View source for NRC 2005-0139, Day Notice of Software Changes to the Emergency Response Data System (ERDS)

{{Adams
| number = ML053410176
| issue date = 11/18/2005
| title = Day Notice of Software Changes to the Emergency Response Data System (ERDS)
| author name = Koehl D
| author affiliation = Nuclear Management Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000266, 05000301
| license number = DPR-024, DPR-027
| contact person = 
| case reference number = NRC 2005-0139
| document type = Letter type:NRC
| page count = 4
}}

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NMC Committed to NuaearExcellc Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC November 18, 2005                                                                     NRC 2005-0139 10 CFR 50 Appendix E.VI.3.a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 30-Day Notice of Software Changes to the Emergency Response Data System (ERDS)
In accordance with 10 CFR 50, Appendix E.VI.3.a, Nuclear Management Company, LLC (NMC), is submitting the 30-day notice for software changes made that affect the transmitted data points in the Point Beach Nuclear Plant, Units 1 and 2, Emergency Response Data System (ERDS) Data Point Library.
The ERDS datalink software provides NUREG-1394, Revision 1, data from the PBNP computer to the NRC computers during an Alert or higher Emergency classification.
Some values sent by the ERDS datalink software are calculated by the Health Physics (HP) Nuclear Application Program (NAP) software. The HP NAP was modified by Computer Work Order (CWO) 2005-011 to correct an error that will improve RMS trending capabilities on the Plant Process Computer System (PPCS). In addition, enhancements were made to change meteorological (MET) calculations from 15-minute averages calculated once per 15 minutes to 15-minute averages calculated once per minute. This change will therefore improve the timeliness of the MET values that are transmitted to the NRC. The ERDS datalink software on the PPCS was not affected by CWO-2005-01 1.
NMC evaluated these changes in accordance with 10 CFR 50.54(q) and concluded that the changes did not result in a decrease of the effectiveness of the PBNP Emergency Plan, specifically the ability to comply with 10 CFR 50.47(b)(9) and 10 CFR 50 Appendix E.VI.3.a. The 39 datapoints transmitted to the NRC via ERDS remain Intact after this change, accomplishing the same functions with an improved overall performance and reliability of data.
The installation of the PPCS Health Physics NAP software changes was completed on October 19, 2005, for Unit 1. Unit 2 installation is planned for December 2005.
6610 Nuclear Road
* Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321

Document Control Desk Page 2 This letter contains no new co mitments and no revisions to existing commitments.
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC cc:    Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC

NueE Committed to Nuclear Excellern"                                              Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC November 17, 2005                                                                      NRC 2005-0146 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Unit 1 Docket 50-266 License No. DPR-24 Unit 1 Fall 2005 (UI R29) Steam Generator Tube Plugging and Repair Report In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.8(a), "Steam Generator Tube Inspection Report,"
Nuclear Management Company, LLC (NMC), is reporting, in the Enclosure, the number of tubes plugged or repaired during the fall 2005 Unit 1 steam generator eddy current examination.
This letter contains no new commitments and no revisions to existing commitments.
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure cc:      Administrator, Region ll, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW 6590 Nuclear Road
* Two Rivers, Wisconsin 54241 Telephone: 920.755.2321

ENCLOSURE FALL 2005 STEAM GENERATOR TUBE PLUGGING AND REPAIR REPORT POINT BEACH NUCLEAR PLANT UNIT 1 Point Beach Nuclear Plant (PBNP) Technical Specification (TS) 5.6.8(a) requires that:
"After each inservice examination, the number of tubes plugged or repaired in each steam generator shall be reported to the commission as soon as practicable."
No tubes were plugged or repaired during the Unit I fall 2005 refueling outage (U1 R29).
The PBNP Unit 1 steam generators are Westinghouse Model 44F with thermally treated, 7/8-inch outer diameter, Inconel 600 tubing. The PBNP Unit 1 steam generators were replaced in 1983, during refueling outage 11. The replacement steam generators have accumulated approximately 17.7 effective full power years of operation since replacement.
Since the Unit 1 steam generators were replaced, a total of 10 tubes were plugged in the Unit 1 steam generators - four tubes in the "A" steam generator and six tubes in the "B" steam generator. Only six of these ten tubes were plugged since the steam generators were placed in service - one tube in the "A"steam generator and five in the "B" steam generator. There are three tubes in the "A" steam generator and one tube in "B" steam generator that were plugged prior to placing the steam generators in service.
In summary, based on the inspection results, no tubes needed to be repaired. Only the "A"steam generator was inspected. In accordance with Point Beach Technical Specifications and Revision 6 of EPRI Steam Generator Examination Guidelines, the next scheduled inspection of Unit 1 steam generators is planned for Unit 1 refueling outage 30 in 2007.
A report detailing the complete results of the current inspection will be filed as required by TS 5.6.8b.}}