ML102571774

OL - FW: Open Items List to Be Sent to TVA (Word Version)

ML102571774
Person / Time
Site:	Watts Bar
Issue date:	09/10/2010
From:	Office of Nuclear Reactor Regulation
To:	Division of Operating Reactor Licensing
References
Download: ML102571774 (83)

Text

WBN2Public Resource From: Poole, Justin Sent: Friday, September 10, 2010 4:13 PM To: Crouch, William D Cc: WBN2HearingFile Resource

Subject:

FW: Open Items List to be sent to TVA (Word version)

Attachments: 20100910 Open Items List Master.docx; image003.jpg FYI Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Darbali, Samir Sent: Friday, September 10, 2010 4:04 PM To: Poole, Justin; Bailey, Stewart Cc: Carte, Norbert; Garg, Hukam; Singh, Gursharan; Marcus, Barry; Halverson, Derek; Kemper, William

Subject:

Open Items List to be sent to TVA (Word version)

All, Attached is the Word 2007 version (.docx) of the Open Item matrix to be sent to TVA. As always, wait until we receive TVAs comments before editing the file on the G drive. The following are some things that are new in the word version:

1- Both Open and Closed items are in the same file. Closed items are shaded in gray (25% shade).

2- Items 1 thru 99 are now 001 thru 099. I had to do this so that they could be sorted properly when using the sort function.

3- There are two new columns: SE Section and FSAR Section. Lets try to fill these cells after we receive TVAs version, but before sending the list next Friday.

4- When editing the Status/Current Actions and Resolution Path columns, the first thing that should be written is Open or Closed, as applicable. This will help sort the items.

5- Currently, I have not found a way to filter rows in Word, so sorting is the only way to see your items together. If anybody knows how to use the filter option in Word, please let me know.

To sort your items:

1- Click anywhere in the table 2- On top toolbar, next to the file title, there should be a yellow sign titled Table Tools 3- Click on the Layout tab under it 4- On the far right there should be a box called Data 5- Click on the Sort Icon. The Sort menu will open.

6- First select Sort By: NRC POC 7- Then By: Status/Current Actions, and select descending to see Open Items first (ascending if you want to see Closed items first) 8- Then By: No.

9- Click Ok 1

10- The first items shown will be DORLs 11- To return to the original sorting, just Sort By: No.

If you have any questions, please let me know.

Samir Darbali Electronics Engineer NRR/DE/EICB Room: O9D11 3014151360 2

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 93 Mail Envelope Properties (19D990B45D535548840D1118C451C74D67862C60BB)

Subject:

FW: Open Items List to be sent to TVA (Word version)

Sent Date: 9/10/2010 4:12:45 PM Received Date: 9/10/2010 4:12:48 PM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:

"WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>

Tracking Status: None "Crouch, William D" <wdcrouch@tva.gov>

Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 2288 9/10/2010 4:12:48 PM 20100910 Open Items List Master.docx 245981 image003.jpg 49487 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 001 11/19/2009 12/15/2009 Presentation Slides Closed Closed November 19, 3/12/2010 NNC 11/19/09: The FSAR contains EICB (Carte) 2010 mostly description of the function that The Watts Bar Nuclear Plant FSAR red-line for Unit 2 This item was partially addressed during the Date: 3/15/2010 ML093230343 the various TVA systems must (Agency wide Documents Access and Management December 15, 2009 meeting. RAI 1 perform. Therefore this question was System Accession Number ML080770366) lists changes RAI response received. asked to determine how the systems to the Unit 1 FSAR and depicts how Chapter 7 of the Unit TVA Letter Dated March 12, 2010 (Enclosure 1, Item have been changed.

2 FSAR will appear at fuel load. Have additional changes No. 1 on Page 1 of 15): TVA responded to this been made to Chapter 7 of the Unit 2 FSAR beyond those request for additional Information. NNC 4/15/10: The response indicated in ML080770366? Which of the changes addresses many systems and should identified correspond to digital instrumentation and be read by all EICB reviewers.

controls (I&C) components and systems that have not been previously reviewed and approved by the NRC?

002 11/19/2009 12/15/2009 Presentation Slides Closed Closed November 19, 3/12/2010 NNC 11/19/09: The FSAR contains EICB (Carte) 2010 mostly description of the function that Are there I&C components and systems that have This item was partially addressed during the Date: 3/15/2010 ML093230343 the various TVA systems must changed to a new or different digital technology without the December 15, 2009 meeting. RAI 2 perform. Therefore this question was change being reflected in the FSAR markup? Are there TVA Letter Dated March 12, 2010 (Enclosure 1, Item RAI response received. asked to determine how the systems any not-redlined I&C components and systems that have No. 2 on Page 2 of 15): TVA responded to this have been changed.

been changed or replaced by digital base technology since request for additional Information. NNC 4/15/10: The response Unit 1 was approved? addresses many systems and should be read by all EICB reviewers.

003 11/19/2009 12/15/2009 Presentation Slides Closed Closed November 19, 3/12/2010 NNC 11/19/09: The FSAR contains EICB (Carte) 2010 mostly description of the function that Because a digital I&C platform can be configured and This item was partially addressed during the Date: 3/15/2010 ML093230343 the various TVA systems must programmed for different applications, the review process December 15, 2009 meeting. RAI 3 perform. Therefore this question was can be divided between a review of the platform and a TVA Letter Dated March 12, 2010 (Enclosure 1, Item RAI response received. asked to determine how the systems review of the application. For planning and scheduling No. 3 on Page 2 of 15): TVA responded to this have been changed.

reasons, it is important to know beforehand which platform request for additional Information. NNC 4/15/10: The response has been used in each digital component and system. addresses many systems and should What is the base platform of each unreviewed digital I&C be read by all EICB reviewers.

component and system (e.g., Common Q)?

