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| | issue date = 09/18/2012 | | | issue date = 09/18/2012 |
| | title = Vibration Data Report | | | title = Vibration Data Report |
| | author name = Ford B S | | | author name = Ford B |
| | author affiliation = Entergy Operations, Inc | | | author affiliation = Entergy Operations, Inc |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:GNRO-201 2/00 113 September 1 8 , 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:Entergy Operations, Inc. |
| | 1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368-5516 GNRO-2012/00113 September 18, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Vibration Data Report Grand Gulf Nuclear Station, Unit 1 Docket No. 50 | | Vibration Data Report Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 |
| -416 License No. | |
| NPF-29 | |
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| ==REFERENCE:== | | ==REFERENCE:== |
| | Entergy Operations, Inc. letter to the NRC (GNRO-2012/00079), Summary Report of Replacement Steam Dryer Data - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession |
| | #ML12221A198) |
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| Entergy Operations, Inc. letter to the NRC (GNRO | | ==Dear Sir or Madam:== |
| -2012/00079), Summary Report of Replacement Steam Dryer Data
| | |
| - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198)
| | In the referenced letter, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in the attachment to this letter. |
| | If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756. |
| | This letter contains no new regulatory commitments. |
| | Sincerely, BSF/ghd |
| | |
| | ==Attachment:== |
| | Vibration Data for the Main Steam Line Piping and Safety Relief Valves - |
| | 4408 MWt |
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|
| ==Dear Sir or Madam:==
| | GNRO- 2012/00113 Page 2 of 2 cc: Mr. Elmo E. Collins, Jr. |
| | Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2) |
| | ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 |
| | |
| | ATTACHMENT GRAND GULF NUCLEAR STATION GNRO-2012/00113 VIBRATION DATA FOR THE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES - |
| | 4408 MWt |
| | |
| | Attachment to GNRO-2012/00113 Page 1 of 8 VIBRATION DATA FOR THE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES - |
| | 4408 MWt In a letter to the NRC staff1, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in Sections I and II, below. |
| | Node 1008 on MSL-A has reported data that contained intermittent high-amplitude spikes. |
| | These types of spikes were not seen in the corresponding data for the other valves at the same valve location (top) nor were they seen in the data at any of the nodes. For these reasons, the data at this location were deemed unusable. |
| | Node 3010 on MSL-C has also reported data that indicates a failure in the mounting system. |
| | Two sets of data were retrieved at the 105% power plateau; one was taken directly after the plateau was reached and a subsequent set was taken before the ascension to the 107.5% |
| | plateau. While the plant data indicated a small increase in main steam flow, there was a markedly higher increase in the X (longitudinal), Y (vertical), and Z (lateral) accelerations at Node 3010 on MSL-C. This magnitude increase for Node 3010 is in excess of 2 standard deviations above the response noted for the other 15 SRVs. PSD comparisons were made to the MSL response at SRV monitoring points on two valves at Nodes 1008 and 3010 on MSL-C. The PSD comparison for X, Y, and Z responses shows a large change in frequency response through much of the 1 - 250-Hz range at Node 3010 and only a small change in magnitude at the Node 1008 location. The three accelerometers at Node 3010 are mounted on the same block and strapped to the valve actuator. It is expected that the mounting straps have loosened and the sensor has shifted. The measured response is most likely being affected by the response of the accelerometer mounting system; therefore, this measured response is unusable. |
| | I. Main Steam Line (MSL) Piping Vibration Data and Acceptance Limits Table 1, below, contains the results from the MSL piping vibration testing performed as part of the GGNS Extended Power Uprate (EPU) Power Ascension Test Plan (PATP) at ~4408 MWt. |
| | The measured accelerations were taken in the major axes for each of the nodes. A band pass filter (RMS) for the test data was applied based on: |
| | * Lower Limit - Capturing frequencies below the lowest piping frequency which corresponds to the highest piping stresses. Generally, this number is higher than 1 Hz, which typically contains voltage drift and DC signals that need to be removed. |
| | 1 Entergy Operations, Inc. letter to the NRC (GNRO-2012/00079), Summary Report of Replacement Steam Dryer Data - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198) |
| | |
| | Attachment to GNRO-2012/00113 Page 2 of 8 |
| | * Upper Limit - The upper limit frequency should be sufficiently high so there is no significant modal participation on the maximum piping stresses. Also, the intent is to remove the high frequency noise, generally above 100 Hz. |
| | The acceptance criteria are based on applying a constant 1-g acceleration spectrum to the piping model and determining the maximum stress. The maximum stress was compared with the OM criteria alternating stress allowable per ASME OM-S/G-1997, Standards and Guides for Operation and Maintenance of Nuclear Power Plants. The resulting ratio was used to modify the output accelerations at the location for each of the test points. |
| | Table 1 ACCEL. |
| | PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 / |
| | DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g) |
| | MARGIN (%) |
| | Piping associated with B21-F041A Non-Operable X 1X N/A 0.720 / 1.440 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A Non-Operable Y 1Y N/A 0.160 / 0.320 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A Non-Operable Z 1Z N/A 0.671 / 1.341 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A X 2X 0.363 0.447 / 0.893 18.8 / 59.4 Acceptable (Actuator) |
| | MSL-A, Node 1010 Piping associated with B21-F041A Y 2Y 0.157 0.231 / 0.461 32.0 / 65.9 Acceptable (Actuator) |
| | MSL-A, Node 1010 Piping associated with B21-F041A Z 2Z 0.212 0.434 / 0.868 51.2 / 75.6 Acceptable (Actuator) |
| | MSL-A, Node 1010 Piping associated with B21-F051A X 3X 0.200 0.349 / 0.697 42.7 / 71.3 Acceptable (Actuator) |
| | MSL-A, Node 2010 Piping associated with B21-F051A Y 3Y 0.193 0.224 / 0.447 13.8 / 56.8 Acceptable (Actuator) |
| | MSL-A, Node 2010 |
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|
| In the referenced letter , Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program.
