Letter Sequence Request |
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Results
Other: CNL-14-201, Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report, CNL-15-174, Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request, CNL-15-214, Updated Pages for As-Constructed Fire Protection Report, ML12207A080, ML13051A045, ML13081A002, ML13081A003, ML14265A449, ML15175A508
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MONTHYEARML1015401332010-06-10010 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Accident Dose Project stage: RAI ML1015402502010-06-24024 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091) Project stage: RAI ML1016002782010-07-12012 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Accident Dose Project stage: RAI ML11129A1582011-05-0606 May 2011 Request for Additional Information Regarding Fire Protection Report, Project stage: Request ML1115201192011-05-26026 May 2011 Response to Request for Additional Information Regarding Fire Protection Report. Project stage: Response to RAI ML1120303872011-07-27027 July 2011 Request for Additional Information Regarding Incore Instrumentation System Project stage: RAI ML11215A1322011-07-29029 July 2011 Response to Request for Additional Information Regarding June 28, 2011 NRC Audit- Steam Line Break (Slb) and Other Miscellaneous RAIs Project stage: Response to RAI ML11227A2572011-08-0505 August 2011 Request for Additional Information (RAI) Group 6 Regarding Fire Protection Report Project stage: Request ML11230A3852011-08-15015 August 2011 Transmittal of Revised Unit 1 / Unit 2 As-Designed Fire Protection Report Project stage: Request ML13060A2252011-09-30030 September 2011 Response to Request for Additional Information Group 7 Regarding Fire Protection Report, (TAC No. ME3091) (Public Version) Project stage: Response to RAI ML11286A0382011-09-30030 September 2011 OL - Draft RAIs on Fire Protection - Group 8 Project stage: Request ML11286A0352011-09-30030 September 2011 OL - Additional Draft RAI on Fire Protection - Group 8 Project stage: Request ML11306A0902011-10-28028 October 2011 Response to Request for Additional Information Group 8 Regarding Fire Protection Report Project stage: Response to RAI ML1207905812012-03-23023 March 2012 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1, Fire Protection Group 8 Project stage: RAI ML12142A0262012-05-17017 May 2012 OL - Request for Additional Information Regarding Fire Protection Review Group 10 Project stage: RAI ML12153A3742012-05-30030 May 2012 Watts, Unit 2, Response to Request for Additional Information Project stage: Response to RAI ML12163A0532012-06-0707 June 2012 OL - Request for Additional Information on Fire Protection Project stage: RAI ML12179A1692012-06-25025 June 2012 OL - Draft Need for Information on Fire Protection Report Project stage: Request ML12181A5312012-06-27027 June 2012 Resolution of Concerns with Fire Protection Report (Fpr) Operator Manual Action (OMA) 732 and Response to Requests for Additional Information Project stage: Response to RAI ML12207A0802012-07-19019 July 2012 Resolution of Concerns with Fire Protection Report Operator Manual Action 732 - Commitment Schedule Update Project stage: Other ML13051A0452013-02-14014 February 2013 Updated Response to NRC Bulletin 2011-01, Mitigation Strategies Project stage: Other ML13081A0042013-03-13013 March 2013 Transmittal of Revised Unit 1/Unit 2 As-Designed Fire Protection Report Project stage: Request ML13081A0032013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 2 of 2 Project stage: Other ML13081A0022013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 1 of 2 Project stage: Other CNL-14-022, Withdrawal of Application to Update Watts Bar Unit 1 License Condition 2.F to Allow Two-Unit Operation (WBN-TS-13-18)2014-02-18018 February 2014 Withdrawal of Application to Update Watts Bar Unit 1 License Condition 2.F to Allow Two-Unit Operation (WBN-TS-13-18) Project stage: Withdrawal ML14265A4492014-09-18018 September 2014 Watts Bar, Unit 2 - Transmittal of Unit 1/Unit 2 As-Constructed Fire Protection Report Project stage: Other CNL-14-201, Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report2014-10-27027 October 2014 Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report Project stage: Other CNL-14-235, Transmittal of Part V of the Unit 1/Unit 2 Fire Protection Report2015-01-0909 January 2015 Transmittal of Part V of the Unit 1/Unit 2 Fire Protection Report Project stage: Request ML15175A5082015-06-24024 June 2015 Watts Bar, Unit 2 - Transmits Unit 1/Unit 2 As-Constructed Fire Protection Report (TAC No. ME3091) Project stage: Other CNL-15-174, Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request2015-08-27027 August 2015 Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request Project stage: Other CNL-15-214, Updated Pages for As-Constructed Fire Protection Report2015-10-0707 October 2015 Updated Pages for As-Constructed Fire Protection Report Project stage: Other 2012-05-30