004 11/19/2009 Responder: Webb 1/13/10 Public Meeting Open Open November 19, January 13, NNC 11/19/09: LIC-110 Rev. 1 EICB (Carte) 2010 2010 Section 6.2.2 states: "Design features Please identify the information that will be submitted for TVA identified a schedule for docketing some Post Date: 3/15/2010 Responsibility: TVA to docket a D3 ML093230343 March 12, and administrative programs that are each unreviewed digital I&C system and component and Accident Monitoring System (PAMS) documentation, NRC (All) and TVA (Hilmes) analysis for the RAI 4 2010 unique to Unit 2 should then be the associated docketing schedule. and the new setpoint methodology. No other Common Q PAMS. June 30, reviewed in accordance with current documentation was discussed. TVA to address the question of 2010 staff positions.TVA will supply a how a Foxboro IA common NNC 8/19/10: TVA August 11, description of the changes Add: By letter dated June 30, 2010, TVA docketed mode or complete failure segmentation 2010 implemented at Unit 1 but have not WNA-LI-00058-WBT-P &-NP, "PAMS Licensing impacts the plant accident analysis has been been reviewed for Unit 2 by the NRC Technical Report." WNA-LI-00058-WBT-P Section analysis as described in Chapter received - NRC to technical staff...TVA will also provide 4.11 addressed CCF and BTP 7-19. 15 of the FSAR. (Demonstrate review. the applicable portion of the FSAR segments are independent and and the proposed TSs...In addition, TVA Letter Dated March 12, 2010 (Enclosure 1, Item how a common mode or the staff should review items that are No. 4 on Page 3 of 15): TVA responded to this complete failure is prevented by identical for WBN Units 1 and 2 that request for additional Information power supply design and have not previously been reviewed segmentation.) and approved by the NRC staff.

Foxboro I/A Segmentation Analysis Calculation These items are changes in the DCSSEGMENT, Rev. 0 submitted on TVA letter NNC 8/19/10: The justification design and licensing basis for WBN dated August 11, 2010. for not performing and D3 Unit 1 that TVA has implemented analysis contained in the CQ without NRC prior approval under the Data Storm Testing PAMS Licensing Technical 10 CFR 50.59 process."

Report is not acceptable. TVA to NNC 4/15/10: The response The procurement specification (Attachment 23) for docket a D3 analysis for the CQ addresses many systems and should the Foxboro I/A sytem section 3.11.2 requires the PAMS. This will be responded be read by all EICB reviewers..

following as part of the Factory Acceptance Test: to in Item 64.

Tests shall include realistic message traffic on all NNC 8/25/10: The segmentation communications networks and subnetworks. In analysis has been read. Please addition, all digital interfaces to external explain why it is believed that environments such as plant computer interface shall faliure will not propagate over

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date be tested to withstand broadcast storm events the peer-to-peer network.

without degradation in the control systems performance. Also, the control system shall be tested Looking for an architectural for broadcast storm events resulting description of the network from component failures on internal communication interconnections similar to the networks without degradation in the control systems ICS overview, identification of performance. credible failure modes caused by the mesh network and what component(s) prevent mesh network failures from disabiling the entire system. What prevents a segment failure from propagating across the mesh network and affecting other segments.

005 7.1.3. December 11, 2009 Responder: Craig/Webb Closed Closed ML093431118, NNC 4/15/10: Related to setpoints EICB (Garg) 1 RAI 5 and SE Section 7.1.3.1.

By letter date February 28, 2008 (Agencywide Documents TVA Letter Dated February 5, 2010: TVA provided Date: 3/15/2010 FSAR Amd 100 Access and Management System (ADAMS) Accession the Unit 2 setpoint methodology (WCAP-177044-P Responsibility: NRC (Garg) and Number ML080770366) TVA provided a "red-lined" version Revision 0 - dated December). TVA (Hilmes and Crouch) of the FSAR for WBN Unit 2. The purpose of this FSAR "red-line" version was to depict how the Unit 2 FSAR will TVA Letter Dated March 12, 2010 (Enclosure 1, Item RAI response received. This appear at fuel load. This letter identified significant FSAR No. 5 on Page 5 of 15): TVA responded to this item is closed as this is covered changes and provided a X-REF number for each. request for additional Information under item 154 later on.

Change 7.3-1 refers to the following two Summary This item is addressed as follows: This item requires futher Reports: discussion between TVA and the

1. FSAR Amendment 100 which was submitted on staff concening the setpoint TVA Letter, P. L. Pace to NRC, dated February.9, 1998, TVA letter to the NRC dated August __, 2010 methodology employed for "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR incorporates as-found and as-left setpoint tolerance WBN2.

50.59(b)(2), Changes, Tests and Experiments Summary discussion into section 7.1.2.1.9, adds EEB-TI-28, Report Setpoint Methodology to the section 7.1 references See Item 8.

and adds a reference to 7.1.2.1.9 to section TVA Letter, P. L. Pace to NRC, dated September 30, 7.2.1.1.10.

2005, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59, Changes, Tests and Experiments Summary Report" TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February Please submit the 50.59 Evaluations for each of these 2, 2010.

Summary Reports and identify which parts are relevant to the Unit 2 Setpoint Methodology.

006 December 11, 2009 (ML093431118, RAI 6) By letter dated February 5, 2010: TVA provided the Open Open NNC: WCAP-12096 Rev. 7 EICB (Garg)

Amendment 95 of the FSAR, Chapter 7.3, shows that Unit 2 setpoint methodology (WCAP-177044-P (ML073460281) is in ADAMS.

change 7.3-1 consists of updating a reference from Revision 0 - dated December 2009). Date: 2/16/2010 TVA to reference revision 5 to revision 7 and making it applicable to Unit 1 TI-28 for as found NNC: WCAP-12096 Rev. 8 is the only, while adding a new reference, applicable only to Unit TVA Letter Dated March 12, 2010 (Enclosure 1, Item The Westinghouse Setpoint and as left value. current revision for Unit 1.

