TMI-14-074, Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections

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Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections
ML14322A152
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/17/2014
From: Libra R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-14-074
Download: ML14322A152 (7)


Text

Three Mile Island Unit 1 ExetonGeneration, Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 10CFR50.55a November 17, 2014 TMI-14-074 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 (TMI Unit 1)

Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections

References:

1) Letter from R. W. Libra (Exelon Generation Company, LLC) to the U.S. Nuclear Regulatory Commission, 'TMI-1 Steam Generator Tube Inspection Report," dated May 22, 2014
2) Letter from John G. Lamb (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), 'Three Mile Island, Unit 1 - Request for Additional Information Regarding the Fall 2013 Steam Generator Tube Inspections (TAC NO. MF4192)," dated October 20, 2014 By letter dated May 22, 2014, Exelon Generation Company, LLC (Exelon) submitted information summarizing the results of the results of the 2013 steam generator (SG) tube inspections performed at Three Mile Island, Unit 1 (TMI-1) during refueling outage 1 R20 (Reference 1). TMI-1 Technical Specification 6.9.6 requires a report of the inspection results be submitted within 180 days after reactor coolant temperature exceeds 200 0 F.

The results of the examinations are documented in Reference 1.

In the Reference 2 letter, the U.S. Nuclear Regulatory Commission requested information regarding Reference 1. Attached is a response to these questions.

There are no regulatory commitments in this letter.

Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections November 17, 2014 Page 2 If you have any questions concerning this letter, please contact Michael D. Fitzwater at 717-948-8228.

Respectfully, R. W. Libra Site Vice President, Three Mile Island Unit 1 Exelon Generation Co., LLC RWL/mdf cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspection, TMI-1 USNRC Project Manager, TMI-1 R. A. Janati, Bureau of Radiation Protection

ATTACHMENT 1 Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections

Attachment 1 Page 1 of 4 Question 1:

Please discuss the results of any plug inspections. Were all plugs confirmed to be present and free of degradation? Please list the tubes that were plugged in RFO 19 and RFO 20.

Response

During the most recent TMI-1 Steam Generator inspections (T1 R20), a 100% visual examination was performed on all hot and cold leg plugs for both newly installed and previously installed plugs. The newly installed plugs are examined to validate proper location and installation. The previously installed plugs are visually examined for evidence of degradation or leakage and to verify all plugs are present in accordance with Section 6.9.1 of the EPRI Steam Generator Examination Guidelines, Revision 7. All examinations were completed satisfactorily with no degradation or leakage observed.

Tables 1 and 2 include a list of all tubes plugged during Refuel Outage (RFO) 19 (T1 R1 9, Fall 2011) and RFO 20 (T1 R20, Fall 2013). In addition, Table 3 identifies the cumulative plugging in both TMI-1 steam generators relative to the 5% plugging limit.

Table 1: 'A' Steam Generator Plugging List TIR19 SG-A Tube Plugging List Outage Row Tube Tube ID Plugged T1R19 26 36 26-36 T1R19 26 37 26-37 T1R19 114 40 114-40 T1R19 115 40 115-40 TI R20 SG-A Tube Plugging List Outage Row Tube Tube ID Plugged T1 R20 69 132 69-132