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Category:E-Mail
MONTHYEARML24309A0552024-11-0101 November 2024 NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5 ML24304A3752024-10-29029 October 2024 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Watts Bar Updated Final Safety Analysis Report (UFSAR) for Hydrologic Analysis ML24274A2762024-09-24024 September 2024 Email from K.Green to S.Hughes, Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, Hydrologic LAR to Revise the UFSAR ML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24215A3152024-07-24024 July 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-276-A, Revision 2 TS 3.8.1, AC Sources ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24157A3152024-06-0303 June 2024 2024 Sequoyah Commercial Grade Dedication Inspection Information Request ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24156A0062024-05-22022 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Recapture Low-Power Testing Time ML24130A0132024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.11 for MCR Chiller Completion Time ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24082A0662024-04-17017 April 2024 Email to Stuart Rymer on Exemption Decision for Watts Bar ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24082A0682024-04-10010 April 2024 Email to Stuart Rymer Re_ Availability of EA-FONSI for Watts Bar ML24100A8392024-04-0909 April 2024 Response from State of Tn Regarding Review of Environmental Assessment for Watts Bar Exemption Request ML24100A8402024-04-0808 April 2024 Email to State of Tn Requesting Review of Environmental Assessment for Watts Bar Exemption Request ML24071A0982024-03-0707 March 2024 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate ML24058A0962024-02-26026 February 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant License Amendment Request to Revise UFSAR for Hydrologic Analysis ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24033A0562024-02-0101 February 2024 NRR E-mail Capture - Correction Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-427-A, Revision 2 Regarding Degraded Barriers ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 2024-09-24
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Text
WBN2Public Resource From: Poole, Justin Sent: Friday, September 30, 2011 9:08 AM To: Arent, Gordon; Bryan, Robert H Jr Cc: Milano, Patrick; WBN2HearingFile Resource
Subject:
DRAFT RAIs on Fire Protection - Group 8 Attachments: WBN group 8 RAIs.docx
- Gordon, In reviewing the latest fire protection report, the staff has come up with the attached questions. Please review to ensure that the RAI questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. If further clarification is needed, and you would like to discuss the questions in a conference call, let us know. Please also let me know how much time Tennessee Valley Authority (TVA) needs to respond to the RAI questions.
This email does not convey a formal NRC staff position, and it does not formally request for additional information.
Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov 1
Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 538 Mail Envelope Properties (19D990B45D535548840D1118C451C74DA9DDA112BD)
Subject:
DRAFT RAIs on Fire Protection - Group 8 Sent Date: 9/30/2011 9:08:25 AM Received Date: 9/30/2011 9:08:29 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:
"Milano, Patrick" <Patrick.Milano@nrc.gov>
Tracking Status: None "WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>
Tracking Status: None "Arent, Gordon" <garent@tva.gov>
Tracking Status: None "Bryan, Robert H Jr" <rhbryan@tva.gov>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 835 9/30/2011 9:08:29 AM WBN group 8 RAIs.docx 26535 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION OPERATING LICENSE APPLICATION WATTS BAR, UNIT 2 DOCKET NO.: 50-391 TAC NO.: ME3091 Office of Nuclear Reactor Regulation Division of Risk Assessment Fire Protection Branch
- A number of the information requests may involve modifications to the fire protection report (FPR). This status is indicated at the end of the specific requests.