2. No. 6 on Page 7 of 15): TVA responded to this methodology document (WCAP- Also provide the request for additional Information. 17044-P Revision 0) identifies reference to FSAR NNC 4/15/10: Hukam, please update Reagan, J. R., "Westinghouse Setpoint Methodology for that the intermediate and source Section 7.1 for the this open item as appropriate.

Protection Systems, Watts Bar Units 1 and 2, Eagle 21 a. TVA to docket Rev. 8 and identify that Rev. 8 is range calculations were setpoint Version," WCAP-12096 Rev. 7, (Westinghouse Proprietary the current revision for Unit 1. TVA to identify any performed by TVA (2-NMD-092- methodology. TVA to docket Rev. 8 and identify that Class 2). Unit 1 Only NRC approval of Rev. 8. 0131). Please provide the Rev. 8 is the current revision for Unit intermediate and source range 1. TVA to identify any NRC approval WCAP Westinghouse Setpoint Methodology for In accordance with item 2, below, there is no change calculations performed by TVA of Rev. 8.

Protection System, Watts Bar Unit 2, Eagle 21 Version, to the methodology, therefore revision 8 is not (2-NMD-092-0131).

WCAP-17044-P. Unit 2 Only. included in this response. TVA to describe how TVA calculations The Westinghouse Setpoint for Unit 2 are different than Unit 1. If Please provide both setpoint methodology documents Westinghouse letter WAT-D-10502 (Attachment 1) methodology document (WCAP- they are the same, TVA to docket identified above. describes the two changes to WCAP-12096 17044-P Revision 0) identifies such statement under oath and Revision. 8. The first change addresses the that the undervoltage and Affirmation.

containment sump level transmitter replacement. underfrequency calculations This change was submitted under 50.59 summary were performed by TVA (2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date report (ML073460444, Page 77). The second 068-0031). Please provide the change is to delete the power range negative flux undervoltage and rate trip. This item was submitted as a Technical underfrequency calculations Specification change (ML073201052). The performed by TVA (2-27-068-Technical Specification change was subsequently 0031).

approved.

Work with Item 7 for WCAP-The current revision of Unit 1 WCAP-12096 is 12906 issues.

Revision 9. Revision 9 was issued to make the changes required by the Steam Generator Replacement Project. Unit 2 is using the original steam generators, therefore the changes in Revision 9 are not applicable to Unit 2.

b. TVA to describe how TVA calculations for Unit 2 are different than Unit 1. If they are the same, TVA to docket such statement under oath and Affirmation.

TVA response letter dated March 12, 2010, Enclosure 1, Item Number. 7 addressed this request; however, the March 12 letter was not submitted under oath and affirmation. This letter fulfills the oath and affirmation requirements for the previous response.

007 December 11, 2009 (ML093431118, RAI 7) TVA Letter Dated March 12, 2010 (Enclosure 1, Item Open Open NNC 4/15/10: Related to setpoints EICB (Garg)

No. 7 on Page 7 of 15): TVA responded to this and SE Section 7.1.3.1.

The setpoint methodology has been reviewed and request for additional Information. Date: 1/13/2010 Same as Item 6 approved by the NRC staff in Section 7.1.3.1 of NUREG- above. NNC 4/15/10: Hukam, please update 0847 (ML072060490), NUREG-0847 Supplement No.4 a. TVA will submit WCAP-12096, Rev. 8 if there is a RAI response received. NRC to this open item as appropriate.

(ML072060524), and NUREG-0847 Supplement No. 15 change to the methodology. review response.

(ML072060488). TVA to provide Rev. 8 of the Unit 1 No change in methodology, therefore WCAP-12906, TVA will submit WCAP-12096, document (which is the current one) if Please describe all changes from the methodology that Revision 8 is not submitted. Rev. 8 if there is a change to the there is a change in methodology and has been reviewed and approved by the staff. methodology. identify how the Unit 2 document

b. TVA will supply the 50.59 letter for Rev. 8 differs from it.

TVA will supply the 50.59 letter Westinghouse letter WAT-D-10502 (Attachment 1) for Rev. 8 describes the two changes to WCAP-12096 Revision. 8. The first change addresses the TVA to locate transmittal letter containment sump level transmitter replacement. that submitted Rev. 7.

This change was submitted under 50.59 summary report (ML073460444, Page 77). The second TVA to determine the last change is to delete the power range negative flux revision of WCAP-12096 where rate trip. This item was submitted and approved as a there was a change in Technical Specification change (ML073201052). methodology.

c. TVA to locate transmittal letter that submitted Rev. Work with Item 6 for WCAP-

7. 12906 issues.

Refer to reponse to Item 1. TVA responded to this request for additional Information in letter dated March 12, 2010, Enclosure 1, Item Number 6.

d. TVA to determine the last revision of WCAP-12096 where there was a change in methodology.

Previous revisions to WCAP-12096 have been due to hardware changes. The calculation methodology has not changed since revision 0.

(

008 7.3 G December 11, 2009 TVA Letter Dated March 12, 2010 (Enclosure 1, Item Closed Closed ML093431118,

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date No. 8 on Page 7 of 15): TVA responded to this RAI 8 There are several staff positions that provide guidance on request for additional Information FSAR Amd 100.

setpoint methodology (e.g., Reg Guide 1.105, BTP 7-12, Closed as it will be RIS-2006-17 and TSTF-493 Rev. 4). Please identify how This item is addressed as follows: covered under item the Unit 2 setpoint methodology addresses staff guidance. 154

1. FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August __, 2010 incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

2. TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February 2, 2010.

009 December 11, 2009 TVA Letter Dated March 12, 2010 (Enclosure 1, Item Closed Closed ML093431118, NNC 4/15/10: Related SE Section 7.3.