| | Attachment to GNRO-2012/00113 Page 3 of 8 ACCEL. |
| The vibrati on data collected at or near the current licensed thermal power of 4408 MWt (1 13% of 3898 MWt, the previous licensed thermal power
| | PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 / |
| ) is provided in the attachment to this letter. | | DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g) |
| If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756. This letter contains no new regulatory commitments
| | MARGIN (%) |
| . Sincerely, BSF/ghd Attachment | | Piping associated with B21-F051A Z 3Z 0.248 0.389 / 0.778 36.2 / 68.1 Acceptable (Actuator) |
| : Vibration Data for the Main Steam Line Piping and Safety Relief Valves
| | MSL-A, Node 2010 Piping associated with B21-F047A X 4X 0.171 0.420 / 0.840 59.3 / 79.6 Acceptable (Actuator) |
| - 4 408 MW t Entergy Operations, Inc. | | MSL-A, Node 4010 Piping associated with B21-F047A Y 4Y 0.031 0.310 / 0.619 90.0 / 95.0 Acceptable (Actuator) |
| 1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368
| | MSL-A, Node 4010 Piping associated with B21-F047A Z 4Z 0.217 0.474 / 0.948 54.2 / 77.1 Acceptable (Actuator) |
| -5516 GNRO- 2012/00113 Page 2 of 2 cc: Mr. Elmo E. Collins, Jr. | | MSL-A ,Node 4010 Piping associated with B21-F051B X 5X 0.004 0.701 / 1.402 99.4 / 99.7 Acceptable (Top of Valve) |
| Regional Administrator, Region I V U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011
| | MSL-B, Node 1008 Piping associated with B21-F051B Y 5Y 0.098 0.185 / 0.370 47.0 / 73.5 Acceptable (Top of Valve) |
| -4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2) | | MSL-B, Node 1008 Piping associated with B21-F051B Z 5Z 0.706 0.756 / 1.512 6.6 / 53.3 Acceptable (Top of Valve) |
| ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852
| | MSL-B, Node 1008 Piping associated with B21-F051F X 6X 0.040 0.389 / 0.778 89.7 / 94.9 Acceptable (Actuator) |
| -2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215 | | MSL-B, Node 3010 Piping associated with B21-F051F Y 6Y 0.093 0.212 / 0.424 56.1 / 78.1 Acceptable (Actuator) |
| -1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 | | MSL-B, Node 3010 Piping associated with B21-F051F Z 6Z 0.166 0.436 / 0.872 61.9 / 81.0 Acceptable (Actuator) |
| | MSL-B, Node 3010 Piping associated with B21-F041F X 7X 0.254 0.645 / 1.290 60.6 / 80.3 Acceptable (Top of Valve) |
| | MSL-B, Node 4008 |
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| ATTACHMENT GRAND GULF NUCLEAR STATION GNRO-2012/00 113 VIBRATION DATA FOR T HE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES - 4 408 MW t Attachment t o GNRO-2012/00113 Page 1 of 8 VIBRATION DATA FOR T HE MAIN STEAM LINE PIPI NG AND SAFETY RELIEF VALVES - 4 408 MW t In a letter to the NRC staff 1, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in Sections I and II, below.
| | Attachment to GNRO-2012/00113 Page 4 of 8 ACCEL. |
| Node 1008 o n MSL-A has reported data that contained intermittent high
| | PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 / |
| -amplitude spikes. These types of spikes were not seen in the corresponding data for the other valves at the same valve location (top) nor were they seen in the data at any of the nodes. For these reasons, the data at this location were deemed unusable. | | DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g) |
| Node 3010 o n MSL-C has also reported data that indicates a failure in the mounting system. Two sets of data were retrieved at the 105% power plateau | | MARGIN (%) |
| ; one was taken directly after the plateau was reached and a subsequent set was taken before the ascension to the 107
| | Piping associated with B21-F041F Y 7Y 0.120 0.181 / 0.362 33.7 / 66.9 Acceptable (Top of Valve) |
| .5% plateau. While the plant data indicated a small increase in main steam flow, there was a markedly higher increase in the X (longitudinal), Y (vertical), and Z (lateral) acceleration s at Node 3010 on M SL-C. This magnitude increase for Node 3010 is in excess of 2 standard deviations above the response noted for the other 15 SRVs. PSD comparisons were made to the MSL response at SRV monitoring points on two valves at Nodes 1008 and 3010 on MSL-C. The PSD comparison for X, Y, and Z response s shows a large change in frequency response through much of the 1 | | MSL-B, Node 4008 Piping associated with B21-F041F Z 7Z 0.572 0.800 / 1.600 28.5 / 64.3 Acceptable (Top of Valve) |
| - 250-Hz range at Node 3010 and only a small change in magnitude at the Node 1008 location. The three accelerometers at Node 3010 are mounted on the same block and strapped to the valve actuator.
| | MSL-B, Node 4008 Piping associated with B21-F041K X 8X 0.176 0.663 / 1.326 73.5 / 86.7 Acceptable (Top of Valve) |
| It is expected that the mounting straps have loosened and the sensor has shifted.
| | MSL-B, Node 6008 Piping associated with B21-F041K Y 8Y 0.155 0.229 / 0.457 32.3 / 66.1 Acceptable (Top of Valve) |
| The measured response is most likely being affected by the response of the accelerometer mounting system; therefore, this measured response is unusable.
| | MSL-B, Node 6008 Piping associated with B21-F041K Z 8Z 0.505 0.677 / 1.353 25.4 / 62.7 Acceptable (Top of Valve) |
| I. Main Steam Line (MSL) Piping Vibration Data and Acceptance Limits Table 1, below, contains the results from the MSL piping vibration testing performed as part of the GGNS Extended Power Uprate (E PU) Power Ascension Test Plan (PAT P) at ~4 408 MWt. The measured accelerations were taken in the major axes for each of the nodes. A band pass filter (RMS) for the test data was applied based on:
| | MSL-B, Node 6008 Piping associated with B21-F041C X 9X 0.218 0.701 / 1.402 68.9 / 84.5 Acceptable (Top of Valve) |
| Lower Limit
| | MSL-C, Node 1008 Piping associated with B21-F041C Y 9Y 0.127 0.185 / 0.370 31.4 / 65.7 Acceptable (Top of Valve) |
| - Capturing frequencies below the lowest piping frequency which corresponds to the highest piping stresses. | | MSL-C, Node 1008 Piping associated with B21-F041C Z 9Z 0.156 0.756 / 1.512 79.4 / 89.7 Acceptable (Top of Valve) |
| Generally , this number is higher than 1 Hz, which typically contains voltage drift and DC signals that need to be removed.
| | MSL-C, Node 1008 Piping associated with B21-F051C Non-Operable X 10AX N/A 0.389 / 0.778 N/A (Actuator) Sensor MSL-C, Node 3010 Piping associated with B21-F051C Non-Operable Y 10AY N/A 0.212 / 0.424 N/A (Actuator) Sensor MSL-C, Node 3010 Piping associated with B21-F051C Non-Operable Z 10AZ N/A 0.436 / 0.872 N/A (Actuator) Sensor MSL-C, Node 3010 |
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| 1 Entergy Operations, Inc. letter to the NRC (GNRO | | Attachment to GNRO-2012/00113 Page 5 of 8 ACCEL. |
| -2012/00079), Summary Report of Replacement Steam Dryer Data | | PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 / |
| - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198) | | DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g) |
| | MARGIN (%) |
| | Piping associated with B21-F047G X 10BX 0.565 0.645 / 1.290 12.4 / 56.2 Acceptable (Top of Valve) |
| | MSL-C, Node 4008 Piping associated with B21-F047G Y 10BY 0.046 0.181 / 0.362 74.6 / 87.3 Acceptable (Top of Valve) |
| | MSL-C, Node 4008 Piping associated with B21-F047G Z 10BZ 0.724 0.800 / 1.600 9.5 / 54.8 Acceptable (Top of Valve) |
| | MSL-C, Node 4008 Piping associated with B21-F047L X 10CX 0.540 0.663 / 1.326 18.6 / 59.3 Acceptable (Top of Valve) |
| | MSL-C, Node 6008 Piping associated with B21-F047L Y 10CY 0.221 0.229 / 0.457 3.5 / 51.6 Acceptable (Top of Valve) |
| | MSL-C, Node 6008 Piping associated with B21-F047L Z 10CZ 0.408 0.677 / 1.353 39.7 / 69.8 Acceptable (Top of Valve) |
| | MSL-C, Node 6008 Piping associated with B21-F047D X 10DX 0.304 0.720 / 1.440 57.8 / 78.9 Acceptable (Top of Valve) |
| | MSL-D, Node 1008 Piping associated with B21-F047D Y 10DY 0.143 0.160 / 0.320 10.6 / 55.3 Acceptable (Top of Valve) |
| | MSL-D, Node 1008 Piping associated with B21-F047D Z 10DZ 0.349 0.671 / 1.341 48.0 / 74.0 Acceptable (Top of Valve) |
| | MSL-D, Node 1008 Piping associated with B21-F047D X 10EX 0.432 0.447 / 0.893 3.4 / 51.6 Acceptable (Actuator) |
| | MSL-D, Node 1010 Piping associated with B21-F047D Y 10EY 0.176 0.231 / 0.461 23.8 / 61.8 Acceptable (Actuator) |
| | MSL-D, Node 1010 |
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| Attachment t o GNRO-2012/00113 Page 2 of 8 Upper Limit | | Attachment to GNRO-2012/00113 Page 6 of 8 ACCEL. |
| - The upper limit frequency should be sufficiently high so there is no significant modal participation on the maximum piping stresses.
| | PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 / |
| Also , the intent is to remove the high frequency noise, generally above 100 Hz.
| | DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g) |
| The acceptance criteria are based on applying a constant 1
| | MARGIN (%) |
| -g acceleration spectrum to the piping model and determining the maximum stress.
| | Piping associated with B21-F047D Z 10EZ 0.132 0.434 / 0.868 69.6 / 84.8 Acceptable (Actuator) |
| The maximum stress was compared with the OM criteria alternating stress allowable per ASME OM
| | MSL-D, Node 1010 Piping associated with B21-F014D X 10FX 0.297 0.349 / 0.697 14.9 / 57.4 Acceptable (Actuator) |
| -S/G-1997, Standards and Guides for Operation and Maintenance of Nuclear Power Plants. The resulting ratio was used to modify the output accelerations at the location for each of the test points.
| | MSL-D, Node 2010 Piping associated with B21-F014D Y 10FY 0.186 0.224 / 0.447 17.0 / 58.4 Acceptable (Actuator) |
| Table 1 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
| | MSL-D, Node 2010 Piping associated with B21-F014D Z 10FZ 0.255 0.389 / 0.778 34.4 / 67.2 Acceptable (Actuator) |
| ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
| | MSL-D, Node 2010 Piping associated with B21-F051D X 10GX 0.247 0.420 / 0.840 41.2 / 70.6 Acceptable (Actuator) |
| NOTES Piping associated with B21-F041A (Top of Valve)
| | MSL-D, Node 4010 Piping associated with B21-F051D Y 10GY 0.142 0.310 / 0.619 54.2 / 77.1 Acceptable (Actuator) |
| MSL-A, Node 1008 X 1X N/A 0.720 / 1.440 N/A Non-Operable Sensor Piping associated with B21-F041A (Top of Valve) | | MSL-D, Node 4010 Piping associated with B21-F051D Z 10GZ 0.450 0.474 / 0.948 5.1 / 52.5 Acceptable (Actuator) |
| MSL-A, Node 1008 Y 1Y N/A 0.160 / 0.320 N/A Non-Operable Sensor Piping associated with B21-F041A (Top of Valve) | | MSL-D, Node 4010 Piping associated with Pipe Support N11G001H14 X 15X 0.092 0.213 / 0.426 56.8 / 78.4 Acceptable Turbine Bldg. |
| MSL-A, Node 1008 Z 1Z N/A 0.671 / 1.341 N/A Non-Operable Sensor Piping associated with B21-F041A (Actuator) | | MSL-D, Node 412 II. Main Steam Safety Relief Valve (SRV) Vibration Data and Acceptance Limits Table 2, below, contains the results from the SRV vibration testing performed as part of the GGNS EPU PATP at ~4408 MWt. |
| MSL-A, Node 1010 X 2X 0.363 0.447 / 0.893 18.8 / 59.4 Acceptable Piping associated with B21-F041A (Actuator) | | The measured acceleration (ACC. ACTUAL) represents the peak acceleration reported by the tri-axial accelerometer in that particular direction for the individual node. This peak was gathered from the time-history data after band-pass filtering (2 - 250 Hz) and DC-offset removal. |
| MSL-A, Node 1010 Y 2Y 0.157 0.231 / 0.461 32.0 / 65.9 Acceptable Piping associated with B21-F041A (Actuator) | |
| MSL-A, Node 1010 Z 2Z 0.212 0.434 / 0.868 51.2 / 75.6 Acceptable Piping associated with B21-F051A (Actuator) | |
| MSL-A, Node 2010 X 3X 0.200 0.349 / 0.697 42.7 / 71.3 Acceptable Piping associated with B21-F051A (Actuator) | |
| MSL-A, Node 2010 Y 3Y 0.193 0.224 / 0.447 13.8 / 56.8 Acceptable | |
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| Attachment t o GNRO-2012/00113 Page 3 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g) | | Attachment to GNRO-2012/00113 Page 7 of 8 The methodology for developing the acceleration limits (ACC. LIMIT) below was through analytical methods involving ASME NB-3500 calculations as well as structural sub-models of individual components. For both the top-of-valve and actuator locations, the horizontal limits (X and Z) seen below are a resultant limit calculated through the square root sum of the squares (SRSS) method. The vertical limit (Y) is an individual limit that is not used to calculate any resultant limits. |
| ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
| | Table 2 COMP./PIPING MONITOR. PT. MEASURED ACCEL LIMIT MARGIN DESCRIPTION / NOTES LOC./DIR. NUM. ACCEL (g) (g) (%) |
| NOTES Piping associated with B21-F051A (Actuator)
| | SEGMENT B21-F041A X Non-Op Sensor Top of Valve Y 1 N/A N/A N/A Non-Op Sensor MSL-A, Node 1008 Z Non-Op Sensor B21-F041A X 1.20 3.78 68.28 Actuator Y 2 1.09 3.77 71.04 Acceptable MSL-A, Node 1010 Z 1.20 3.78 68.28 B21-F051A X 1.19 3.78 68.47 Actuator Y 3 1.11 3.77 70.49 Acceptable MSL-A, Node 2010 Z 1.19 3.78 68.47 B21-F047A X 0.70 3.78 81.58 Actuator Y 4 0.01 3.77 99.76 Acceptable MSL-A, Node 4010 Z 0.70 3.78 81.58 B21-F051B X 1.32 6.62 80.05 Top of Valve Y 5 2.08 3.42 39.27 Acceptable MSL-B, Node 1008 Z 1.32 6.62 80.05 B21-F051F X 1.57 3.78 58.50 Actuator Y 6 1.20 3.77 68.15 Acceptable MSL-B, Node 3010 Z 1.57 3.78 58.50 B21-F041F X 5.01 6.62 24.29 Top of Valve Y 7 0.12 3.42 96.57 Acceptable MSL-B, Node 4008 Z 5.01 6.62 24.29 B21-F041K X 1.40 6.62 78.80 Top of Valve Y 8 0.72 3.42 79.02 Acceptable MSL-B, Node 6008 Z 1.40 6.62 78.80 B21-F041C X 3.50 6.62 47.18 Top of Valve Y 9 3.27 3.42 4.31 Acceptable MSL-C, Node 1008 Z 3.50 6.62 47.18 B21-F051C X Non-Op Sensor Actuator Y 10a N/A N/A N/A Non-Op Sensor MSL-C, Node 3010 Z Non-Op Sensor B21-F047G X 2.93 6.62 55.71 Top of Valve Y 10b 0.08 3.42 97.81 Acceptable MSL-C, Node 4008 Z 2.93 6.62 55.71 |
| MSL-A, Node 2010 Z 3Z 0.248 0.389 / 0.778 36.2 / 68.1 Acceptable Piping associated with B21-F047A (Actuator) | |
| MSL-A, Node 4010 X 4X 0.171 0.420 / 0.8 40 59.3 / 79.6 Acceptable Piping associated with B21-F047A (Actuator) | |
| MSL-A, Node 4010 Y 4Y 0.031 0.310 / 0.619 90.0 / 95.0 Acceptable Piping associated with B21-F047A (Actuator) | |