- References to the FPR refer to the August 2011 as-designed version of that document.
RAI number format Example: [RAI FPR V-1]
RAI - RAI FPR - topic or document from which the comment originates V - Section of the document Sequential comment for that section RAI FPR I-4 The separation requirements of Appendix R to 10 CFR 50 are applicable in areas containing redundant trains of fire safe shutdown (FSSD) equipment or cables. However, this information does not appear to be readily available in the FPR in an easily identifiable format. For instance, Table I-1 indicates which rooms contain safe shutdown equipment but does not indicate whether these rooms contain credited or redundant trains of equipment or both. Additionally, Part III, Section 10.3.1, of the FPR states that TVA performed an evaluation for each analysis volume to ensure compliance with Appendix R Section III.G.2.
Identify all rooms and analysis volumes containing redundant trains of FSSD equipment or cables and state whether they comply with the requirements contained in Section III.G.2 of Appendix R. Where explicit compliance is not provided, describe the method used to achieve an equivalent level of protection to that intended by Appendix R. Include a description of the spatial separation between redundant trains, proximity to in situ and transient combustibles, automatic fire detection and suppression systems, and installed fire barriers.
RAI FPR IV-5 Part VI of the FPR lists alternate shutdown operator manual actions for a fire in Fire Area 48.
The feasibility criteria for these manual actions are not explicitly described in Part IV, Alternate Shutdown Capability. Part V, Manual Actions, Repairs, and Emergency Lighting, Section 2.1.2, does include operator manual action acceptance criteria, but it is not clear to the staff reviewers that alternate shutdown operator manual actions are included in that review.
Confirm that operator manual actions for alternate shutdown have been evaluated using the feasibility and reliability analysis criteria in Section 2.1.1 of Part V, and that the evaluation used
the acceptance criteria in Section 2.1.2 of Part V. Also, confirm that the walk downs described in Section 2.2.1 of Part V have been performed for alternate shutdown operator manual actions and that the timing of those walkdowns has considered that the control room operators will need to travel from the Main Control Room to the Auxiliary Control Room as part of the timeline.
If the above confirmations cannot be provided, provide a description of the feasibility criteria for operator manual actions performed for alternative shutdown. The discussion should confirm that these operator manual actions have been walked down and confirm that travel time from the Main Control Room to the Auxiliary Control Room has been considered.
RAI FPR V-17 Part V, Section 2.2, item 5, states, For a fire located in the control building . . ., notify Appendix R AUOs to report to the control room . . . Section 2.2.2 states that operators performing manual actions are dispatched, . . . from the Auxiliary Control Room for Control Building fires.
Confirm that the statement in Section 2.2.2 is the appropriate statement. If not, provide an explanation of how Appendix R AUOs are assured access to the control room since access to the control room could be impeded by fire, fire products, or gaseous suppression system actuation.
In either case, correct the inconsistency.
RAI FPR VII-27 Part VII, Section 6.2 Justification for Fire Damper Surveillance Requirements, of the FPR states that the surveillances cannot be performed because of ALARA concerns. Examination of Part VI, Section 3.22.1, indicates that these dampers are in ducts that connect rooms 737.0-A5 and 737.0-A1 (damper 0-ISD-31-3846) or rooms 737.0-A5 and 729.0-A6 (dampers 0-ISD 3847 and 0-ISD-31-3828). None of these three rooms is on the list of inaccessible high radiation areas in Part II of the FPR.
- 1. More clearly describe the nature of the ALARA concern for performing these surveillances.
- 2. The descriptions of the locations of the fire dampers are confusing. More clearly describe the physical location of the dampers. For example, are they located in the wall of room 737.0-A5?
- 3. Where is the collector box identified as the start of the duct in Section 6.2.2.1 located? For example, is it in the wall of the fuel transfer canal?