Attachment 1 Page 2 of 4 Table 2: 1 Steam Generator Plugging List T1 R19 SG-B3 Tube Plugging List Outage Plugged Row Tube Tube ID Outage Plugged Row Tube Tube ID T1R19 1 4 1-4 T1R19 2 20 2-20 T1R19 1 5 1-5 T1R19 2 21 2-21 T1R19 1 6 1-6 T1R19 2 22 2-22 T1R19 1 7 1-7 T1R19 2 23 2-23 T1R19 1 8 1-8 T1R19 2 24 2-24 T1R19 1 14 1-14 T1R19 2 26 2-26 T1R19 1 15 1-15 T1R19 3 11 3-11 T1R19 1 20 1-20 T1R19 3 27 3-27 T1R19 1 21 1-21 T1R19 3 30 3-30 T1R19 1 22 1-22 T1R19 14 76 14-76 T1R19 2 2 2-2 T1R19 15 79 15-79 T1R19 2 3 2-3 T1R19 16 80 16-80 T1R19 2 6 2-6 T1R19 151 24 151-24 T1R19 2 8 2-8 T1R19 51 102 51-102 T1R19 2 9 2-9 T1R19 116 36 116-36 T1R19 2 17 2-17 T1R19 117 36 117-36 T1R19 2 18 2-18 T1R20 SG-B Tube Plugging List Outage Plugged Row Tube Tube ID Outage Plugged Row Tube Tube ID T1R20 1 9 1-9 T1R20 37 103 37-103 T1R20 1 23 1-23 T1R20 46 117 46-117 T1R20 3 5 3-5 T1R20 48 117 48-117 T1R20 3 6 3-6 T1R20 48 118 48-118 T1R20 3 12 3-12 T1R20 48 119 48-119 T1R20 3 22 3-22 T1R20 49 118 49-118 T1R20 3 24 3-24 T1R20 49 119 49-119 T1R20 3 25 3-25 T1R20 54 121.54-121 T1R20 7 49 7-49 T1R20 94 129 94-129 T1R20 8 52 8-52 T1R20 101 119 101-119 T1R20 9 12 9-12 T1R20 102 117 102-117 T1R20 13 17 13-17 T1R20 103 118 103-118 T1R20 14 67 14-67 T1R20 103 122 103-122 T1R20 14 75 14-75 T1R20 104 118 104-118 T1R20 17 82 17-82 T1R20 107 118 107-118 T1R20 21 85 21-85

Attachment 1 Page 3 of 4 Table 3: TMI-1 Cumulative Steam Generator Plugging SGA Plug History SGB Plug History SGA SGB Total Outage TSP TTW Other Total TSP TTW Other Total Plugged Plugged Plugged PSI 0 0 0 0 0 0 0 0 0 1R19 0 4 0 4 30 3 0 33 37 1R20 1 0 0 1 31 0 0 31 32 Total (Tubes) 1 4 0 j 5 61 3 0 64 69 Total (%) 0.032% 0.410% 0.221%

Limit (%) 5.0% 5.0% 5.0%

Limit (Tubes) 779 779 1558 Notes:

PSI = Pre-service Inspection TTW = Tube-to-Tube Wear TSP Wear = Tube-to-Tube Support Plate Wear Question 2:

Please confirm that there were no tubes pulled during RFO 20.

Response

No tubes were pulled during the TMI-1 RFO 20 (T1 R20, Fall 2013) steam generator inspections.

Question 3:

Please provide the number of effective full-power years that the SGs had operated at the time of the first and second SG inservice inspections.

Response

The TMI-1 Once-Through Steam Generators (OTSGs) are in their first sequential period of operation since replacement. The length of the current inspection period is 144 effective-full power months (EFPMs) per TMI-1 plant Technical Specification 6.19.

The first operating cycle (Cycle 18) of the new steam generators was from January 23, 2010 to October 24, 2011. The total OTSG operating time at T1 R1 9 was 1.719 effective full power years (EFPYs). The second operating cycle (Cycle 19) of the TMI-1 OTSGs was from November 25, 2011 to October 28, 2013 for a length of 1.877 EFPYs.

Therefore, the cumulative operation time of the TMI-1 OTSGs as of the end of the most recent second in-service inspection (T1 R20) is 3.596 EFPYs.

Attachment 1 Page 4 of 4 Question 4:

Please discuss the results of the SG channel head inspections

Response

During the most recent TMI-1 Steam Generator inspections (T1 R20), primary channel head visual inspections were performed in both the upper and lower bowls of both steam generators. These inspections were looking for evidence of cladding degradation in accordance with the recommendations of Westinghouse in Nuclear Safety Advisory Letter (NSAL) 12-1 per the T1 R20 Degradation Assessment. The T1 R20 channel head inspections were completed satisfactorily with no degradation observed.