PNP 2014-067, Response to Third Request for Additional Information - Reactor Vessel Internals (ME9569)
| ML14183A014 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/01/2014 |
| From: | Gustafson O Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PNP 2014-067, TAC ME9569 | |
| Download: ML14183A014 (5) | |
Text
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-=-Entergy Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, M I 49043-9530 PNP 2014-067 July 1,2014 Tel 269 7642000 Otto W. Gustafson Regulatory and Performance Improvement Director U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Third Request for Additional Information - Reactor Vessel Internals (ME9569)
Palisades Nuclear Plant Docket 50-255 License No. DPR-20
References:
- 1. Entergy Nuclear Operations, Inc. letter to NRC, "Revised Program Plan for Aging Management of Reactor Vessel Internals," September 13, 2012 (ADAMS Accession Number ML12257A352)
- 2. NRC e-mail, "Palisades - Request for Additional Information - ME9569 -
Revised Program Plan for Aging Management of Reactor Vessel Internals,"
March 4,2013 (ADAMS Accession Number ML13063A318)
- 3. Entergy Nuclear Operations, Inc. letter to NRC, "Response to Request for Additional Information - Revised Program Plan for Aging Management of Reactor Vessel Internals," April 4, 2013 (ADAMS Accession Number ML13094A414)
- 4. NRC e-mail, "Palisades - Request for Additional Information - Reactor Vessel Internals - ME9569 - Email Resend," December 12, 2013 (ADAMS Accession Number ML13346A644)
- 5. Entergy Nuclear Operations, Inc. letter to NRC, "Summary of January 2, 2014 Teleconference with Nuclear Regulatory Staff on Palisades - Request for Additional Information - Reactor Vessel Internals - ME9569 Response Schedule," January 07, 2014 (ADAMS Accession Number ML14007A151)
- 6. Entergy Nuclear Operations, Inc. letter to NRC, "Response to Second Request for Additional Information - Reactor Vessel Internals -ME9569,"
April 03, 2014 (ADAMS Accession Number ML14097A376)
- 7. NRC e-mail, "Request for Additional Information - Palisades - Aging Management Program for Reactor Vessel Internals - ME9569," June 09, 2014 (ADAMS Accession Number ML14160B264)
PNP 2014-067 Page 2 of 2
Dear Sir or Madam:
In Reference 1, Entergy Nuclear Operations, Inc. (ENO) submitted to the Nuclear Regulatory Commission (NRC) a revised program plan for aging management of reactor vessel internals.
In Reference 2, the NRC issued a request for additional information (RAI). ENO responded to the RAI in Reference 3.
In Reference 4, the NRC issued a second RAI with a 30-day required response. In Reference 5, ENO documented a teleconference during which the NRC accepted a request to extend the second RAI response from 30 days to 120 days. ENO responded to the second RAI in Reference 6.
In Reference 7, the NRC issued a third RAI with a 30-day required response.
The response to the third RAI is provided in the attachment.
This submittal contains no proprietary information.
This submittal contains no new or revised commitments.
Sincerely, OWG/jpm
Attachment:
Response to Third Request for Additional Information for Reactor Vessel Internals (ME9569) cc:
Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ATTACHMENT Response to Third Request for Additional Information for Reactor Vessel Internals (ME9569)
By letter dated September 13, 2012, Entergy Nuclear Operations, Inc. (END) submitted to the Nuclear Regulatory Commission (NRC) a revised program plan for aging management of reactor vessel internals. By electronic mail, dated June 09, 2014 the Nuclear Regulatory Commission (NRC) issued a third request for additional information. The requested information is provided below.
- 1.
NRC Information Request - RAI-3.1 Provide the value of the heat generation figure of merit, "F", for the Palisades Nuclear Plant (PNP) reactor vessel internals (RVI) as defined on p. 6 of Attachment 1 to MRP 2013-025 (Ref. 1).
ENO Response The heat generation Figure of Merit, "F", for the PNP reactor vessel internals is shown in the figure below.
