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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 March 30. 2011 Mr. Barry S. Allen Vice President, Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449 SUB.JECT: REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.1 (TAC NO. ME4640) |
| D.C. 20555-0001 March 30. 2011 Mr. Barry S. Allen Vice President, Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION -SECTION 2.1 (TAC NO. ME4640) | |
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| ==Dear Mr. Allen:== | | ==Dear Mr. Allen:== |
| By letter dated August 27,2010, FirstEnergy Nuclear Operating Company (FENOC). submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (1 0 CFR Part 54) for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station (DBNPS). The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the Enclosure. | | |
| Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions. | | By letter dated August 27,2010, FirstEnergy Nuclear Operating Company (FENOC). submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (1 0 CFR Part 54) for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station (DBNPS). |
| please contact me by telephone at 301-415-2277 or bye-mall at brian.harris2@nrc.gov Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket 50-346 | | The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future. |
| | Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions. |
| | please contact me by telephone at 301-415-2277 or bye-mall at brian.harris2@nrc.gov sincere: /~ |
| | tf~* |
| | Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv DAVIS-BESSE NUCLEAR POWER LICENSE RENEWAL REQUEST FOR ADDITIONAL 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] | | As stated cc w/encl: Distribution via Listserv |
| functions identified in (a)(1 )(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the License Renewal Application (LRA), the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined that the applicant had identified safety-related components located in the turbine building.
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| The applicant also confirmed that there are nonsafety-related structures, systems, and components (SSCs) in the vicinity of the safety-related components.
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| The applicant had concluded that the nonsafety-related SSCs were not required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| The staff requests that the applicant provide a description and the results of the evaluation that formed the basis for concluding that the nonsafety related SSCs, located within the vicinity of safety-related SSCs within the turbine building, do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-2 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)(1 )(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined through a review of license renewal drawings and discussion with the applicant that for certain systems, nonsafety-related pipe attached to safety-related pipe, had not been included within the scope of license renewal. ENCLOSURE
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| -The staff requests that the applicant provide details of the analysis performed and any conclusions related to nonsafety-related pipe, attached to safety-related pipe, for inclusion within the scope of license renewal up to and including a seismic anchor or equivalent, in accordance with 10 CFR 54.4(a)(2).
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-3 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)(1 )(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28,2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined through a review of license renewal drawings and discussion with the applicant that equipment that was no longer required had been placed in an abandoned state. The staff requests that the applicant provide details on the activities performed to confirm that all abandoned equipment that at any time contained fluids, and is in the proximity of safety-related SSCs, has been verified to be drained. If abandoned equipment has not been verified to be drained or is not included within the scope of license renewal, provide details of the analysis performed and any conclusions, related to the inclusion of abandoned equipment within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-4 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)(1 )(i), (ii), or (iii) of this section.
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| -During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined that the applicant did not include nonsafety-related relief valve drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staff's review determined that the function of a drain line is to pass fluid when required and therefore the pipe should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction.
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| The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs.
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| The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially
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| 'fluid filled, nonsafety-related relief valve drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-5 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)(1)(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined that the applicant did not include nonsafety-related drip pans and retention area drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staffs review determined that the function of the drip pans and retention area drain lines is to contain or pass fluid when required and therefore should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction and 10 CFR 54.21. The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs.
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| The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially fluid filled, non safety-related drip pan and retention area drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-6 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)( 1 )(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| During a plant walkdown, the staff observed a nonsafety-related domestic water valve and other nonsafety-related fluid filled SSCs located in the service water tunnel and in the vicinity of safety-related SSCs. The staff requests that the applicant provide a basis for not including the non-safety related components, within the vicinity of safety-related SSCs within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-7 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related]
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| functions identified in (a)(1)(i), (ii), or (iii) of this section. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns.
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| During a plant walkdown, the staff
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| -observed the nonsafety-related condensate line located in the turbine building that exited through the deck to the space below that contained the auxiliary feedwater pumps. The applicant indicated that the condensate line nonsafety-related to safety-related interface was located at a point below the turbine building deck. The staff requests that the applicant identify the specific location of the nonsafety to related interface and all mitigative features installed to protect the integrity of the nonsafety to safety-related interface.
