PLA-5553, CFR 50.46 Report - 30-Day Report & Annual Report
| ML023230272 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/12/2002 |
| From: | Jones G Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5553 | |
| Download: ML023230272 (3) | |
Text
G. T. Jones PPL Susquehanna, LLC Vice President - Special Projects 2 North Ninth Street Allentown, PA 18101 a
Tel. 610 774 7602 gtjones@pplweb corn NOV 12 2002-
%T U. S. Nuclear Regulatory Commission Attn.: Document Control Center Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION 10 CFR 50.46 REPORT DAY REPORT AND ANNUAL REPORT Docket Nos. 50-387 PLA-5553 and 50-388
References:
- 1)
Letter from R. G. Byram (PPL) to the U. S. Nuclear Regulatory Commission, "10 CFR 50.46 Report", dated November 12, 2001 (PLA-5390).
- 2)
Letter from J. F. Mallay (FRA-ANP) to Chief, Planning, Program and Management Support Branch of the U.S. Nuclear Regulatory Commission, "2001 - Annual
-Reporting of-Changes and Errors in ECCS Evaluation Models'-
dated February 28, 2002.
This report is being sent in accordance with 10 CFR 50.46 (a)(3)(ii). 10 CFR 50.46 (a)(3)(ii) requires a 30-day report for significant changes (>500 F) to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance. 10 CFR 50.46(a)(3)(ii) also requires annual reporting of changes to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis. Additionally, a proposed schedule is required for reanalysis or identification of other actions necessary to show compliance with 50.46 requirements.
General Electric SAFER/GESTR-LOCA - Annual Report This methodology was applicable to Susquehanna SES Unit 1 until the March 2002 refueling outage, at which time the last of the FRA-ANP 9x9-2 fuel was removed from the core. Unit 2 has not contained 9x9-2 fuel since before the last report (Reference 1).
Subsequent to the submittal of the last annual 10 CFR 50.46 report (Reference 1), two non-zero PCT changes were reported by GE/GNF to PPL Susquehanna, LLC. The specific changes in PCT for Susquehanna SES are provided in Table 1. The total error listed in the last column of Table 1 does not meet the significance threshold for change
(>50 0F) identified in 10 CFR 50.46(a)(3)(i); therefore, a 30-day report is not required.
-A&D/
Absolute
-,Estimated Value of Description of Change/Error APCT (OF)
APCT (OF)
SAFER Core Spray Injection Elevation Error 40 40 SAFER Bulk Water Level Error 5
5 Total 45 45 Framatome-ANP (FRA-ANP) EXEM/BWR LOCA Analysis - 30 Day and Annual Report This methodology is applicable to both Susquehanna SES Unit 1 and Unit 2.
After-the submittal-of the last annual-10-CFR 50.46 report (Reference l), four.non-zero PCT changes were reported to PPL Susquehanna, LLC. The specific changes in PCT for the Susquehanna SES are provided in Table 2. The first listed error was reported on Reference 2. The last three errors were reported to PPL on October 12, 2002. The total error listed in the last column of Table 2 exceeds the significance threshold for change
(>50'F) identified in 10 CFR 50.46(a)(3)(i); therefore, this letter constitutes the required 30-day report required by 10 CFR 50.46 (a)(3)(ii). Concurrently, the annual report requirement is met by this letter.
The cumulative effect of the errors/changes given in Table 2 is to decrease the calculated PCT by approximately 25'F. Thus, the current licensing basis PCT is conservative and no further actions are required.
Document Control Desk PLA-5553 Table 1 GE/GNF SAFER/GESTR LOCA Analysis Changes and/or Errors in Calculated ECCS Performance (Susquehanna Unit 1)
Document Control Desk PLA-5553 Table 2 Framatome-ANP EXEM/BWR LOCA Analysis Changes and/or Errors in Calculated ECCS Performance (Susquehanna Unit 1 and Unit 2)
Absolute Estimated Value of Description of Change/Error APCT (OF)
APCT (OF)
Automation of LOCA Calculation Process
-24 24 Initial Fuel Temperature Reduction in RELAX
-4 4
Steam/Feedwater Flow Rate Corrected in RELAX 13 13 Boundary Condition data write frequency increased in
-10 10 RELAX system calculation.
Total
-25 51 PPL Susquehanna, LLC will continue to track future changes to the evaluation models used in the above LOCA analyses to ensure that the PCT values remain below the
-10 CFR-50.46 -limit; and to ensure-that the 10 CFR-50:46 reporting requirements-are-mfet.
Please contact Mr. C. T. Coddington at (610) 774-4019, if there are any questions concerning this letter.
Sincerely, iones copy: NRC Region I Mr. S. L. Hansell, NRC Sr. Resident Inspector Mr. T. G. Colburn, NRC Sr. Project Manager Mr. R. Janati, DEP/BRP G.