| MSL-A ,Node 4010 Z 4Z 0.217 0.474 / 0.948 54.2 / 77.1 Acceptable Piping associated with B21-F051B (Top of Valve) | |
| MSL-B, Node 1008 X 5X 0.004 0.701 / 1.402 99.4 / 99.7 Acceptable Piping associated with B21-F051B (Top of Valve)
| |
| MSL-B, Node 1008 Y 5Y 0.098 0.185 / 0.370 47.0 / 73.5 Acceptable Piping associated with B21-F051B (Top of Valve) MSL-B, Node 1008 Z 5Z 0.706 0.756 / 1.512 6.6 / 53.3 Acceptable Piping associated with B21-F051F (Actuator)
| |
| MSL-B, Node 3010 X 6X 0.040 0.389 / 0.778 89.7 / 94.9 Acceptable Piping associated with B21-F051F (Actuator)
| |
| MSL-B, Node 3010 Y 6Y 0.09 3 0.212 / 0.424 56.1 / 78.1 Acceptable Piping associated with B21-F051F (Actuator)
| |
| MSL-B, Node 3010 Z 6Z 0.166 0.436 / 0.872 61.9 / 81.0 Acceptable Piping associated with B21-F041F (Top of Valve) | |
| MSL-B, Node 4008 X 7X 0.254 0.645 / 1.290 60.6 / 80.3 Acceptable Attachment t o GNRO-2012/00113 Page 4 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
| |
| ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
| |
| NOTES Piping associated with B21-F041F (Top of Valve)
| |
| MSL-B, Node 4008 Y 7Y 0.120 0.181 / 0.362 33.7 / 66.9 Acceptable Piping associated with B21-F041F (Top of Valve)
| |
| MSL-B, Node 4008 Z 7Z 0.572 0.800 / 1.600 28.5 / 64.3 Acceptable Piping associated wi th B21-F041K (Top of Valve) | |
| MSL-B, Node 6008 X 8X 0.176 0.663 / 1.326 73.5 / 86.7 Acceptable Piping associated with B21-F041K (Top of Valve)
| |
| MSL-B, Node 6008 Y 8Y 0.155 0.229 / 0.457 32.3 / 66.1 Acceptable Piping associated with B21-F041K (Top of Valve)
| |
| MSL-B, Node 6008 Z 8Z 0.505 0.677 / 1.353 25.4 / 62.7 Acceptable Piping associated with B21-F041C (Top of Valve) | |
| MSL-C, Node 1008 X 9X 0.218 0.701 / 1.402 68.9 / 84.5 Acceptable Piping associated with B21-F041C (Top of Valve)
| |
| MSL-C, Node 1008 Y 9Y 0.127 0.185 / 0.370 31.4 / 65.7 Acceptable Piping associated with B21-F041C (Top of Valve)
| |
| MSL-C, Node 1008 Z 9Z 0.156 0.756 / 1.512 79.4 / 89.7 Acceptable Piping associated with B21-F051C (Actuator) | |
| MSL-C, Node 3010 X 10AX N/A 0.389 / 0.778 N/A Non-Operable Sensor Piping associated with B21-F051C (Actuator)
| |
| MSL-C, Node 3010 Y 10AY N/A 0.212 / 0.424 N/A Non-Operable Sensor Piping associated with B21-F051C (Actuator)
| |
| MSL-C, Node 3010 Z 10AZ N/A 0.436 / 0.872 N/A Non-Operable Sensor Attachment t o GNRO-2012/00113 Page 5 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g) | |
| ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
| |
| NOTES Piping associated with B21-F047G (Top of Valve)
| |
| MSL-C, Node 4008 X 10BX 0.565 0.645 / 1.290 12.4 / 56.2 Acceptable Piping associated with B21-F047G (Top of Valve)
| |
| MSL-C, Node 4008 Y 10BY 0.046 0.181 / 0.362 74.6 / 87.3 Acceptable Piping associated with B21-F047G (Top of Valve)
| |
| MSL-C, Node 4008 Z 10BZ 0.724 0.800 / 1.600 9.5 / 54.8 Acceptable Piping associated with B21-F047L (Top of Valve)
| |
| MSL-C, Node 6008 X 10CX 0.540 0.663 / 1.326 18.6 / 59.3 Acceptable Piping associated with B21-F047L (Top of Valve)
| |
| MSL-C, Node 6008 Y 10CY 0.22 1 0.229 / 0.457 3.5 / 51.6 Acceptable Piping associated with B21-F047L (Top of Valve)
| |
| MSL-C, Node 6008 Z 10CZ 0.408 0.677 / 1.353 39.7 / 69.8 Acceptable Piping associated with B21-F047D (Top of Valve) | |
| MSL-D, Node 1008 X 10DX 0.304 0.720 / 1.440 57.8 / 78.9 Acceptable Piping associated with B21-F047D (Top of Valve)
| |
| MSL-D, Node 1008 Y 10DY 0.143 0.160 / 0.320 10.6 / 55.3 Acceptable Piping associated with B21-F047D (Top of Valve)
| |
| MSL-D, Node 1008 Z 10DZ 0.349 0.671 / 1.341 48.0 / 74.0 Acceptable Piping associated with B21-F047D (Actuator)
| |
| MSL-D, Node 1010 X 10EX 0.432 0.447 / 0.893 3.4 / 51.6 Acceptable Piping associated with B21-F047D (Actuator)
| |
| MSL-D, Node 1010 Y 10EY 0.176 0.231 / 0.461 23.8 / 61.8 Acceptable
| |
|
| |
|
| Attachment t o GNRO-2012/00113 Page 6 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g) | | Attachment to GNRO-2012/00113 Page 8 of 8 COMP./PIPING MONITOR. PT. MEASURED ACCEL LIMIT MARGIN DESCRIPTION / NOTES LOC./DIR. NUM. ACCEL (g) (g) (%) |
| ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
| | SEGMENT B21-F047L X 1.50 6.62 77.40 Top of Valve Y 10c 0.85 3.42 75.23 Acceptable MSL-C, Node 6008 Z 1.50 6.62 77.40 B21-F047D X 1.43 6.62 78.35 Top of Valve Y 10d 0.76 3.42 77.69 Acceptable MSL-D, Node 1008 Z 1.43 6.62 78.35 B21-F047D X 2.66 3.78 29.63 Actuator Y 10e 1.07 3.77 71.63 Acceptable MSL-D, Node 1010 Z 2.66 3.78 29.63 B21-F041D X 1.33 3.78 64.79 Actuator Y 10f 0.85 3.77 77.57 Acceptable MSL-D, Node 2010 Z 1.33 3.78 64.79 B21-F051D X 1.46 3.78 61.23 Actuator Y 10g 0.59 3.77 84.31 Acceptable MSL-D, Node 4010 Z 1.46 3.78 61.23}} |
| NOTES Piping associated with B21-F047D (Actuator) MSL-D, Node 1010 Z 10EZ 0.132 0.434 / 0.868 69.6 / 84.8 Acceptable Piping associated with B21-F014D (Actuator)
| |
| MSL-D, Node 2010 X 10FX 0.297 0.349 / 0.697 14.9 / 57.4 Acceptable Piping associated with B21-F014D (Actuator)
| |
| MSL-D, Node 2010 Y 10FY 0.186 0.224 / 0.447 17.0 / 58.4 Acceptable Piping associated with B21-F014D (Actuator)
| |
| MSL-D, Node 2010 Z 10FZ 0.255 0.389 / 0.778 34.4 / 67.2 Acceptable Piping associated with B21-F051D (Actuator)
| |
| MSL-D, Node 4010 X 10GX 0.247 0.420 / 0.840 41.2 / 70.6 Acceptable Piping associated with B21-F051D (Actuator)
| |
| MSL-D, Node 4010 Y 10GY 0.142 0.310 / 0.619 54.2 / 77.1 Acceptable Piping associated with B21-F051D (Actuator)
| |
| MSL-D, Node 4010 Z 10GZ 0.450 0.474 / 0.948 5.1 / 52.5 Acceptable Piping associated with Pipe Support N11G001H14 Turbine Bldg.