- 4. Is the fuel transfer canal (Section 6.2.2.1) the same location as the Spent Fuel Pit (Section 6.2.2.2)?
- 5. Is the large (64 inch by 54 inch) duct mentioned for each of the three dampers the same duct?
- 6. Examination of Part VI, Section 3.22.1 reveals other dampers (specifically -3845 and -3849) that superficially match those that are evaluated in Section 6.2. Confirm that all of the dampers covered by the ALARA concern identified in Section 6.2 have been evaluated.
- 7. The evaluations in Section 6.2 seem to be focused on Unit 1 (room 737.0-A5 is the Unit 1 Ventilation and Purge Air Room). Will there be a corresponding Unit 2 evaluation? If so, when will that be submitted to the NRC?
It would be appropriate to modify the FPR to incorporate the answer to this RAI.
RAI FPR VII-28 Part VII, Section 2.7, of the FPR indicates that the hand-held portable lanterns, provided in lieu of installed emergency lights, are dedicated and maintained.
Provide the methods used to ensure that the portable lanterns are dedicated for manual actions in containment and for other post-fire manual actions. Additionally, provide the methods used to maintain the lanterns to ensure that they will provide sufficient lighting for operators to perform the manual actions.
RAI FPR VII-29 The evaluation of penetration seal surveillance requirements in Part VII, Section 6.4.2.3, of the FPR, states that there is no safe shutdown equipment in the Waste Holdup Tank Room. This appears to contradict Table I-1 and Section 3.1.1 of Part VII, which indicate that there is safe shutdown equipment installed in this room.
Resolve this apparent conflict.
RAI FPR VII-30 Part VII, Section 4.3 Manual Hose Stations, of the FPR, states that hose stations that are equipped with more than 100 feet of hose have had their pressure tested at the standpipe to compensate for additional lengths of hose. The implication is that the static pressure was tested at the standpipe, not the more appropriate dynamic pressure.
Provide a description of how TVA assures that the sufficient flow and pressure is available at the nozzles for these extended lengths of hose for fire fighting purposes.
Additionally, for each of the hose stations with these longer hoses, identify the rooms or portions of rooms that each hose station is relied upon to protect.
RAI FPR VII-31 Part VII, Section 2.6.3.2.b, of the FPR, states, in part: Sheet metal ducts that are not provided with fire dampers are identified on the Fire Compartmentation drawings (see Part II of this Report). They are constructed of minimum 22 gauge sheet metal and will provide a 1-hour
equivalent level of protection. Similar statements are made in sections 6.2.2.1 and 6.2.2.2 of Part VII.
Provide a technical basis for the claimed fire endurance rating for sheet metal ducts.
RAI FPR VII-32 Part VII, Section 3.2, of the FPR, states, in part: A flexible connection is provided between the purge air duct and the embedded containment duct penetration. The flexible connection is protected with 3M M20A fire barrier mat to give a 3-hour rating to the connection.
Provide a technical basis for the fire endurance rating for the sheet metal ducts. For example, is this a tested configuration?
RAI FPR VII-33 Section 3.1.2 of Part VII of the FPR states that portions of Room 713.0-A1 lack automatic fire suppression but then the discussion for this deviation appears to credit an automatic suppression system in the immediate vicinity of the area.
Justify the statement that automatic suppression in nearby areas will serve as a form of suppression for an unprotected area and explain how this is consistent with the underlying purpose of the rule.
RAI FPR X-5 Part X of the FPR states that CO2 systems were evaluated against NFPA-12, 1973 Edition, and then discusses any deviations that might exist. However, the FPR does not discuss the fact that several of the rooms protected by these systems have doors installed to swing in the direction of discharge. For instance, the diesel generator rooms have double doors that swing out of the rooms.
Confirm that all door assemblies for rooms containing gaseous suppression systems have been designed, installed, and tested in accordance with the appropriate design standards, or otherwise evaluated, to ensure that appropriate concentrations and soak times can be achieved and maintained for the systems to perform as intended.