EICB (Darbali)

No. 9 on Page 8 of 15): TVA responded to this RAI 9 Change 7.3-2, identified in Watts Bar Nuclear Plant FSAR request for additional Information Date: 3/15/2010 red-line for Unit 2 (ADAMS Accession Number Responsibility: NRC (Darbali)

ML080770366), refers to the following Summary Report:

TVA Letter, P. L. Pace to NRC, dated September 20, 50.59 evaluation was submitted 2002, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR in the RAI response. NRC to 50.59, Changes, Tests and Experiments Summary Report" review.

Please provide the 50.59 Evaluation summarized in this Summary Report.

010 December 11, 2009 (ML093431118, RAI 10) TVA Letter Dated March 12, 2010 (Enclosure 1, Item Open Open NNC 4/15/10: Related SE Section 7.3.

EICB (Darbali)

No. 10 on Page 8 of 15): TVA responded to this The original SER on Watts Bar (NUREG-0847) documents request for additional Information. Date: 3/15/2010 NRC Review that the scope of the review of FSAR Section 7.3, Engineered Safety Features Actuations System, TVA Letter (ML073550386) dated FEB 26 1992: NRC evaluating TVA response.

included: included single-line, function logic and docketed WCAP-12374 Rev. 1 (ML080500664).

schematic diagrams, and descriptive information for the NRC to discuss document ESFAS and those auxiliary supporting systems that are requirements and provide essential to the operation of either the ESFAS or the ESF additional information to resolve systems. The review included the applicant's design this item.

criteria and design bases for the ESFAS and the instrumentation and controls of auxiliary supporting systems. The review also included the applicant's analyses of the manner in which the design of the ESFAS and the auxiliary supporting systems conform to the design criteria."

Please provide the information referred to in the quotation and include a description of all changes since this information was reviewed and approved by the NRC staff.

If some parts of this information is included in the FSAR (e.g., Design Criteria) this information can be explicitly referenced in the response to this question.

011 December 11, 2009 (ML093431118, RAI 11) TVA Letter Dated March 12, 2010 (Enclosure 1, Item Closed Closed NNC 4/15/10: Related SE Section 7.3.

EICB (Darbali)

No. 11 on Page 13 of 15): TVA responded to this NUREG-0847 Supplement No. 2 Section 7.3.2 includes an request for additional Information Date: 3/15/2010 evaluation of a change in containment sump level Responsibility: NRC (Darbali) measurement. Provide information to demonstrate that Unit 2 implements the containment sump level indication Requested information was as described and evaluated in NUREG-0847 Supplement submitted in the RAI response.

No. 2, Section 7.3.2, for Unit 1.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 012 December 11, 2009 (ML093431118, RAI 12) TVA Letter Dated March 12, 2010 (Enclosure 1, Item Closed Closed NNC 4/15/10: Related SE Section 7.4.

EICB (Darbali)

No. 12 on Page 13 of 15): TVA responded to this The original SER on Watts Bar (NUREG-0847) documents request for additional Information Date: 3/15/2010 that the scope of the review of FSAR Section 7.4, "Systems Required for Safe Shutdown," included single- A revised response was included in the 7/30 letter TVA provided the following:

line and schematic diagrams: "The scope of the review of that provides the requested information.

the systems required for safe shutdown included the 1. Description of what is different single-line and schematic diagrams and the descriptive from Unit 1 information for these systems and for the auxiliary systems essential for their operation." 2. Road map between functions listed in 7.4 and the FSAR Please provide the single-line and schematic diagrams for section that describes the the systems required for safe shutdown that are applicable equipment that performs the to Unit 2, and include a description of all changes since function. Item Closed.

these diagrams were reviewed and approved by the NRC staff.

013 December 11, 2009 (ML093431118, RAI 13) TVA Letter Dated March 12, 2010 (Enclosure 1, Item Closed Closed TS have been docketed.

EICB (Garg)

No. 13 on Page 14 of 15): TVA responded to this Chapter 7 and Chapter 16 of Amendment 95 to the FSAR request for additional Information Date: 3/15/2010 This item is closed NNC 4/15/10: Related to setpoints do not include any setpoint values. Please describe how for chapter 7. NRC and SE Section 7.1.3.1.

and when setpoint values (e.g., TS allowable values) will RAI response received. will review T.S.

be provided for Unit 2. Westinghouse is completing the under different NNC 4/15/10: Hukam, please update setpoint calculations which will chapter. this open item as appropriate.

Please describe the information that will be provided to be completed by May 11, 2011.

justify the acceptability of these values. NRC to review response. Related to SE Section 7.1.3.1.

014 December 22, 2009 (ML093560019, item 1) Date: 4/27/10 Closed Closed NNC 4/30/10: Related to Eagle 21; EICB (Carte)

Responder: TVA therefore Garg is responsible.

Provide the justification for any hardware and software Date: 4/27/10 changes that have been made since the previous U.S. By letter dated April 27, 2010: TVA responded to this Responsibility: NRC (Carte)

Nuclear Regulatory Commission (NRC) staff review for request for information (Enclosure, Item No. 1)

Eagle 21 and other platforms stated: "In discussion with the staff, TVA's NNC: I do not recall saying that understanding is that the focus of this question is the the NRC is not interested in Eagle 21 system. Please refer to Reference 2 [TVA changes in other platforms.

Letter Dated March 12, 2010], Question 10, and TVA Please provide a description of letter to NRC dated August 25, 2008, 'Watts Bar changes to other platforms (e.g.,

Nuclear Plant (WBN) - Unit 2 - Westinghouse Eagle SSPS).

21 Process Protection System, Response to NRC I&C Branch request for additional information' For Eagle 21, this response (Reference 3 [TVA letter dated August 25, 2008]) for points to Open Item No. 10.

the discussion of changes to the Eagle 21 system."