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| The staff requests that the applicant provide the evaluation of all components and structures relied upon to protect the safety/nonsafety interface for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. RAI2.1-8 10 CFR 54.21, "Contents of application--technical information," states, in part: (1) For those systems, structures, and components within the scope of this part, as delineated in 10 CFR 54.4, identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components: (i) That perform an intended function, as described in 10 CFR 54.4, without moving parts or without a change in configuration or properties. (ii) That are not subject to replacement based on a qualified life or specified time period. During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, selected aging management review documents and license renewal drawings, and also performed plant walkdowns.
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| The staff determined through a review of the service water aging management review documentation that the service water pump bolts were excluded from the scope of license renewal based on periodic replacement.
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| However, the aging management review documentation indicated that a visual inspection was also used to determine whether bolt replacement would be required.
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| The staff determined that the use of inspection activities to determine the need to replace a component did not meet the requirements of 10 CFR 54.21 (a}(1 )(ii), replacement based on a qualified life or specified time period. The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of service water pump bolts, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
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| The staff requests that the applicant
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| -perform a review of the issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria.
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| List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations.
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| For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
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| March 30, 2011 Mr. Barry S. Allen Vice President, Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION -SECTION 2.1 (TAC NO. ME4640)
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| ==Dear Mr. Allen:==
| | DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI2.1-1 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i), |
| By letter dated August 27,2010, First Energy Nuclear Operating Company (FENOC), submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station (DBNPS). The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the Enclosure.
| | (ii), or (iii) of this section. |
| Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by .telephone at 301-415-2277 or bye-mail at brian.harris2@nrc.gov.
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the License Renewal Application (LRA), the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant had identified safety-related components located in the turbine building. The applicant also confirmed that there are nonsafety-related structures, systems, and components (SSCs) in the vicinity of the safety-related components. The applicant had concluded that the nonsafety-related SSCs were not required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). |
| Sincerely, IRA! Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket 50-346
| | The staff requests that the applicant provide a description and the results of the evaluation that formed the basis for concluding that the nonsafety related SSCs, located within the vicinity of safety-related SSCs within the turbine building, do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-2 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i), |
| | (ii), or (iii) of this section. |
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of license renewal drawings and discussion with the applicant that for certain systems, nonsafety-related pipe attached to safety-related pipe, had not been included within the scope of license renewal. |
| | ENCLOSURE |
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| | - 2 The staff requests that the applicant provide details of the analysis performed and any conclusions related to nonsafety-related pipe, attached to safety-related pipe, for inclusion within the scope of license renewal up to and including a seismic anchor or equivalent, in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-3 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i), |
| | (ii), or (iii) of this section. |
| | During the scoping and screening methodology audit, performed on-site January 24-28,2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of license renewal drawings and discussion with the applicant that equipment that was no longer required had been placed in an abandoned state. |
| | The staff requests that the applicant provide details on the activities performed to confirm that all abandoned equipment that at any time contained fluids, and is in the proximity of safety-related SSCs, has been verified to be drained. If abandoned equipment has not been verified to be drained or is not included within the scope of license renewal, provide details of the analysis performed and any conclusions, related to the inclusion of abandoned equipment within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-4 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i), |
| | (ii), or (iii) of this section. |
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| | - 3 During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant did not include nonsafety-related relief valve drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staff's review determined that the function of a drain line is to pass fluid when required and therefore the pipe should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction. The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs. |
| | The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially 'fluid filled, nonsafety-related relief valve drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-5 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1)(i), |
| | (ii), or (iii) of this section. |
