ML20216D008
| ML20216D008 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/06/1998 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20013F498 | List: |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9803160259 | |
| Download: ML20216D008 (4) | |
Text
Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonado Dr. E.
Welch, MN 55089 March 6,1998 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING STATION Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated March 6,1998 Amendment of Technical Specifications to Update the Heatup and Cooldown Rate Curves, incorporate the Use of a Pressure and Temperature Limits Report, and Change the Pressurizer Power Operated Relief Valves Operability Temperature Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant. This request is submitted in accordance with the provisions of 10CFR50.90.
This amendment request proposes the following changes:
1)
Update the Technical Specification heatup and cooldown rate curves and extend their reactor vessel fluence limit from the current 20 Effective Full Power Years (EFPY) to a new value of 35 EFPY.
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2)
Incorporate into Technical Specifications the use of a Pressure and Temperature Limits Report (PTLR).
3)
Change the Power Operated Relief Valves (PORVs) temperature requirement for operabilitv.
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ATTACHMENT CONTAINS PROPRIETARY INFORMATION TO BE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10CFR2.790
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USNRC NORTHERN STATES POWER COMPANY l
M rch 6,1998 l-Page 2 L
l The first proposed change is necessary because the Prairie Island units are approaching the 20 EFPY limit for the current heatup and cooldown rate curves.
l The second proposed change will make the current Prairie Island Technical l
Specifications for pressure / temperature (P/T) limitations consistent with the l
guidance of NUREG-1431, Standard Technical Specifications, Westinghouse l
Plants. The third proposed change will clarify the temperature ranges where the I
PORVs must be operable and where the PORVs may be operable.
l l
Exhibit A contains a description of the proposed changes, the reasons for I
requesting the changes, a supporting safety evaluation, and a significant hazards determination. Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changos. Exhibit C contains the revised Technical Specification pages. Exhibit D contains the proposed Pressure Temperature Limits Report with revised Heatup and Cooldown Rate Curves and Over Pressure Protection System (OPPS) Setpoints to 35 EFPY. Exhibits E and F l
contain reports detailing the determination of the revised P/T Limit curves. Exhibits G and H contain non-proprietary and proprietary versions of the report detailing the l
determination of the OPPS setpoints. Exhibit I contains the Westinghouse authorization letter, CAW-98-1199 and accompanying Affidavit, Proprietary l
I information Notice, and Copyright Notice.
l As Exhibit H contains information proprietary to Westinghouse Electric Company, a division of CBS Corporation (" Westinghouse"), it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on i
which the information may be withheld from public disclosure by the Commission and addresses with specificity the consideration listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
l l
Accordingly, it is respectfully requested that the information which is proprietary to l
Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of Exhibit H or the supporting Westinghouse Affidavit should reference CAW-98-1199 and should be addressed to N.J. Liparulo, Manager of Equipment Design and Regulatory i
Engineering, Westinghouse Electric Company, a division of CBS Corporation
(" Westinghouse"), P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
On January 15,1997 and July 30,1996 Prairie Island made submittals of technical reports for the vessel material surveillance capsules removed for the reactor vessels of Unit 1 (WCAP-14779) and Unit 2 (WCAP-14613). Moreover, these submittals also included Pressurized Thermal Shock Evaluation (PTS) reports for Unit 1
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U::NRC NORTHERN STATES POWER COMPANY M:rch 6,1998 l
Paga 3 (WCAP-14781) and Unit 2 ( WCAP-14638). Due to errors, revised Capsule and PTS reports were then submitted on May 13,1997 for both units. As a consequence of the following two independent events it became necessary to re-perform these analyses and revise the reports:
- 1. The NRC staff requested, by letter dated September 18,1997, additional information regarding Prairie Island Unit 1 "S" Vessel Capsule data and the treatment of the data with regards to the Pressurized Thormal Shock (PTS)
Evaluation. In the response, by letter dated December 5,1997, Prairie Island I
stated that new evaluations were under preparation for the Unit 1 Capsule and PTS reports based upon assessment of the NRC's Request for Additional
]
Information (RAl). The RAI assessment contained conclusions that affected the Unit 2 Capsule and PTS reports as well.
- 2. A November 12,1997 meeting between representatives of NEl, the four NSSS Owners Groups and NRC staff provided information about the review methods used to evaluate licensee GL 92-01 responses. Some of these NRC review methods are new and do not appear in either the regulations or existing regulatory guides. These new methods appear conservative and also affected the methodology of evaluation of Prairie Island's Surveillance Capsules and PTS for both units.
Copies of the most recent revisions of these reports have been submitted under a separate cover letter. This License Amendment Request is based on the most recent revisions of these reports.
NSP requests that the proposed license amendment request be issued prior to the j
expiration of the current curves. Based on current operating conditions, Unit 1 is projected to reach 20 EFPY by May 1,1998. NSP recognizes that the delay in submittal of this request limits the time available for the NRC staff to complete their review of this request. However, the delay was unavoidable because of the events described above.
This submittal makes no new commitments to the NRC. If you have any questions concerning this License Amendment Request, please contact John Stanton at 612-388-1121 x4083.
+m Joel P. Sorensen Plant Manager Prairie Island Nuclear Generating Plant
USNRC NORTHERN STATES POWER COMPANY March 6,1998 Page 4 I
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Regional Administrator-Ill, NRC NRR Project Manager, NRC l
Senior Resident inspector, NRC State of Minnesota, Attn: Kris Sanda J. E Silberg Attachments:
Affidavit Exhibit A-Description of the Proposed Change, Reasons for Requesting the Change, Safety Evaluation, and Significant Hazards Determination.
Exhibit B -
Marked Up Technical Specification Pages Exhibit C -
Revised Technical Specification Pages i
Exhibit D -
Pressure and Temperature Limits Report Exhibit E -
WCAP-14780 Rev 3," Prairie Island Unit 1 Heatup and Cooldown Limit Curves for Normal Operation", February 1998 Exhibit F -
WCAP-14637 Rev 2," Prairie Island Unit 2 Heatup and Cooldown Limit Curves for Normal Operation, February 1998 Exhibit G -
Westinghouse Letter NSP-98-0120 Rev 2, " Prairie Island Units 1 and 2 COMS Setpoint Analysis", February 1998, Non-Proprietary Version Exhibit H -
Westinghouse Letter NSP-98-0120 Rev 2, " Prairie Island Units 1 and 2 COMS Setpoint Analysis", February 1998, Proprietary Version Exhibit I -
Westinghouse Authorization Letter, CAW-98-1199, Accompanying Affidavit, Proprietary Information Notice and Copyright Notice l
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