ML20203F049
| ML20203F049 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/15/1986 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20203F055 | List: |
| References | |
| TAC-62137, TAC-62138, NUDOCS 8607300087 | |
| Download: ML20203F049 (2) | |
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-o Northern States Power Ccmpany 414 Nicollet Mall Minneapolis. Minnesota 55401 Telephone (612) 330 5500 July 15, 1986 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND h"JCLEAR GENEPATINC PIANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated July 15, 1986 Heatup/Cooldown Curves and Miscellaneous Changes Attached are three originals and 37 conformed copies of a request for a change to the Technical Specifications, Appendix A, of Operating Licenses DPR-42 and DPR-60. This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.
A check is attached in the amount of $150.00 in accordance with the requirements of 10 CFR Part 170 for the amendment application fee.
The existing Prairie Island reactor coolant system heatup and cooldown only valid for ten effective full power years (EFPY) of plant curves are operation.
Prairie Island Unit 1 (lead unit) is expected to reach 10 EFPY by early October, 1986. This license amendment request includes proposed heatup and cooldown curves valid to 15 EFPY and other administrative changes to the Heatup and Cooldown Technical Specifications and associated bases.
This license amendment request also proposes changes in the following areas: 1) Radiation Environmental Monitoring Program;
- 2) Design Featurer, Section 5;
- 3) Security Plan Implementing Procedures Review; and
- 4) Administrative Controls, Section 6.
Exhibit A describes the proposed changes, reason for the changes and significant hazards considerations evaluation.
Exhibit B contains the proposed changes marked up on the existing Technical Specification pages.
Exhibit C contains the revised Technical Specification pages.
t 8607300097 860715 PDR ADOCK 05000282 P
PDR g il gJ 4e= ve e
a Director NRR NhhM July 15, 1986 Page 2 The Pressurized Thermal Shock (PTS) Rule, 10 CFR Part 50, Section 50.61, requires that the projected assessment of the RTPTS must be updated whenever changes in core loadings, surveillance measurements or other information indicate a significant change in the projected values.
In that regard, the NRC Pressurized Thermal Shock Safety Evaluation Reports for Prairie Island Units 1 and 2, dated June 23, 1986, requested that a re-evaluation of the RTPTS and comparison of the predicted value be submitted with any future pressure-temperature submittals which are required by 10 CFR 50, Appendix G.
This re-assessment of the RT 18 PTS attached as Exhibit E.
Please contact us if you have any questions concerning this License Amendment Request or if additional information is required to supplement it.
Because the existing heatup and cooldown curves are only valid until early October, NRC Staff review and approval of these changes is requested prior to October 1, 1986.
d Mm David Musolf Managet - Nuclear Support l Services DMM/EFE/efe c: Regicnal Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn:
F V Ferman G Charnoff i
Attachments l
Exhibit A Evaluation of Proposed Changes to the Technical Specifications Exhibit B Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C Revised Technical Specification Pages Exhibit D Draft Revised Page From Offsite Dose Calculation Manual Exhibit E Summary of RTPTS Re-evaluation
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