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Cycle 21 Depletion Step 1 Core Average Power Density 80.44 ultra-low leakage 1
2 4
5 6
7 9
10 11 12 13 14 15 16 **
26.84 0.196 0.321 0.312 0.312 0.321 0.196 26.82 0.057 0.338 0.747 1.22 0.952 0.952 1.219 0.746 0.338 0.057 44.42 0.385 0.886 1.41 1.302 1.48 1.48 1.301 1.408 0.885 0.384 44.35 0.133 0.42 1.21 1 1.27 1.331 1.536 1.112 1.112 1.535 1.329 1.266 1.209 0.42 0.133 27.54 0.355 0.904 1.28 1.234 1.554 1.071 1.547 1.547 1.071 1.552 1.232 1.278 0.903 0.355 27.52 0.202 0.73 1.391 1.317 1.535 1.273 1.513 1.042 1.041 1.512 1.272 1.534 1.316 1.39 0.729 0.202 0.276 1.125 1.257 1.501 1.049 1.493 1.031 1.165 1.165 1.03 1.492 1.048 1.5 1.256 1.124 0.275 0.118 0.809 1.388 1.077 1.517 1.028 1.158 1.463 1.462 1.157 1.027 1.515 1.076 1.387 0.808 0.118 0.119 0.809 1.388 1.077 1.517 1.029 1.158 1.463 1.462 1.157 1.027 1.515 1.076 1.387 0.808 0.118 10 0.276 1.125 1.257 1.501 1.049 1.493 1.031 1.165 1.165 1.03 1.492 1.048 1.499 1.256 1.124 0.275 11 0.202 0.73 1.391 1.318 1.536 1.274 1.513 1.041 1.041 1.512 1.272 1.533 1.315 1.389 0.729 0.202 12 27.56 0.356 0.905 1.282 1.234 1.554 1.072 1.547 1.547 1.071 1.552 1.232 1.278 0.902 0.355 27.52 13 0.133 0.421 1.212 1.268 1.331 1.536 1.112 1.112 1.535 1.329 1.266 1.209 0.42 0.133 14 44.46 0.385 0.886 1.409 1.302 1.481 1.48 1.302 1.408 0.885 0.384 44.35 15 0.057 0.338 0.747 1.22 0.952 0.952 1.22 0.746 0.338 0.057 16 26.84 0.196 0.321 0.312 0.312 0.321 0.196 26.82 ABO E
G H
K M
N Q
R T
V X
Z Cycle 21 Depletion Step 9 Core Average Power Density 80.44 ultra-low leakage 456 7
9 10 11 12 13 14 15 16 **
28.70 0.218 0.345 0.345 0.345 0.345 0.218 28.67 0.07 0.371 0.763 1.167 0.962 0.962 1.167 0.763 0.37 0.07 42.79 0.391 0.874 1.402 1.266 1.518 1.518 1.266 1.402 0.874 0.391 42.79 0.154 0.428 1.09 1.174 1.279 1.565 1.146 1.146 1.565 1.278 1.172 1.09 0.428 0.154 30.17 0.395 0.899 1.188 1.173 1.556 1.101 1.59 1.59 1.101 1.556 1.172 1.188 0.899 0.395 30.17 0.232 0.766 1.409 1.281 1.549 1.267 1.528 1.046 1.045 1.528 1.267 1.549 1.282 1.409 0.766 0.232 0.31 1.122 1.259 1.56 1.094 1.521 1.009 1.068 1.068 1.009 1.521 1.094 1.56 1.259 1.122 0.31 0.146 0.866 1.479 1.139 1.587 1.043 1.066 1.226 1.226 1.066 1.043 1.587 1.139 1.479 0.866 0.146 0.146 0.866 1.479 1.139 1.587 1.043 1.066 1.226 1.226 1.066 1.043 1.587 1.139 1.479 0.866 0.146 10 0.31 1.122 1.259 1.56 1.094 1.521 1.009 1.068 1.068 1.009 1.521 1.093 1.56 1.259 1.122 0.31 11 0.232 0.766 1.409 12 30.17 0.395 0.899 13 0.154 0.428 14 42.79 15 16 A
B o
E ICycie 21 Depletion Step 17 1
2 0.211 35.84 0.482 0.297 0.839 0.384 1.162 0.197 0.934 0.197 0.934 10 0.384 1.162 11 0.297 0.839 12 35.84 0.482 13 14 15 16 A
B 0.211 o
48.29 0.512 0.963 1.37 1.234 1.465 1.465 1.233 1.37 0.963 0.512 48.29 E
1.282 1.549 1.267 1.528 1.045 1.045 1.189 1.173 1.556 1.101 1.59 1.59 1.09 1.173 1.279 1.565 1.146 1.146 0.391 0.874 1.402 1.266 1.518 1.518 0.07 0.37 0.763 1.167 0.962 0.962 28.67 0.218 0.345 0.345 0.345 G
H J
K M
N Core Average Power Density 456 7
33.84 0.277 0.418 0.105 0.452 0.829 1.189 0.469 0.936 1.357 1.227 1.13 1.176 1.229 1.479 1.19 1.156 1.473 1.068 1.237 1.473 1.204 1.415 1.486 1.067 1.413 1.012 1.118 1.448 1.032 1.083 1.118 1.448 1.032 1.084 1.486 1.067 1.413 1.013 1.237 1.473 1.205 1.415 1.192 1.156 1.473 1.068 1.13 1.175 1.229 1.479 0.469 0.936 1.357 1.227 0.105 0.451 0.828 1.189 33.80 0.277 0.418 G
