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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MONTHYEARML1001916862010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 8 - Electric Power Through 8E-12 Project stage: Request ML1015401332010-06-10010 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 ML11286A0352011-09-30030 September 2011 OL - Additional Draft RAI on Fire Protection - Group 8 Project stage: Request ML11286A0382011-09-30030 September 2011 OL - Draft RAIs 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 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 ML13081A0042013-03-13013 March 2013 Transmittal of Revised Unit 1/Unit 2 As-Designed Fire Protection Report Project stage: Request 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 2012-05-17
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Category:E-Mail
MONTHYEARML24022A2592024-01-22022 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 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) 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) 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 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22081A2222022-03-22022 March 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 1, License Amendment Request to Revise Allowable Value for TS Table 3.3.2-1, Function 6.e(1) ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML22131A1902022-02-23023 February 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Request to Revise the Reactor Vessel Surveillance Capsule Withdrawal Schedule ML22046A0392022-02-15015 February 2022 NRR E-mail Capture - Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22011A0382022-01-10010 January 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A ML21306A2452021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level ML21223A2592021-08-11011 August 2021 Affidavit - Prop Slides - Partially Closed Meeting with TVA Potential Watts Bar, Unit 2 Tube Locking LAR ML21221A2602021-08-0909 August 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary ML21215A1152021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21215A1142021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21197A0452021-07-15015 July 2021 WBN U1 Isi/Sgisi Request for Information (RFI) Letter ML21193A2422021-07-12012 July 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 2 Technical Specifications Related to Steam Generator Inspection/Repair Program Provisions ML21189A0202021-06-29029 June 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specifications 3.3.6 and 3.3.7 Re Radiation Monitor Redundant Unit of Measure 2024-01-22
[Table view] |
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.