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant did not include nonsafety-related drip pans and retention area drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staffs review determined that the function of the drip pans and retention area drain lines is to contain or pass fluid when required and therefore should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction and 10 CFR 54.21. The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs. |
| | The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially fluid filled, non safety-related drip pan and |
| | |
| | -4 retention area drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. |
| | During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-6 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)( 1)(i), |
| | (ii), or (iii) of this section. |
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. During a plant walkdown, the staff observed a nonsafety-related domestic water valve and other nonsafety-related fluid filled SSCs located in the service water tunnel and in the vicinity of safety-related SSCs. |
| | The staff requests that the applicant provide a basis for not including the non-safety related components, within the vicinity of safety-related SSCs within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-7 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1)(i), |
| | (ii), or (iii) of this section. |
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. During a plant walkdown, the staff |
| | |
| | - 5 observed the nonsafety-related condensate line located in the turbine building that exited through the deck to the space below that contained the auxiliary feedwater pumps. The applicant indicated that the condensate line nonsafety-related to safety-related interface was located at a point below the turbine building deck. |
| | The staff requests that the applicant identify the specific location of the nonsafety to safety related interface and all mitigative features installed to protect the integrity of the nonsafety to safety-related interface. The staff requests that the applicant provide the evaluation of all components and structures relied upon to protect the safety/nonsafety interface for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | RAI2.1-8 10 CFR 54.21, "Contents of application--technical information," states, in part: (1) For those systems, structures, and components within the scope of this part, as delineated in 10 CFR 54.4, identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components: |
| | (i) That perform an intended function, as described in 10 CFR 54.4, without moving parts or without a change in configuration or properties. |
| | (ii) That are not subject to replacement based on a qualified life or specified time period. |
| | During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, selected aging management review documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of the service water aging management review documentation that the service water pump bolts were excluded from the scope of license renewal based on periodic replacement. However, the aging management review documentation indicated that a visual inspection was also used to determine whether bolt replacement would be required. The staff determined that the use of inspection activities to determine the need to replace a component did not meet the requirements of 10 CFR 54.21 (a}(1 )(ii), replacement based on a qualified life or specified time period. |
| | The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of service water pump bolts, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). The staff requests that the applicant |
| | |
| | - 6 perform a review of the issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects. |
| | |
| | '.. ML110820624 OFFICE: LA:DLR ! PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1:DLR NAME: YEdmonds BHarris BPham BHarris DATE: 3/29/11 3/29/11 3/30/11 3/30/11 |
|
| |
|
| ==Enclosure:==
| | Letter To: B. Allen from B. Harris dated March 30, 2011 |
|
| |
|
| As stated cc w/encl: Distribution via Listserv ADAMS Accession No'.. ML110820624 OFFICE: LA:DLR ! PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1:DLR NAME: YEdmonds BHarris BPham BHarris DATE: 3/29/11 3/29/11 3/30/11 3/30/11 OFFICIAL RECORD Letter To: B. Allen from B. Harris dated March 30, 2011 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION -SECTION 2.1 (TAC NO. ME4640) HARD COPY: DLR RF E-MAIL: PUBLIC] RidsNrrDlrResource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDIrRer1 Resource RidsNrrDIrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource B. Harris P. Cooper B. Harris (OGC) M. Mahoney}}
| | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.1 (TAC NO. ME4640) |
| | HARD COPY: |
| | DLR RF E-MAIL: |
| | PUBLIC] |
| | RidsNrrDlrResource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDIrRer1 Resource RidsNrrDIrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource B. Harris P. Cooper B. Harris (OGC) |
| | M. Mahoney}} |
Letter Sequence RAI |
|---|
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
|
MONTHYEARML11126A0882008-01-12012 January 2008
Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501
Project stage: Other
ML11126A0902008-01-15015 January 2008
Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008
Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
ML11126A0682008-05-0505 May 2008
Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System.
Project stage: Other
ML11126A0652008-08-0606 August 2008
Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System.
Project stage: Other
ML11126A0592008-10-0909 October 2008
Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection.
Project stage: Other
ML11126A0632008-10-10010 October 2008
Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1.
Project stage: Other
ML11126A0702008-10-10010 October 2008
Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2.
Project stage: Other
ML11126A0742008-11-0606 November 2008
Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System.
Project stage: Other
ML11126A0832008-12-18018 December 2008
Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501
Project stage: Other
ML11126A0712009-04-0707 April 2009
Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems.
Project stage: Other
ML11126A0892009-04-0707 April 2009
Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System.
Project stage: Other
ML1024505652010-08-27027 August 2010
License Renewal Application and Ohio Coastal Management Program Consistency Certification
Project stage: Other
ML1104500462011-02-17017 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection
Project stage: RAI
ML11126A0792011-02-25025 February 2011
Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic.