| |
| MSL-D, Node 412 X 15X 0.092 0.213 / 0.426 56.8 / 78.4 Acceptable II. Main Steam Safety Relief Valve (SRV) Vibration Data and Acceptance Limits Table 2, below, contains the results from the SRV vibration testing performed as part of the GGNS EPU PAT P at ~4 408 MWt. The measured acceleration (ACC. ACTUAL) represents the peak acceleration reported by the tri-axial accelerometer in that particular direction for the individual node. This peak was gathered from the time
| |
| -history data after band
| |
| -pass filtering (2
| |
| - 250 Hz) and DC
| |
| -offset removal.
| |
| Attachment t o GNRO-2012/00113 Page 7 of 8 The methodology for developing the acceleration limits (ACC. LIMIT) below was through analytical methods involving ASME NB
| |
| -3500 calculations as well as structural sub
| |
| -models of individual components. For both the top
| |
| -of-valve and actuator locations, the horizontal limits (X and Z) seen below are a resultant limit calculated through the square root sum of the squares (SRSS) method. The vertical limit (Y) is an individual limit that is not used to calculate any resultant limits.
| |
| Table 2 COMP./PIPING DESCRIPTION / SEGMENT MONITOR. LOC./DIR. PT. NUM. MEASURED ACC EL (g) ACC EL LIMIT (g) MARGIN (%) NOTES B21-F041A X 1 N/A N/A Non-Op Sensor Top of Valve Y N/A Non-Op Sensor MSL-A, Node 1008 Z Non-Op Sensor B21-F041A X 2 1.20 3.78 68.28 Actuator Y 1.09 3.77 71.04 Acceptable MSL-A, Node 1010 Z 1.20 3.78 68.28 B21-F051A X 3 1.19 3.78 68.47 Actuator Y 1.11 3.77 70.49 Acceptable MSL-A, Node 2010 Z 1.19 3.78 68.47 B21-F047A X 4 0.70 3.78 81.58 Actuator Y 0.01 3.77 99.76 Acceptable MSL-A, Node 4010 Z 0.70 3.78 81.58 B21-F051B X 5 1.32 6.62 80.05 Top of Valve Y 2.08 3.42 39.27 Acceptable MSL-B, Node 1008 Z 1.32 6.62 80.05 B21-F051F X 6 1.57 3.78 58.50 Actuator Y 1.20 3.77 68.15 Acceptable MSL-B, Node 3010 Z 1.57 3.78 58.50 B21-F041F X 7 5.01 6.62 24.29 Top of Valve Y 0.12 3.42 96.57 Acceptable MSL-B, Node 4008 Z 5.01 6.62 24.29 B21-F041K X 8 1.40 6.62 78.80 Top of Valve Y 0.72 3.42 79.02 Acceptable MSL-B, Node 6008 Z 1.40 6.62 78.80 B21-F041C X 9 3.50 6.62 47.18 Top of Valve Y 3.27 3.42 4.31 Acceptable MSL-C, Node 1008 Z 3.50 6.62 47.18 B21-F051C X 10a N/A N/A Non-Op Sensor Actuator Y N/A Non-Op Sensor MS L-C, Node 3010 Z Non-Op Sensor B21-F047G X 10b 2.93 6.62 55.71 Top of Valve Y 0.08 3.42 97.81 Acceptable MSL-C, Node 4008 Z 2.93 6.62 55.71 Attachment t o GNRO-2012/00113 Page 8 of 8 COMP./PIPING DESCRIPTION / SEGMENT MONITOR. LOC./DIR. PT. NUM. MEASURED ACC EL (g) ACC EL LIMIT (g) MARGIN (%) NOTES B21-F047L X 10c 1.50 6.62 77.40 Top of Valve Y 0.85 3.42 75.23 Acceptable MSL-C, Node 6008 Z 1.50 6.62 77.40 B21-F047D X 10d 1.43 6.62 78.35 Top of Valve Y 0.76 3.42 77.69 Acceptable MSL-D, Node 1008 Z 1.43 6.62 78.35 B21-F047D X 10e 2.66 3.78 29.63 Actuator Y 1.07 3.77 71.63 Acceptable MSL-D, Node 1010 Z 2.66 3.78 29.63 B21-F041D X 10f 1.33 3.78 64.79 Actuator Y 0.85 3.77 77.57 Acceptable MSL-D, Node 2010 Z 1.33 3.78 64.79 B21-F051D X 10g 1.46 3.78 61.23 Actuator Y 0.59 3.77 84.31 Acceptable MSL-D, Node 4010 Z 1.46 3.78 61.23}}
| |
|
|---|
Category:Letter type:GNRO
MONTHYEARGNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021
2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1
GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021
Notification of Readiness for Supplemental Inspection
GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021
Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency
GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021
Annual Radioactive Effluent Release Report
GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021
Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020
GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021
Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206
GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020
2020 Report of Changes and Errors to 10 CFR 50.46 Analysis
GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020
Notification of Spent Fuel Cask Use
GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020
Response to NRC Integrated Inspection Report 05000416/2020002
GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020
Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020
GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020
Report of Technical Specification Bases Changes
GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020
Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)
GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020
Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies
GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020
Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)
GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020
Annual Radiological Effluent Release Report
GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020
Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206
GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020
Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test
GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020
Spent Fuel Storage Radioactive Effluent Release Report for 2019
GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020
License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies
GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019
Report of Changes and Errors to 10 CFR 50.46 Analysis
GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019
Notification of Readiness of 92723 Inspection
GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019
Emergency Plan, Revision 79
GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019
Notification of Spent Fuel Cask Use
GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019
Correction to Gnro 2019-00017 Emergency Plan Revision 78
GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019
Notification of Readiness of 95001 Supplemental Inspections
GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019
Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report
GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019
Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.
GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019
Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval
GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019
Annual Radioactive Effluent Release Report
GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019
Annual Radiological Operating Report (AREOR)
GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019
Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206
GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019
Emergency Plan, Revision 78
GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019
Snubber Testing Program for Fourth Inspection Interval
GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019
Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019
Spent Fuel Storage Radioactive Effluent Release Report for 2018
GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019
Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018
Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan
GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018
Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...
GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018
Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval
GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018
License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information
GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018
Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control
GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018
Submittal of 2018 Report of Changes and Errors to 10CFR50.46
GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018
Submittal of 2018 Inservice Inspection Summary Report
GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018
Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6
GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018
Core Operating Limits Report Cycle 22, Revision 1
GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018
Revised Offsite Dose Calculation Manual
GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018
Report of Technical Specification Bases Changes
GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018
Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018
2023-06-06
[Table view]
Category:Report
MONTHYEARML23325A1422023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23270B1892023-09-27027 September 2023
Evacuation Time Estimate Study
ML22011A2982022-01-11011 January 2022
ANS Evaluation Report
CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021
Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L
ML21272A3032021-09-30030 September 2021
Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report
ML21237A0512021-08-25025 August 2021
Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors
ML21081A1922021-06-30030 June 2021
Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment
GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021
Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020
ML21272A3382021-04-0101 April 2021
Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report
ML21090A0332021-03-31031 March 2021
Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1)
ML21083A1362021-03-23023 March 2021
Completed Activities
ML21083A1402021-03-22022 March 2021
Strategy 2
ML21083A1382021-03-22022 March 2021
Rulemaking
ML21083A1372021-03-22022 March 2021
NEIMA Reporting
ML21083A1392021-03-22022 March 2021
Strategy 1
ML21083A1412021-03-22022 March 2021
Strategy 3
ML21083A1432021-03-22022 March 2021
Strategy 5
ML21083A1422021-03-22022 March 2021
Strategy 4
ML21083A1442021-03-22022 March 2021
Strategy 6
ML21014A2672021-01-14014 January 2021
Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy
ML21075A2752020-12-22022 December 2020
FAQ 20-06 GGNS Scram - Final Approved
ML18123A3142018-05-0707 May 2018
Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015)
ML18085A5792018-03-26026 March 2018
Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals
ML17290B1372017-10-17017 October 2017
Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP
GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017
Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package
GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017
Focused Evaluation of External Flooding
GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016
Mitigating Strategies Assessment (MSA) for Flooding Submittal
GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016
Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016
GNRO-2016/00015, Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/000112016-03-23023 March 2016
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10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014
2014 Report of Changes and Errors to 10CFR50.46
GNRO-2014/00060, Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-26026 August 2014
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Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident
GNRO-2014/00027, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.2014-03-31031 March 2014
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Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
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Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Grand Gulf Nuclear Station, Unit 1, TAC No.: MF0954
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Summary of Root Cause Evaluation - Apparent Violation of 10CFR54.13 for Grand Gulf License Renewal
GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report2013-03-11011 March 2013
Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report
CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013
Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments
GNRO-2012/00150, Final Report for Replacement Steam Dryer2012-12-0606 December 2012
Final Report for Replacement Steam Dryer
GNRO-2012/00140, Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from ..2012-11-26026 November 2012
Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from ..
GNRO-2012/00141, Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 3452012-11-15015 November 2012
Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 345
ML12352A0712012-11-15015 November 2012
Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Cover Through Attachment C, Seismic Walkdown Checklists (Swcs), Page 150 of 345
ML12352A0692012-11-15015 November 2012
Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment D, Area Walk-by Checklist (Awcs), Page 1 of 167 Through End
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Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 252 of 345 Through Page 345 of 345
GNRO-2012/00113, Vibration Data Report2012-09-18018 September 2012
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GNRO-2012/00109, Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation2012-09-0606 September 2012
Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation
GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012
Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp
ML12159A5152012-06-11011 June 2012
Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident
2023-09-27
[Table view]
Category:Miscellaneous
MONTHYEARML23325A1422023-11-21021 November 2023
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ANS Evaluation Report
CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021
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GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021
Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020
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Completed Activities
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Rulemaking
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Strategy 6
ML21083A1432021-03-22022 March 2021
Strategy 5
ML21083A1422021-03-22022 March 2021
Strategy 4
ML21083A1412021-03-22022 March 2021
Strategy 3
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Strategy 2
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Strategy 1
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NEIMA Reporting
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Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy
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FAQ 20-06 GGNS Scram - Final Approved
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Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015)
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Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals
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Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP
GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017
Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package
GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017
Focused Evaluation of External Flooding
GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016
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GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016
Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016
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10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014
2014 Report of Changes and Errors to 10CFR50.46
GNRO-2014/00060, Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-26026 August 2014
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Report of 10CFR72.48 Evaluations - July 1, 2012 Through June 30, 2014
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Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident
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Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report
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Vibration Data Report
GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012
Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp
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Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident
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Attachment 8 to GNRO-2012/00039 - from Diskette Labeled: Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment K Labeled Condition Reports.
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Attachment 38 to GNRO-2012/00039 - Ensr. 2007, Impingement Mortality and Entrainment Characterization Study (Imecs), Entergy -Waterford 3. December 2007
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Attachment 22 to GNRO-2012/00039, Er Reference - Entergy 2010e (NPDES Crs)
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Attachment 27 to GNRO-2012/00039, Er Reference - GGNS 2007b (2006 Wmp Report) Grand Gulf Nuclear Station 2006 Waste Minimization Certified Report
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Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
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BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages
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Special Report 2008-001 - Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System
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Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints
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GG-05-2007-FINAL Operating Exam, Operations Training, Determine Shift Staffing to Meet Shift Requirements
CNRO-2006-00043, Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-7162006-09-22022 September 2006
Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-716
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Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee
CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests2006-04-24024 April 2006
Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests
ML0607204302006-03-0101 March 2006
March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations.
2023-11-21
[Table view] |
Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368-5516 GNRO-2012/00113 September 18, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Vibration Data Report Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
Entergy Operations, Inc. letter to the NRC (GNRO-2012/00079), Summary Report of Replacement Steam Dryer Data - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession
- ML12221A198)
Dear Sir or Madam:
In the referenced letter, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in the attachment to this letter.
If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
This letter contains no new regulatory commitments.
Sincerely, BSF/ghd
Attachment:
Vibration Data for the Main Steam Line Piping and Safety Relief Valves -
4408 MWt
GNRO- 2012/00113 Page 2 of 2 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)
ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
ATTACHMENT GRAND GULF NUCLEAR STATION GNRO-2012/00113 VIBRATION DATA FOR THE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES -
4408 MWt
Attachment to GNRO-2012/00113 Page 1 of 8 VIBRATION DATA FOR THE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES -
4408 MWt In a letter to the NRC staff1, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in Sections I and II, below.
Node 1008 on MSL-A has reported data that contained intermittent high-amplitude spikes.
These types of spikes were not seen in the corresponding data for the other valves at the same valve location (top) nor were they seen in the data at any of the nodes. For these reasons, the data at this location were deemed unusable.
Node 3010 on MSL-C has also reported data that indicates a failure in the mounting system.
Two sets of data were retrieved at the 105% power plateau; one was taken directly after the plateau was reached and a subsequent set was taken before the ascension to the 107.5%
plateau. While the plant data indicated a small increase in main steam flow, there was a markedly higher increase in the X (longitudinal), Y (vertical), and Z (lateral) accelerations at Node 3010 on MSL-C. This magnitude increase for Node 3010 is in excess of 2 standard deviations above the response noted for the other 15 SRVs. PSD comparisons were made to the MSL response at SRV monitoring points on two valves at Nodes 1008 and 3010 on MSL-C. The PSD comparison for X, Y, and Z responses shows a large change in frequency response through much of the 1 - 250-Hz range at Node 3010 and only a small change in magnitude at the Node 1008 location. The three accelerometers at Node 3010 are mounted on the same block and strapped to the valve actuator. It is expected that the mounting straps have loosened and the sensor has shifted. The measured response is most likely being affected by the response of the accelerometer mounting system; therefore, this measured response is unusable.