Response understood.

A listing of changes to other platforms was provided Additioanl material will be in TVA letter dated April 27, 2010, Enclosure 1, items requested separately to 21 and 23. understand the systems described.

015 December 22, 2009 (ML093560019, item 2) Date: 4/27/10 Closed Closed EICB (Garg)

Responder: TVA Verify that the refurbishment of the power range nuclear Date: 4/27/10 instrumentation drawers resulted in only like-for-like By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Garg) replacements. request for information (Enclosure, Item No. 2).

Response acceptable. Close 016 December 22, 2009 (ML093560019, item 3) Date: 4/27/10 Closed Closed EICB (Carte)

Responder: TVA Identify the precedents in license amendment requests Date: 4/27/10 (LARs), if any, for source range monitors or intermediate By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Garg) range monitors. request for information (Enclosure, Item No. 3).

Acceptable. Close

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 017 December 22, 2009 (ML093560019, item 4) Date: 4/27/10 Open Open EICB Identify precedents in LARs, if any, for the solid state By letter dated April 27, 2010 TVA responded to this Date: 4/27/10 NRC Review (Darbali) protection system. Also, identify any hardware deviation request for information (Enclosure, Item No. 4).

from the precedent. Awaiting NRC evaluation of response.

018 December 22, 2009 (ML093560019, item 5) Date: 4/27/10 Closed Closed EICB (Garg)

Responder: TVA Identify any changes made to any instrumentation and Date: 4/27/10 control (I&C) system based on prior knowledge of failures. By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Garg) request for information (Enclosure, Item No. 5).

Acceptable. Close 019 December 22, 2009 (ML093560019, item 6) Date: 4/27/10 Open Open EICB (Garg)

Verify that the containment purge isolation radiation By latter dated April 27, 2010 TVA responded to this Date: 4/27/10 NRC Review monitor is the same as used in Watts Bar Unit 1, or identify request for information (Enclosure 1, Item No. 6) for any hardware changes. the ratemeter. Response unacceptable. Should A newer model, RD-52, of the RD-32 detector discuss all changes.

assembly used in Unit 1. The detector assembly replacement is due to obsolescence and improved reliability.

Clarify electronics are analog and the same as unit 1 and the only difference is the detector assembly.

020 December 22, 2009 (ML093560019, item 7) Date: 4/27/10 Closed Closed NNC 4/30/10: SRP Section 7.0 EICB (Garg)

Responder: TVA states: "The organization responsible Provide environmental qualification information pursuant to Date: 4/27/10 for the review of environmental Section 50.49 of Title 10 of the Code of Federal By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (EEEB) qualification reviews the Regulations (10 CFR) for safety-related actuation request for information (Enclosure, Item No. 7). environmental qualification of I&C transmitters. Garg to coordinate with Weibi to equipment. The scope of this review ensure EEEB takes includes the design criteria and responsibility for this one. qualification testing methods and procedures for I&C equipment."

021 December 22, 2009 (ML093560019, item 8) Date: 5/25/10 Open Open EICB (Garg)

For the Foxboro Spec 200 platform, identify any changes No vendor system description is available for the Date: 5/24/10 NRC Review in hardware from the precedent systems. Provide the Foxboro Spec 200 system. The hardware design report and the equipment qualification information. description and qualification documents are provided The understanding reached in on a component level basis. A TVA generated the meeting on April 14, 2010, system description is provided to assist the reviewer. was that TVA should identify any The hardware differences from the unit 1 systems changes, or state under oath and are provided in the loop and card comparison affirmation that there were no documents. As agreed with the reviewer, the changes. If there were no component level documents are not required to be changes, then the NRC would submitted at this time, but may be required later confirm by inspection.

based on the review of attached documents. The following TVA generated documents are provided A revised response was (Attachment 1): requested at the 5/24/10 public meeting.

1. Analog loop comparison

2. Analog card comparison

3. Analog system description

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 022 December 22, 2009 (ML093560019, item 9) Date: 4/27/10 Open Open EICB (Darbali)

Verify the auxiliary feedwater control refurbishment results By letter dated April 27, 2010 TVA responded to this Date: 4/27/10 NRC Review in a like-for-like replacement, and identify any changes request for information (Enclosure, Item No. 9).

from the identified precedents. TVA should confirm if Woodward The control function of the Auxiliary Feedwater Governer is the only change.

(AFW) Flow for Steam Generator Level is the same as Unit 1. The controllers and signal See Item 285 for follow up modifiers/conditioners are Foxboro SPEC 200 question.

discrete analog modules as Unit 1 control loops. The only different Unit 1 uses a 10-50ma signal and Unit 2 is using a 4-20ma. The SPEC 200 control modules operate with a 0-10mv system for both Unit 1 and Unit 2.

The differences between the Units that have a control function for the AFW system is the differential pressure control upstream of the motor driven AFW pumps 2A-A and 2B-B. Unit 1 still has the analog Bailey/GEMac controllers and signal conditioners.

Whereas Unit 2 has converted the controllers and signal conditioners to Foxboro SPEC 200 discrete analog components. Both loops still maintain a Fisher modifier for valve control.

The four (4) control loops are described below:

2-P-3-122A This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varying valve 2-PCV-3-122. Differential Pressure Indicating Controller 2-PdIC-3-122A (on panel 2-M-4) can be used either in manual mode or in automatic mode.

This loop controls this valve from the Main Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the normal position.

2-P-3-122C This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varying valve 2-PCV-3-122. Differential Pressure Indicating Controller 2-PdIC-3-122C (on panel 2-L-10) can be used either in manual mode or in automatic mode.

This loop controls this valve from the Auxiliary Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the auxiliary position.

2-P-3-132A This loop controls the differential pressure of the Auxiliary Feedwater Pump 2B-B by varying valve 2-PCV-3-132. Differential Pressure Indicating Controller 2-PdIC-3-132A (on panel 2-M-4) can be used either in manual mode or in automatic mode.

