
Mr. T. G. Colburn of your staff has asked that we advise you of those minor changes if they differ from the plans outlined in the Steam Generator Repair Report (Repair Report), Revision 1, dated March 1983.
In all cases the changes are bounded by the commitments of the Repair Report, NRC Safety Evaluation Report, and Environmental Impact Statement and will result in improved communica-tions, less radiation exposure, and a savings in both time and project cost.
The reporting relationship within the steam generator replacement project organization has been changed to provide direct interface responsibility for the Wisconsin Electric Health Physics Coordinator to report directly'to the Plant Manager, in addition to his direct line responsibility to the Administrator-Special Projects.
This change is consistent with the ALARA objectives as outlined in Section 6.0 of the Repair Report and Section 7.0 of the NRC Safety Evaluation Report. is provided to illustrate this change in the project Health Physics Organization.
Metal reflective insulation rather than the existing blanket insulation will be used on the steam generator shell assemblies and reactor coolant piping, except for the channel heads where the original insulation blankets will be reused.
The upper steam generator steam drum assembly will be placed in the upright position for refurbishment of the primary moisture separator equipment instead of being placed in the inverted position as stated in Section 3.2.6.5 of the Repair Report.
8309160183 830909 PDR ADOCK 05000266 g(
p PDR 1
Mr. H. R. Denton September 9, 1983 A wet layup nozzle will not be added to the upper shell as stated in Section 2.2.3.3 of the Repair Report.
Recirculation during periods of wet layup by nitrogen sparging or by use of the auxiliary feedwater and blowdown systems is also an acceptable method of providing recirculation flow during wet layup.
The licensee is investigating and may use a single pipe cut procedure rather than the double cut procedure of the hot leg and cold leg reactor coolant piping as described in Section 3.2.6.5 of the Repair Report.
Rigid templates of the replacement steam generator reactor coolant nozzles will be used to verify proper fitup of the existing reactor coolant piping prior to placing the replacement steam generators into position.
If proper fitup of the replacement steam generators can be made with the single cut procedure a savings in time and exposure will be realized.
If the proper fit cannot be made with the single cut procedure we will proceed to make the second cuts and replace the removed sections of reactor coolant piping as originally planned.
Should you have any questions regarding the information provided in this letter please contact us.
We will keep you informed of any other revisions to our original plans and procedures.
Very truly yours, C-(A, lv )
i Vice President-Nuclear Power C. W. Fay Attachment Copy to NRC Resident Inspector 1
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