Project stage: Other
ML1104205972011-02-28028 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4
Project stage: RAI
ML1106801722011-03-17017 March 2011
Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S
Project stage: RAI
ML1107007322011-03-18018 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3
Project stage: RAI
L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011
Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1
Project stage: Response to RAI
ML11068A0002011-03-21021 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640)
Project stage: RAI
L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review of the License Renewal Application
Project stage: Response to RAI
L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review License Renewal Application
Project stage: Response to RAI
ML1108206242011-03-30030 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640)
Project stage: RAI
ML1109002952011-03-31031 March 2011
Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station
Project stage: Approval
ML1108204902011-04-0505 April 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1
Project stage: RAI
ML11110A0932011-04-15015 April 2011
Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System
Project stage: Other
ML11110A1072011-04-15015 April 2011
Drawing No. M-045, Rev. 56, Chemical Addition Systems
Project stage: Other
ML11110A1062011-04-15015 April 2011
Drawing No. M-042C, Rev. 33, Sampling System Sh. 3
Project stage: Other
ML11110A1052011-04-15015 April 2011
Drawing No. M-040A, Rev. 76, Reactor Coolant System Details
Project stage: Other
ML11110A0952011-04-15015 April 2011
Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0942011-04-15015 April 2011
Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0922011-04-15015 April 2011
Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System
Project stage: Other
L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011
Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples
Project stage: Other
L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011
Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...
Project stage: Response to RAI
ML11110A0882011-04-15015 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal
Project stage: Response to RAI
ML11110A0912011-04-15015 April 2011
Drawing No. M-011, Rev. 61, Domestic Water System
Project stage: Other
ML11110A0892011-04-15015 April 2011
Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System
Project stage: Other
ML1110500912011-04-19019 April 2011
Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application
Project stage: Other
L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4
Project stage: Response to RAI
ML1109807182011-04-20020 April 2011
Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2
Project stage: RAI
ML11126A0362011-04-29029 April 2011
Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator.
Project stage: Other
ML11126A0352011-04-29029 April 2011
Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil.
Project stage: Other
ML11126A0342011-04-29029 April 2011
Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start.
Project stage: Other
ML11126A0332011-04-29029 April 2011
Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0322011-04-29029 April 2011
Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0262011-04-29029 April 2011
Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System
Project stage: Other
ML11126A0252011-04-29029 April 2011
Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System
Project stage: Other
ML11126A0242011-04-29029 April 2011
Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System
Project stage: Other
ML11126A0192011-04-29029 April 2011
Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1
Project stage: Other
ML11126A0452011-04-29029 April 2011
Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps.
Project stage: Other
2011-02-25
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024
NRC Initial License Examination Report 05000346/2024301
IR 05000346/20230042024-01-31031 January 2024
Integrated Inspection Report 05000346/2023004
ML23313A1352024-01-17017 January 2024
Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program
ML23353A1192023-12-19019 December 2023
Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
IR 05000346/20234032023-11-0202 November 2023
Security Baseline Inspection Report 05000346/2023403
ML23293A0612023-11-0101 November 2023
Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000346/20234012023-09-13013 September 2023
Security Baseline Inspection Report 05000346/2023401 (Public)
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
IR 05000346/20230112023-08-30030 August 2023
Biennial Problem Identification and Resolution Inspection Report 05000346/2023011
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000346/20230052023-08-24024 August 2023
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005)
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
IR 05000346/20230502023-08-0303 August 2023
Special Inspection Report 05000346/2023050
IR 05000346/20230902023-08-0101 August 2023
EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public)
ML23178A2742023-08-0101 August 2023
Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
IR 05000346/20230022023-07-27027 July 2023
Integrated Inspection Report 05000346/2023002
ML23193A7842023-07-13013 July 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
ML23160A2342023-06-13013 June 2023
Confirmation of Initial License Examination
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
IR 05000346/20235012023-06-13013 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
ML23131A2732023-05-15015 May 2023
Notification of NRC Supplemental Inspection 95001 and Request for Information
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
IR 05000346/20230102023-05-0909 May 2023
Commercial Grade Dedication Inspection Report 05000346/2023010
ML23123A1272023-05-0303 May 2023
Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station
IR 05000346/20230012023-05-0101 May 2023
Integrated Inspection Report 05000346/2023001 and 07200014/2022001
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
ML23111A1972023-04-26026 April 2023
Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station
ML23114A1062023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23096A1382023-04-11011 April 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
ML23066A2892023-03-14014 March 2023
Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement
ML23066A2592023-03-14014 March 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1
2024-02-02
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
ML23193A7842023-07-13013 July 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402
ML23131A2732023-05-15015 May 2023
Notification of NRC Supplemental Inspection 95001 and Request for Information
ML23033A0322023-02-0101 February 2023
NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115)
ML22357A0302022-12-23023 December 2022
Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000346/2023010
ML22266A1102022-09-23023 September 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure
ML22214A7042022-08-0202 August 2022
Reissue - Davis-Besse Nuclear Power Station, Unit 1 Notification of Nrc Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011
ML22187A0992022-07-0606 July 2022
Notification of NRC Supplemental Inspection (95001) and Request for Information
ML22164A8572022-06-13013 June 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan
ML22118A6862022-04-28028 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval
ML22112A1092022-04-22022 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
ML22055A0872022-02-23023 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3
IR 05000346/20210912021-12-17017 December 2021
NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding
ML21321A3792021-11-16016 November 2021
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval
ML21301A0992021-10-28028 October 2021
Draft Request for Additional Information: Proposed Alternate for Examination of Steam Generator Welds - Energy Harbor Nuclear Corp., Davis-Besse Nuclear Power Station, Unit No. 1
ML21203A3252021-07-28028 July 2021
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000346/2021011
ML21155A1952021-06-0404 June 2021
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Davis Besse Nuclear Power Station
ML21041A5452021-02-10010 February 2021
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports
ML21007A3732021-01-0707 January 2021
NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff,
ML21004A1442020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff
ML20300A5592020-10-27027 October 2020
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML20154K7642020-06-0202 June 2020
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425
ML20133J9792020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML20127H8672020-05-0606 May 2020
NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
ML20021A3162020-01-21021 January 2020
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing
ML19192A2222019-07-18018 July 2019
Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19179A1382019-06-28028 June 2019
NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program
ML19164A1532019-06-13013 June 2019
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan
ML19162A3922019-06-11011 June 2019
NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications
ML19143A0732019-05-29029 May 2019
FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments
ML18305B0192018-11-0101 November 2018
18 Davis-Besse Nuclear Power Station - Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information(Rdb)
ML18201A4122018-07-19019 July 2018
NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML18190A4902018-07-0909 July 2018
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team), Inspection Report 05000346/2018011 (DRP-DXB)
ML18102B0852018-04-12012 April 2018
NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver
ML18043A0102018-02-0909 February 2018
NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans
ML17355A3722017-12-21021 December 2017
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML17303B1582017-11-0707 November 2017
FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information
ML17257A1402017-09-14014 September 2017
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
ML17135A3612017-05-12012 May 2017
Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000346/2017010 (Jvb)
ML17129A4112017-05-0909 May 2017
Request for Additional Information Regarding Evaluation Submitted in Response to License Renewal Commitment No. 54
ML17100A1732017-04-19019 April 2017
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805
ML16364A2792017-01-23023 January 2017
Request for Additional Information Regarding License Renewal Commitment No. 42
ML16355A0352016-12-19019 December 2016
Ltr 12/19/16 Davis-Besse Nuclear Power Station, Unit 1 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000346/2017009 (Bxj)
ML16256A0662016-10-18018 October 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805
ML16196A0152016-07-22022 July 2016
Request for Additional Information Regarding Amendment Request to Revise Emergency Action Level Scheme
L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-06-24024 June 2016
Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML16060A0122016-02-29029 February 2016
FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120
ML16047A1452016-02-22022 February 2016
Supplemental Information Needed for Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805
ML16019A3972016-01-20020 January 2016
Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements
ML15222A1792015-09-21021 September 2015
Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements (TAC No. MF6060)(L-15-117)
2023-07-13
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 March 30. 2011 Mr. Barry S. Allen Vice President, Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449 SUB.JECT: REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.1 (TAC NO. ME4640)
Dear Mr. Allen:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company (FENOC). submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (1 0 CFR Part 54) for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station (DBNPS).
The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions.
please contact me by telephone at 301-415-2277 or bye-mall at brian.harris2@nrc.gov sincere: /~
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Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
As stated cc w/encl: Distribution via Listserv
DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI2.1-1 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the License Renewal Application (LRA), the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant had identified safety-related components located in the turbine building. The applicant also confirmed that there are nonsafety-related structures, systems, and components (SSCs) in the vicinity of the safety-related components. The applicant had concluded that the nonsafety-related SSCs were not required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
The staff requests that the applicant provide a description and the results of the evaluation that formed the basis for concluding that the nonsafety related SSCs, located within the vicinity of safety-related SSCs within the turbine building, do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-2 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of license renewal drawings and discussion with the applicant that for certain systems, nonsafety-related pipe attached to safety-related pipe, had not been included within the scope of license renewal.