This loop controls this valve from the Main Control Room when transfer switch 2-XS-3-132 (on panel 2-L-11B) is in the normal position.

2-P-3-132C

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date This loop controls the differential pressure of the Auxiliary Feedwater Pump 2B-B by varying valve 2-PCV-3-132. Differential Pressure Indicating Controller 2-PdIC-3-132A (on panel 2-M-4) can be used either in manual mode or in automatic mode.

This loop controls this valve from the Main Control Room when transfer switch 2-XS-3-132 (on panel 2-L-11B) is in the normal position.

Unit 2 controllers are Foxboro model N-250HM-M2NH-F; Signal Converters, current-voltage IN are model N-2AI-I2V, and voltage-current OUT are N-2AO-VAI; Control Card is model N-2AX+A4.

All components are supplied in accordance with requirements of 10CFR50 Appendix B and ASME NQA-1 as defined in Invensys Systems, Inc.

Corporate Quality Assurance Program Requirements, QMS, Revision S, dated October 26, 2007.

All components were manufactured with the same materials and processes as thst qualified foe Nuclear Class 1E Service per IEEE-323-1974 and IEEE-344-1975.

023 December 22, 2009 (ML093560019, item 10) Date: 4/27/10 Closed Closed NNC 4/30/10: SRP Section 7.0 EICB (Garg)

Responder: TVA states: "The organization responsible Provide environmental qualification (10 CFR 50.49) Date: 12/22/09 for the review of environmental information for safety-related control transmitters and By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (EEEB) qualification reviews the complete the deviation section of the table. request for information (Enclosure, Item No. 10). environmental qualification of I&C Garg to coordinate with Weibi to equipment. The scope of this review ensure EEEB takes includes the design criteria and responsibility for this one. qualification testing methods and procedures for I&C equipment."

024 December 22, 2009 (ML093560019, item 11) During the January 13, 2010 meeting, TVA Closed Closed  ; NNC 4/30/10: Carte to address EICB (Carte) presented a schedule for completing various response with respect to PAMS and Provide a schedule by the January 13, 2010, meeting for documents for the PAMS system. This schedule did Date: 4/27/10 Closed to Item 43 Darbali to address response with providing information in accordance with I&C Interim Staff not support TVA's desired schedule. TVA was so respect to RM1000.

Guidance (ISG) 6. informed and said they would work on improving the The explanations provided by schedule. TVA said that the setpoint methodology TVA (that certain information is TVA has agreed to submit the would be provided shortly. No other systems of not required) are unacceptable. requested information on the docket.

documentation was discussed.

NNC 8/18/10: The TVA By letter dated February 5, 2010 (see enclosure 1), agreement in the Comments TVA provided a list of documents and associated column conflicts with the TVA availability for PAMS. responses to other open items where TVA states that By letter dated April 27, 2010 TVA responded to this information is available for audit.

request for information (Enclosure, Item No. 11).

By letter Dated June 18, 2010 (see Attachment 3)

TVA providded a table, "Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix."

025 December 22, 2009 (ML093560019, item 12) Date: 4/27/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Singh) For the containment radiation high radiation monitor, verify By letter dated April 27, 2010 TVA responded to this Date: 07/28/2010 NRC Review Section 7.5.2 that the information provided by TVA is consistent with the request for information (Enclosure, Item No. 12).

information provided with the previously-approved license NRC review in progress.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date amendment request for the Duane Arnold plant or provide Phase 3 information. Need Radiation Monitoring System Description/Design Criteria Are detectors different than Unit 1

Are there any commercially dedicated parts in the RM-1000.

State digital communication ports are not used.

026 December 22, 2009 (ML093560019, item 13) Date: 4/27/10 Closed Closed NNC 4/30/10: SRP Section 7.0 EICB (Garg)

Responder: TVA states: "The organization responsible Provide environmental qualification (10 CFR 50.49) Date: 12/22/09 for the review of environmental information for safety-related monitoring transmitters. By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (EEEB) qualification reviews the request for information (Enclosure, Item No. 13). environmental qualification of I&C Garg to coordinate with Weibi to equipment. The scope of this review ensure EEEB takes includes the design criteria and responsibility for this one. qualification testing methods and procedures for I&C equipment."

027 December 22, 2009 (ML093560019, item 14) Date: 4/27/10 Closed Closed EICB (Carte)

Responder: TVA For Foxboro I/A provide information regarding safety/non- Date: 4/27/10 safety-related interaction, common cause failures, and By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Carte) communication with safety related equipment in request for information (Enclosure, Item No. 14):

accordance with ISG 4. "There is no digital communications or interactions between Foxboro Intelligent Automation (IA) and any Safety-related system."

028 December 22, 2009 (ML093560019, item 15) Responder: Mark Scansen Open Open EICB (Garg)

Date: 4/27/10 For the turbine control AEH system, verify that the Provide 50.59 evaluation. Provide 50.59 refurbishment results in a like-for-like replacement. By letter dated April 27, 2010 TVA responded to this Response acceptable.

request for information (Enclosure, Item No. 15).

The requested 50.59 is included in Attachment __.

029 December 22, 2009 (ML093560019, item 16) Date: 4/27/10 Closed Closed EICB (Carte)

Responder: TVA For the rod control system, verify that the refurbishment Date: 4/27/10 results in a like-for-like replacement. By letter dated April 27, 2010 (ML101230248) TVA Responsibility: NRC (Carte) responded to this request for information (Enclosure, Item No. 16 & Attachment 5): TVA stated on a card by card basis that the referbished cards have the same form fit and function.