H J
K 0.423 1.007 1.472 1.113 1.444 1.031 1.084 1.228 1.228 1.084 1.03 1.444 1.113 1.472 1.007 0.423 M
80.44 9
0.423 1.007 1.472 1.113 1.444 1.03 1.084 1.228 1.228 1.084 1.03 1.444 1.113 1.472 1.007 0.423 N
1.528 1.267 1.549 1.281 1.187 1.09 0.391 0.07 1.1 01 1.556 1.172 1.565 1.279 1.172 1.266 1.402 0.874 1.167 0.763 0.37 0.345 0.218 28.67 10 0.418 1.189 1.227 1.479 1.068 1.415 1.012 1.083 1.083 1.013 1.415 1.068 1.479 1.228 1.189 0.418 Q
R T
ultra-low leakage 11 12 13 0.277 33.81 0.829 0.451 0.105 1.357 0.936 0.469 1.229 1.175 1.13 1.473 1.156 1.19 1.205 1.473 1.237 1.413 1.067 1.486 1.032 1.449 1.118 1.032 1.449 1.118 1.413 1.067 1.486 1.205 1.473 1.237 1.473 1.156 1.19 1.229 1.175 1.13 1.357 0.936 0.469 0.829 0.451 0.105 0.277 33.81 V
Q R
T V
Figure of Merit Calculations for Palisades Cycle 21 1.409 0.899 0.428 42.79 14 48.29 0.512 0.963 1.37 1.234 1.465 1.465 1.234 1.37 0.963 0.512 48.29 X
X 0.766 0.395 0.154 15 0.211 0.482 0.839 1.163 0.934 0.934 1.163 0.839 0.482 0.211 z
z 0.232 30.17 16 **
35.84 0.297 0.384 0.197 0.197 0.384 0.297 35.84 Note: The shaded boxes show the Figure of Merit (FoM) calculations for Cycle 21. Cycle 21 is considered ultra-low leakage, representative of current and planned future core designs at PNP. Cycle 21 above shows FoM values well below the MRP 2013-025 criteria ofF :s 68 watts/cm3.
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5 10 11 13 14 16 17 19 20 22 23 4
10 11 13 14 16 17 19 20 22 23 4
10 11 13 14 16 17 19 20 22 23
- 2.
NRC Information Request - RAI-3.2 The April 4,2013 response to Request for Additional Information (RAI) 5 (Ref. 2) indicates that Alloy A-286 is used in two components related to the hold-down spring assembly, the plunger assemblies and jackscrews, and that 17-4 PH stainless steel is used in the grid ring bushings in the upper guide structure. The response to RAI 5 also provided evaluations for these components demonstrating no inspections were necessary under the PNP RVI aging management program (AMP). However, these components do not appear to be listed in Attachment B to the AMP, "Palisades Reactor Vessel Internals Components in LRA
[License Renewal Application] and Aging Management Evaluation," unless under a different name. Clarify whether the components identified in RAI 5 are included in Attachment B under different names, or revise Attachment B to include these components.
References:
- 1. MRP-227 -A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs, Enclosure to MRP Letter 2013-025, October 14, 2013.
- 2. Palisades, Response to Request for Additional Information - Revised Program Plan for Aging Management of Reactor Vessel Internals, dated April 4, 2013 (ADAMS Accession No. ML13094A414)
ENO Response The A-286 components are listed in Attachment B. The plunger assemblies and jack screws are listed under "Component/Commodity" "Upper Internal Assembly Hold-down Ring Plunger." The column labeled "Additional Description" states what is included in each component and for this component, it lists the "Hold-Down Ring Plungers including washers and jack screws."
The 17-4 PH stainless steel grid ring bushings are included in Attachment B under the "Component/Commodity" "Upper Internal Assembly Brace Grid Beam" grouping, as they are part of this assembly.
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