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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
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Text
NRR-PMDAPEm Resource From: Minarik, Anthony Sent: Monday, April 13, 2015 7:47 AM To: Bryan, Robert H Jr (rhbryan@tva.gov)
Cc: Arent, Gordon (garent@tva.gov); Poole, Justin; Dion, Jeanne
Subject:
Questions from EICB on Draft Test Plan (Closure of HH-083)
Attachments: HH-083 Questions from NRC-EICB WBN U2 4-13-2015.docx
- Bob, Please see the attached document with detailed questions from EICB on the draft Test Plan submitted by TVA.
Anthony Minarik 301-415-6185 Office of Nuclear Reactor Regulation (NRR)
Division of Operating Reactor Licensing (DORL)
Watts Bar Special Projects Branch (LPWB)
Normal Hours:
0600-1545: Mon-Fri 1
Hearing Identifier: NRR_PMDA Email Number: 1994 Mail Envelope Properties (Anthony.Minarik@nrc.gov20150413074600)
Subject:
Questions from EICB on Draft Test Plan (Closure of HH-083)
Sent Date: 4/13/2015 7:46:59 AM Received Date: 4/13/2015 7:46:00 AM From: Minarik, Anthony Created By: Anthony.Minarik@nrc.gov Recipients:
"Arent, Gordon (garent@tva.gov)" <garent@tva.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "Dion, Jeanne" <Jeanne.Dion@nrc.gov>
Tracking Status: None "Bryan, Robert H Jr (rhbryan@tva.gov)" <rhbryan@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 342 4/13/2015 7:46:00 AM HH-083 Questions from NRC-EICB WBN U2 4-13-2015.docx 34034 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
NRR/DE/EICB Comments Regarding Closure of Open Item 83 in Watts Bar Unit 2 Safety Evaluation Report NUREG-0847,Supplement 23 In Supplement 23 of NUREG-0847(ADAMS Accession No. ML1206A499), TVA was to confirm to the NRC the completion of a data storm test on the DCS. This was identified as Open Item
- 83. Per Section 7.7 of the Standard Review Plan, the NRC staff is directed to perform an evaluation of the effects of control system failures on plant safety. The review is required to confirm that the failure of any control system component or any auxiliary supporting system for control systems does not cause plant conditions more severe than those described in the analysis of anticipated operational occurrences in Chapter 15 of the SAR. One aspect of control system failure of concern is the potential for a failure within a data communications network that is connected to multiple control systems. It may be possible for such a failure to simultaneously prevent two or more control systems from properly functioning in such a manner that results in the plant being put into a condition that has not been previously analyzed in the SAR. TVA has proposed to conduct a network data storm test to confirm that the control systems associated with the functions described in FSAR Section 7.7.1.11.1 will continue to perform their required control functions with a failed communication network without any plant upset.
In order for the staff to close Open Item 83, the staff needs to understand the benefits and limitations of any testing that is performed to demonstrate that it is not possible (or very unlikely) for a data communications fault occurring on a common control system network to simultaneously prevent two or more control systems from properly functioning in such a manner that results in the plant being put into a condition that has not been previously analyzed in the SAR. With regard to the draft test procedure provided by TVA to date, the staff has additional questions to aid in its understanding of the test that has been proposed.
- 1) TVA is requested to provide a copy of thedata storm test plan, which establishes the requirements, general methodology, test objectives, and acceptance criteria for the test.
The plan should provide the reasons why the proposed test procedure will conclusively demonstrate the objectives of the test are satisfied. There should be a descriptionof the required analysis of the test data resulting from performance of the testthat would support(or how it may not support) the final conclusion.The test plan information should also include these specific objectives:
- a. How the results will support the segmentation analysis and, particularly, the conclusion that the events listed in NUGEG-0847, Section 7.7.1.4.4.1, items (1) through (8),will not be caused by the propagation of failures. Also confirmation should be provided that the failures of one control processor (CP) pair are limited to outputs failing high, low, or as is.
- b. NUREG-0847 also states that: The test will demonstrate conformance toClause 6.3 of IEEE Std. 603-1991 by proving that the Foxboro I/A mesh will not propagate failures from one segment to another and cause a plant upset. The test then shall specifically stateClause 6.3 of IEEE Std. 603-1991 is met and the Page 1 of 4
propagation of failures does not take place beyond the Foxboro I/A meshnetwork from one segment to another.
- c. Finally, the test should confirm that a failed communication network, which includes consideration of the effects of both network action and inaction, will permit the system to continue to function and will not cause plant conditions more severe or not previously identified in the analysis of anticipated operational occurrences in Chapter 15 of the SAR.
- 2) The NRC staff requests anetwork diagram that depicts the associated control system workstations, switches, firewalls, and connectivity of the following systems on the control network:
- a. Feedwater Flow/Steam Generator Level Control System
- b. Feedpump Turbine Speed Control system
- c. Condenser Steam Dump valve/loss of load interlock controls
- d. Atmospheric steam dump valve controls
- e. SG PORV controls
- f. Pressurizer Pressure, Level, charging, letdown spray, cold overpressure mitigation controls
- g. Auxiliary Control system
- 3) The NRC staff also requests a table that relates the associated switches and ports to the names of the control systems listed above would be very helpful in understanding the procedure supplied.
- 4) See specific comments ATTACHMENT 1: Comments to WBN U2 Foxboro I/A Network Storm Test, Procedure No. ?,
Page 2 of 4
ATTACHMENT 1 Comments to:
WBN U2 Foxboro I/A Network Storm Test Procedure No.?
DRAFT General Comments:
- 1) In each of the Broadcast and Multicast tests, the description reads This test will verify system performance and data is recorded but no acceptance criteria is identified for the generated or destination network traffic at the given ports.
- 2) Only Test 6.5, Aux Control Room CP Broadcast Storm Testing, makes a statement that would be considered a test objective. That test states: This test will verify that the broadcast limit settings for the FCPs and WSs are functioning correctly. The remaining tests should identify a similar specific objective.
- 3) Also, each of these tests say to document system performance observed (e.g.
Workstation __ Normal ___ Smurf). It is not clear what type of entry is required. Is it a matter of simple acceptance or if data is requested to be entered in those spaces.
- 4) Specific Comments:
Comment Section Description Comment
- a. All Sections Acceptance Criteria With the exception of verifying the 0-Comment on 100% in X seconds, there are no test adequate testing requirements or requirements acceptance criteria identified in the and criteria procedure. Where will these be described?
- b. Attachments/ Lists 7 items in this Only Attachments 1, 2 & 3 are Forms category included.
- c. 5. Special Tools Test Indicator; Further information is necessary on
& Equipment 0 - 100% scale what this equipment is. (e.g., name, inputs, what it measures etc.).
- d. 5. Special Tools Network Sniffer - PC If Ethereal is installed, the libpcap
& Equipment with Ethereal or packet capture library software Wireshark installed should be or may already be installed. However, it is not clear if the intent is to simply capture packet information, but rather what to check for.
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Comment Section Description Comment
- e. 6.1.1.11 Test Obtain printout of Wireshark captures packets and lets Step CP6TEST compound you examine their contents. It is not and blocks and attach clear what the test is requesting or in Attachment 3 what the inspection criteria are.
- f. 6.1.1.13 Test Verify that the output What is the intent of identifying X Step from W20614 CH 8 seconds? Is this to be determined sweeps from 0-100% later? How will this be determined?
in approx. X seconds. How was the value for X determined? Is it different for different components?
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