I. Main Steam Line (MSL) Piping Vibration Data and Acceptance Limits Table 1, below, contains the results from the MSL piping vibration testing performed as part of the GGNS Extended Power Uprate (EPU) Power Ascension Test Plan (PATP) at ~4408 MWt.
The measured accelerations were taken in the major axes for each of the nodes. A band pass filter (RMS) for the test data was applied based on:
- Lower Limit - Capturing frequencies below the lowest piping frequency which corresponds to the highest piping stresses. Generally, this number is higher than 1 Hz, which typically contains voltage drift and DC signals that need to be removed.
1 Entergy Operations, Inc. letter to the NRC (GNRO-2012/00079), Summary Report of Replacement Steam Dryer Data - Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198)
Attachment to GNRO-2012/00113 Page 2 of 8
- Upper Limit - The upper limit frequency should be sufficiently high so there is no significant modal participation on the maximum piping stresses. Also, the intent is to remove the high frequency noise, generally above 100 Hz.
The acceptance criteria are based on applying a constant 1-g acceleration spectrum to the piping model and determining the maximum stress. The maximum stress was compared with the OM criteria alternating stress allowable per ASME OM-S/G-1997, Standards and Guides for Operation and Maintenance of Nuclear Power Plants. The resulting ratio was used to modify the output accelerations at the location for each of the test points.
Table 1 ACCEL.
PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 /
DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g)
MARGIN (%)
Piping associated with B21-F041A Non-Operable X 1X N/A 0.720 / 1.440 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A Non-Operable Y 1Y N/A 0.160 / 0.320 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A Non-Operable Z 1Z N/A 0.671 / 1.341 N/A (Top of Valve) Sensor MSL-A, Node 1008 Piping associated with B21-F041A X 2X 0.363 0.447 / 0.893 18.8 / 59.4 Acceptable (Actuator)
MSL-A, Node 1010 Piping associated with B21-F041A Y 2Y 0.157 0.231 / 0.461 32.0 / 65.9 Acceptable (Actuator)
MSL-A, Node 1010 Piping associated with B21-F041A Z 2Z 0.212 0.434 / 0.868 51.2 / 75.6 Acceptable (Actuator)
MSL-A, Node 1010 Piping associated with B21-F051A X 3X 0.200 0.349 / 0.697 42.7 / 71.3 Acceptable (Actuator)
MSL-A, Node 2010 Piping associated with B21-F051A Y 3Y 0.193 0.224 / 0.447 13.8 / 56.8 Acceptable (Actuator)
MSL-A, Node 2010
Attachment to GNRO-2012/00113 Page 3 of 8 ACCEL.
PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 /
DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g)
MARGIN (%)
Piping associated with B21-F051A Z 3Z 0.248 0.389 / 0.778 36.2 / 68.1 Acceptable (Actuator)
MSL-A, Node 2010 Piping associated with B21-F047A X 4X 0.171 0.420 / 0.840 59.3 / 79.6 Acceptable (Actuator)
MSL-A, Node 4010 Piping associated with B21-F047A Y 4Y 0.031 0.310 / 0.619 90.0 / 95.0 Acceptable (Actuator)
MSL-A, Node 4010 Piping associated with B21-F047A Z 4Z 0.217 0.474 / 0.948 54.2 / 77.1 Acceptable (Actuator)
MSL-A ,Node 4010 Piping associated with B21-F051B X 5X 0.004 0.701 / 1.402 99.4 / 99.7 Acceptable (Top of Valve)
MSL-B, Node 1008 Piping associated with B21-F051B Y 5Y 0.098 0.185 / 0.370 47.0 / 73.5 Acceptable (Top of Valve)
MSL-B, Node 1008 Piping associated with B21-F051B Z 5Z 0.706 0.756 / 1.512 6.6 / 53.3 Acceptable (Top of Valve)
MSL-B, Node 1008 Piping associated with B21-F051F X 6X 0.040 0.389 / 0.778 89.7 / 94.9 Acceptable (Actuator)
MSL-B, Node 3010 Piping associated with B21-F051F Y 6Y 0.093 0.212 / 0.424 56.1 / 78.1 Acceptable (Actuator)
MSL-B, Node 3010 Piping associated with B21-F051F Z 6Z 0.166 0.436 / 0.872 61.9 / 81.0 Acceptable (Actuator)
MSL-B, Node 3010 Piping associated with B21-F041F X 7X 0.254 0.645 / 1.290 60.6 / 80.3 Acceptable (Top of Valve)
MSL-B, Node 4008
Attachment to GNRO-2012/00113 Page 4 of 8 ACCEL.
PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 /
DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g)
MARGIN (%)
Piping associated with B21-F041F Y 7Y 0.120 0.181 / 0.362 33.7 / 66.9 Acceptable (Top of Valve)
MSL-B, Node 4008 Piping associated with B21-F041F Z 7Z 0.572 0.800 / 1.600 28.5 / 64.3 Acceptable (Top of Valve)
MSL-B, Node 4008 Piping associated with B21-F041K X 8X 0.176 0.663 / 1.326 73.5 / 86.7 Acceptable (Top of Valve)
MSL-B, Node 6008 Piping associated with B21-F041K Y 8Y 0.155 0.229 / 0.457 32.3 / 66.1 Acceptable (Top of Valve)
MSL-B, Node 6008 Piping associated with B21-F041K Z 8Z 0.505 0.677 / 1.353 25.4 / 62.7 Acceptable (Top of Valve)
MSL-B, Node 6008 Piping associated with B21-F041C X 9X 0.218 0.701 / 1.402 68.9 / 84.5 Acceptable (Top of Valve)
MSL-C, Node 1008 Piping associated with B21-F041C Y 9Y 0.127 0.185 / 0.370 31.4 / 65.7 Acceptable (Top of Valve)
MSL-C, Node 1008 Piping associated with B21-F041C Z 9Z 0.156 0.756 / 1.512 79.4 / 89.7 Acceptable (Top of Valve)
MSL-C, Node 1008 Piping associated with B21-F051C Non-Operable X 10AX N/A 0.389 / 0.778 N/A (Actuator) Sensor MSL-C, Node 3010 Piping associated with B21-F051C Non-Operable Y 10AY N/A 0.212 / 0.424 N/A (Actuator) Sensor MSL-C, Node 3010 Piping associated with B21-F051C Non-Operable Z 10AZ N/A 0.436 / 0.872 N/A (Actuator) Sensor MSL-C, Node 3010
Attachment to GNRO-2012/00113 Page 5 of 8 ACCEL.
PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 /
DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g)
MARGIN (%)
Piping associated with B21-F047G X 10BX 0.565 0.645 / 1.290 12.4 / 56.2 Acceptable (Top of Valve)
MSL-C, Node 4008 Piping associated with B21-F047G Y 10BY 0.046 0.181 / 0.362 74.6 / 87.3 Acceptable (Top of Valve)
MSL-C, Node 4008 Piping associated with B21-F047G Z 10BZ 0.724 0.800 / 1.600 9.5 / 54.8 Acceptable (Top of Valve)
MSL-C, Node 4008 Piping associated with B21-F047L X 10CX 0.540 0.663 / 1.326 18.6 / 59.3 Acceptable (Top of Valve)
MSL-C, Node 6008 Piping associated with B21-F047L Y 10CY 0.221 0.229 / 0.457 3.5 / 51.6 Acceptable (Top of Valve)
MSL-C, Node 6008 Piping associated with B21-F047L Z 10CZ 0.408 0.677 / 1.353 39.7 / 69.8 Acceptable (Top of Valve)
MSL-C, Node 6008 Piping associated with B21-F047D X 10DX 0.304 0.720 / 1.440 57.8 / 78.9 Acceptable (Top of Valve)
MSL-D, Node 1008 Piping associated with B21-F047D Y 10DY 0.143 0.160 / 0.320 10.6 / 55.3 Acceptable (Top of Valve)
MSL-D, Node 1008 Piping associated with B21-F047D Z 10DZ 0.349 0.671 / 1.341 48.0 / 74.0 Acceptable (Top of Valve)
MSL-D, Node 1008 Piping associated with B21-F047D X 10EX 0.432 0.447 / 0.893 3.4 / 51.6 Acceptable (Actuator)
MSL-D, Node 1010 Piping associated with B21-F047D Y 10EY 0.176 0.231 / 0.461 23.8 / 61.8 Acceptable (Actuator)
MSL-D, Node 1010
Attachment to GNRO-2012/00113 Page 6 of 8 ACCEL.
PIPING ACCEL. LIMIT MONITOR POINT MEASURED LEVEL 2 /
DESCRIPTION/ LEVEL 2 / NOTES LOC./DIR. NUM. ACCEL (g) LEVEL 1 SEGMENT LEVEL 1 (g)
MARGIN (%)
Piping associated with B21-F047D Z 10EZ 0.132 0.434 / 0.868 69.6 / 84.8 Acceptable (Actuator)
MSL-D, Node 1010 Piping associated with B21-F014D X 10FX 0.297 0.349 / 0.697 14.9 / 57.4 Acceptable (Actuator)
MSL-D, Node 2010 Piping associated with B21-F014D Y 10FY 0.186 0.224 / 0.447 17.0 / 58.4 Acceptable (Actuator)
MSL-D, Node 2010 Piping associated with B21-F014D Z 10FZ 0.255 0.389 / 0.778 34.4 / 67.2 Acceptable (Actuator)
MSL-D, Node 2010 Piping associated with B21-F051D X 10GX 0.247 0.420 / 0.840 41.2 / 70.6 Acceptable (Actuator)
MSL-D, Node 4010 Piping associated with B21-F051D Y 10GY 0.142 0.310 / 0.619 54.2 / 77.1 Acceptable (Actuator)
MSL-D, Node 4010 Piping associated with B21-F051D Z 10GZ 0.450 0.474 / 0.948 5.1 / 52.5 Acceptable (Actuator)
MSL-D, Node 4010 Piping associated with Pipe Support N11G001H14 X 15X 0.092 0.213 / 0.426 56.8 / 78.4 Acceptable Turbine Bldg.
MSL-D, Node 412 II. Main Steam Safety Relief Valve (SRV) Vibration Data and Acceptance Limits Table 2, below, contains the results from the SRV vibration testing performed as part of the GGNS EPU PATP at ~4408 MWt.
The measured acceleration (ACC. ACTUAL) represents the peak acceleration reported by the tri-axial accelerometer in that particular direction for the individual node. This peak was gathered from the time-history data after band-pass filtering (2 - 250 Hz) and DC-offset removal.
Attachment to GNRO-2012/00113 Page 7 of 8 The methodology for developing the acceleration limits (ACC. LIMIT) below was through analytical methods involving ASME NB-3500 calculations as well as structural sub-models of individual components. For both the top-of-valve and actuator locations, the horizontal limits (X and Z) seen below are a resultant limit calculated through the square root sum of the squares (SRSS) method. The vertical limit (Y) is an individual limit that is not used to calculate any resultant limits.
Table 2 COMP./PIPING MONITOR. PT. MEASURED ACCEL LIMIT MARGIN DESCRIPTION / NOTES LOC./DIR. NUM. ACCEL (g) (g) (%)
SEGMENT B21-F041A X Non-Op Sensor Top of Valve Y 1 N/A N/A N/A Non-Op Sensor MSL-A, Node 1008 Z Non-Op Sensor B21-F041A X 1.20 3.78 68.28 Actuator Y 2 1.09 3.77 71.04 Acceptable MSL-A, Node 1010 Z 1.20 3.78 68.28 B21-F051A X 1.19 3.78 68.47 Actuator Y 3 1.11 3.77 70.49 Acceptable MSL-A, Node 2010 Z 1.19 3.78 68.47 B21-F047A X 0.70 3.78 81.58 Actuator Y 4 0.01 3.77 99.76 Acceptable MSL-A, Node 4010 Z 0.70 3.78 81.58 B21-F051B X 1.32 6.62 80.05 Top of Valve Y 5 2.08 3.42 39.27 Acceptable MSL-B, Node 1008 Z 1.32 6.62 80.05 B21-F051F X 1.57 3.78 58.50 Actuator Y 6 1.20 3.77 68.15 Acceptable MSL-B, Node 3010 Z 1.57 3.78 58.50 B21-F041F X 5.01 6.62 24.29 Top of Valve Y 7 0.12 3.42 96.57 Acceptable MSL-B, Node 4008 Z 5.01 6.62 24.29 B21-F041K X 1.40 6.62 78.80 Top of Valve Y 8 0.72 3.42 79.02 Acceptable MSL-B, Node 6008 Z 1.40 6.62 78.80 B21-F041C X 3.50 6.62 47.18 Top of Valve Y 9 3.27 3.42 4.31 Acceptable MSL-C, Node 1008 Z 3.50 6.62 47.18 B21-F051C X Non-Op Sensor Actuator Y 10a N/A N/A N/A Non-Op Sensor MSL-C, Node 3010 Z Non-Op Sensor B21-F047G X 2.93 6.62 55.71 Top of Valve Y 10b 0.08 3.42 97.81 Acceptable MSL-C, Node 4008 Z 2.93 6.62 55.71
Attachment to GNRO-2012/00113 Page 8 of 8 COMP./PIPING MONITOR. PT. MEASURED ACCEL LIMIT MARGIN DESCRIPTION / NOTES LOC./DIR. NUM. ACCEL (g) (g) (%)
SEGMENT B21-F047L X 1.50 6.62 77.40 Top of Valve Y 10c 0.85 3.42 75.23 Acceptable MSL-C, Node 6008 Z 1.50 6.62 77.40 B21-F047D X 1.43 6.62 78.35 Top of Valve Y 10d 0.76 3.42 77.69 Acceptable MSL-D, Node 1008 Z 1.43 6.62 78.35 B21-F047D X 2.66 3.78 29.63 Actuator Y 10e 1.07 3.77 71.63 Acceptable MSL-D, Node 1010 Z 2.66 3.78 29.63 B21-F041D X 1.33 3.78 64.79 Actuator Y 10f 0.85 3.77 77.57 Acceptable MSL-D, Node 2010 Z 1.33 3.78 64.79 B21-F051D X 1.46 3.78 61.23 Actuator Y 10g 0.59 3.77 84.31 Acceptable MSL-D, Node 4010 Z 1.46 3.78 61.23