ENCLOSURE
- 2 The staff requests that the applicant provide details of the analysis performed and any conclusions related to nonsafety-related pipe, attached to safety-related pipe, for inclusion within the scope of license renewal up to and including a seismic anchor or equivalent, in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-3 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28,2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of license renewal drawings and discussion with the applicant that equipment that was no longer required had been placed in an abandoned state.
The staff requests that the applicant provide details on the activities performed to confirm that all abandoned equipment that at any time contained fluids, and is in the proximity of safety-related SSCs, has been verified to be drained. If abandoned equipment has not been verified to be drained or is not included within the scope of license renewal, provide details of the analysis performed and any conclusions, related to the inclusion of abandoned equipment within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-4 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1 )(i),
(ii), or (iii) of this section.
- 3 During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant did not include nonsafety-related relief valve drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staff's review determined that the function of a drain line is to pass fluid when required and therefore the pipe should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction. The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs.
The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially 'fluid filled, nonsafety-related relief valve drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-5 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1)(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined that the applicant did not include nonsafety-related drip pans and retention area drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staffs review determined that the function of the drip pans and retention area drain lines is to contain or pass fluid when required and therefore should be included within the scope of license renewal and subject to aging management review in accordance with 10 CFR 54.4 (a)(2) for spatial interaction and 10 CFR 54.21. The staff further determined that following inclusion of the drain lines within the scope of license renewal, the applicant's aging management review will allow for the evaluation of material and environment combinations to identify aging effects and the suitability of aging management programs.
The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of the potentially fluid filled, non safety-related drip pan and
-4 retention area drain lines, located within the vicinity of safety-related SSCs, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-6 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)( 1)(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. During a plant walkdown, the staff observed a nonsafety-related domestic water valve and other nonsafety-related fluid filled SSCs located in the service water tunnel and in the vicinity of safety-related SSCs.
The staff requests that the applicant provide a basis for not including the non-safety related components, within the vicinity of safety-related SSCs within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction. During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-7 10 CFR 54.4(a)(2) states: (a) Plant systems, structures and components within the scope of this part are (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the [safety-related] functions identified in (a)(1)(i),
(ii), or (iii) of this section.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. During a plant walkdown, the staff
- 5 observed the nonsafety-related condensate line located in the turbine building that exited through the deck to the space below that contained the auxiliary feedwater pumps. The applicant indicated that the condensate line nonsafety-related to safety-related interface was located at a point below the turbine building deck.
The staff requests that the applicant identify the specific location of the nonsafety to safety related interface and all mitigative features installed to protect the integrity of the nonsafety to safety-related interface. The staff requests that the applicant provide the evaluation of all components and structures relied upon to protect the safety/nonsafety interface for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). During the review of this issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a)(2) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
RAI2.1-8 10 CFR 54.21, "Contents of application--technical information," states, in part: (1) For those systems, structures, and components within the scope of this part, as delineated in 10 CFR 54.4, identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components:
(i) That perform an intended function, as described in 10 CFR 54.4, without moving parts or without a change in configuration or properties.
(ii) That are not subject to replacement based on a qualified life or specified time period.
During the scoping and screening methodology audit, performed on-site January 24-28, 2011, the staff reviewed the LRA, selected aging management review documents and license renewal drawings, and also performed plant walkdowns. The staff determined through a review of the service water aging management review documentation that the service water pump bolts were excluded from the scope of license renewal based on periodic replacement. However, the aging management review documentation indicated that a visual inspection was also used to determine whether bolt replacement would be required. The staff determined that the use of inspection activities to determine the need to replace a component did not meet the requirements of 10 CFR 54.21 (a}(1 )(ii), replacement based on a qualified life or specified time period.
The staff requests that the applicant provide details of the analysis performed and any conclusions, related to the review of service water pump bolts, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). The staff requests that the applicant
- 6 perform a review of the issue, consider extent of condition, and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
'.. ML110820624 OFFICE: LA:DLR ! PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1:DLR NAME: YEdmonds BHarris BPham BHarris DATE: 3/29/11 3/29/11 3/30/11 3/30/11
Letter To: B. Allen from B. Harris dated March 30, 2011
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.1 (TAC NO. ME4640)
HARD COPY:
DLR RF E-MAIL:
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