030 December 22, 2009 (ML093560019, item 17) Responder: Clark Open Open EICB (Garg)

Regarding the refurbishment of I&C equipment, identify Date: 4/27/10 Date: 4/27/10 any component digital upgrades and, if so, provide the supporting design information. By letter dated April 27, 2010 TVA responded to this Does not state if there are no request for information (Enclosure, Item No. 17). other upgrade which contain imbedded digital processor.

There are no other I&C upgrades which contain an Revised response acceptable.

imbedded digital processor.

031 December 22, 2009 (ML093560019, item 18) Date: 4/27/10 Closed Closed CERPI is non-safety related.

EICB (Carte)

Responder: TVA For the rod position indication system (CERPI), provide Date: 4/27/10 information in accordance with ISG 4. Need to consider By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Carte) cyber-security issues. request for information (Enclosure, Item No. 18).

Response acceptable.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 032 December 22, 2009 (ML093560019, item 19) Date: 4/27/10 Closed Closed EICB (Carte)

Responder: TVA For the process computer, need to consider cyber security Date: 4/27/10 issues and emergency response data system needs. By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Carte) request for information (Enclosure, Item No. 19).

EICB will no longer consider cyber issues.

033 December 22, 2009 (ML093560019, item 20) Date: 4/27/10 Closed Closed The loose parts monitoring system is EICB (Carte)

Responder: TVA not connected to any other system.

For the loose parts monitoring system, provide information Date: 4/27/10 regarding interactions with safety related equipment. By letter dated April 27, 2010 TVA responded to this Responsibility: NRC (Carte) request for information (Enclosure, Item No. 20):

Loose parts is not connected to any other system. TVA stated that there are no interactions.

034 2/4/2010 Responder: TVA Open Open EICB (Garg)

In the December 15, 2009 public meeting, TVA listed the By letter dated April 27, 2010 TVA responded to this Awaiting NRC evaluation of NRC review significant changes made since the Watts Bar Unit 1 request for information (Enclosure, Item No. 21). response.

Licensing (see below). For each of the following significant changes: Remove all references to Elbow Tap Methodology from Unit 2 Licensing Bases.

1) Is the change unique to Unit 2, or will it be the same as whats currently installed in Unit 1?

2) If its the same as Unit 1, was this change made under a license amendment or under a 50.59?

3) When do you plan to submit the detailed information regarding the changes?

034. Chapter 7.1 - Introduction Open Open EICB 1 Reactor Coolant System Flow Rate Measurement Design Basis Analysis Parameters Loose Parts Monitoring (Garg/Singh) 034. Chapter 7.2 - Reactor Trip System Open Open EICB (Garg) 2 Deletion of Neutron Flux Negative Rate Trip Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump Reactor Coolant System Flow Rate Measurement Foxboro I/A 034. Chapter 7.3 - ESFAS Open Open 3 EICB Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump (Darbali) 034. Chapter 7.5 - Instrumentation Systems Important to Open Open EICB (Carte) 4 Safety Plant Process Computer Replacement Containment Sump Level Transmitter Replacement Safety Injection Systems Cold Leg Accumulator Level Measurement System Common Q/PAMs 034. B Chapter 7.6 - All Other Systems Required for Safety Open Open 5 (Gar Plant Process Computer Replacement g/Sin Loose Parts Monitoring System

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 034. Chapter 7.7 Control Systems Open Open EICB (Garg/Darbali) 6 Alternate Means for Monitoring Control or Shutdown Rod Position Eliminate Pressurizer Backup Heaters on High Level Signal AMSAC Replacement Foxboro I/A WINCISE /Power Distribution Monitoring System (Beacon) 035 2/18/2010 Responder: Clark Open Open LIC-110 Section 6.2.2 states: Design EICB (Singh) features and administrative programs Please provide a system description of the Digital Metal TVA Letter dated March 12, 2010 Enclosure 1, item Description provide is not of TVA to docket the that are unique to Unit 2 should be Impact Monitoring System that contains sufficient detail to 4 responded to this request for information. sufficient detail to allow a information reviewed in accordance with the support a review of this system using current staff regulatory determination. TVA to including current staff positions. Unit 2 FSAR positions. The attached non-proprietary system description was send the proprietary information proproietary Section 7.6.7, Loose Part Monitoring developed from proprietary Westinghouse Watts Bar for NRC review. At the 9-2 information for (LPMS) system Description, Unit 2 DMIMS-DX Operations and Maintenance meeting G. Singh stated the LPMS. describes a system design that is Manual, 1TS3176 Rev.0 (Reference 1). system descriptionn provided unique to Unit 2.

Westinghouse approved this non-proprietary was acceptable and the response via letter WBT-D-____ dated August , proprietary information was not 2010. The system description is contained in required at this time.

Attachment 2.

036 February 18, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1, SE Section EICB (Carte)

Responder: Clark 7.5.2 Please provide a system description of the Post Accident Date: 2/18/2010 Monitoring System that contains sufficient detail to support In previous letters TVA has provided the Common Q Responsibility: TVA NNC: Unit 2 FSAR Section 7.5.1, a review of this system using current staff positions. documents that address this item: Post Accident Monitoring Instrumentation, describes a system design that is unique to Unit 2. LIC-110, "Watts Bar Unit 2 License Application Review," states: "Design features and administrative programs that are unique to Unit 2 should then be reviewed in accordance with the current staff positions."

037 2/18/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5, Instrumentation EICB (Marcus)

System Important to Safety, consists Is the plant computer a safety-related display system? As identified in TVA letter dated March 12, 2010, August 19, 2010 - TVA to submit NRC review of two major subsections: 7.5.1, Post Enclosure 1, item 2, the plant computer system is markup of FSAR Amendment Accident Monitoring Instrumentation non-safety related. 100. (PAM), and 7.5.2, Plant Computer System.

FSAR section 7.5 describes both safety and non-safety related devices and systems. FSAR section Regulatory Guide 1.70, Standard 7.1.1.2 is revised in FSAR Amendment 100 format and content of Safety Analysis submitted to the NRC on TVA letter to the NRC Reports for Nuclear Power Plants, dated September 1, 2010. Revision 3 dated November 1978 states (see Section 7.1.1): List all instrumentation, control, and supporting systems that are safety-related including alarms, communication, and display instrumentation. FSAR Section 7.1.1.2, Safety-Related Display Instrumentation, describes, in the first paragraph, the PAM system, and the

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date second paragraph states: All other safety-related instrumentation is discussed in Section 7.5. Therefore, to be consistent with the preceding paragraph, the FSAR states that the plant computer system is safety related.

Contrary to the FSAR the slides presented at the December 15, 2010 meeting indicate that the plant process computer is not safety-related. Therefore the docketed material is inconsistent and needs to be clarified.

038 2/18/2010 Responder: Clark Date: 5/25/10 Open Open The slides presented at the December EICB (Marcus) 15, 2010 meeting (ML093520967)

Please provide a description of the interfaces between: (1) FSAR section 7.1.1.2 is revised in FSAR August 19, 2010 - TVA to submit NRC review indicate that the plant process the Safety Parameter Display System and (2) the Amendment 100 submitted to the NRC on TVA letter markup of FSAR Amendment computer has been replaced.

Technical Support Center and Nuclear Data Links with the to the NRC dated September 1, 2010.. 100.

plant control and safety systems. This Description should contain sufficient detail to support a review of these interfaces using current staff positions.

039 January 13, 2010 Responder: Clark Date: 5/25/10 Closed Closed The equation for the calculation of the EICB (Garg) estimated average hot leg Please describe the change to the calculation of the Refer to revised equations in FSAR amendment 98. Date: 1/13/2010 temperature on page 7.2-13 of estimated average hot leg temperature (see FSAR Section Responsibility: TVA Revision WBNP-96 of the Unit 2 7.2.1.1.4, page 7.2-14 Version WBNP-96) in sufficient FSAR is different than the calculation detail to support a review of this system using current staff NRC staff will review of the average hot leg temperature positions. shown at the top of page 7.2-14 of version WBNP-1 of the UNIT 1 FSAR.

040 January 13, 2010 Responder: Clark Date: 5/25/10 Closed Closed The equation for the calculation of the EICB (Garg) power fraction on page 7.2-14 of Please describe the change to the calculation of the power Refer to revised equations in FSAR amendment 98. Date: 1/13/2010 Revision WBNP-96 of the Unit 2 fraction (see FSAR Section 7.2.1.1.4, page 7.2-13 Version Responsibility: TVA FSAR is different than the calculation WBNP-96) in sufficient detail to support a review of this of the power fraction shown at the top system using current staff positions. NRC staff will review of page 7.2-14 of version WBNP-1 of the UNIT 1 FSAR.

041 2/19/2010 Responder: WEC Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE Please provide the following Westinghouse documents: Items (1) and (2) were docketed by TVA letter dated The SysRS and SRS incorporate TVA to docket Section 7.5.2 (1) WNA-DS-01617-WBT Rev. 1, "PAMS System April 8, 2010. requirements from many other information Requirements Specification" documents by reference. indetified in ISG6. See also Open Item Nos. 226 & 270.

(2) WNA-DS-01667-WBT Rev. 0, "PAMS System Design Items (3), (4) and (5) WNA-CD-00018-GEN Rev. 3, Specification" "CGD for QNX version 4.5g," WNA-PT-00058-GEN NNC 8/25/10: (3) An earlier TVA to provide (3) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version Rev. 0, "Testing Process for Common Q Safety version of this report was date when 4.5g" systems" and WNA-TP-00357-GEN Rev. 4, "Element docketed for the Common Q information will be Please provide the following Westinghouse documents or Software Test Procedure" are available for audit at topical report; therefore, there docketed.

pointers to where the material was reviewed and approved the Westinghouse Rockville office (Westinghouse should be no problem to docket in the CQ TR or SPM: letter WBT-D-1526, Reference 6). this version. (4) Per (4) WNA-PT-00058-GEN Rev. 0, "Testing Process for ML091560352, the testing Common Q Safety systems" 3 will be addressed during September 20 and 21 process document does not (5) WNA-TP-00357-GEN Rev. 4, "Element Software Test audit. address the test plan Procedure" 4 Westinghouse will develop a WBN2 Specific Test requirements of the SPM.

Plan to compensate for WNA-PT-00058-GEN. TBD Please provide a test plan that 5 WNA-TP-00357-GEN superseded by the SPM implements the requirements of compliance matrix in the Licensing Technical Report the SPM.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date next revision.

042 February 25, 2010: Telecom Date: 5/25/10 Closed Closed The drawing provided did not have EICB (Carte)

Responder: Clark the identification numbers as in the On December 16, 2009: EICB stated to DORL: "I am Date: 2/25/2010 FSAR.

having trouble reading the drawings in the binder that was Attachment 2 provides a drawing cross reference list Responsibility: TVA given to me. Is it possible to produce a set of full size for FSAR Chapter 7 and electronic copies of the fully drawing that are in the FSAR?" legible current drawings previously submitted in full TVA provided readable size hard copies. drawings.

On February 23, 2010: EICB received a set of enlarged Chapter 7 FSAR pages (drawings) that are still unreadable.

043 2/19/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE The PAMS ISG6 compliance matrix supplied as Enclosure The PAMS ISG6 compliance matrix supplied as Revised compliance matrix is TVA to docketed Section 7.5.2 1 to TVA letter dated February 5, 2010 is a first draft of the Enclosure 1 to TVA letter dated February 5, 2010 is unacceptable. requested material.

information needed. The shortcomings of the first three a first draft of the information needed. NNC 8/25/10: A CQ PAMS ISG6 lines in the matrix are: NNC 8/12/10: It is not quite TVA to provide compliance matrix was dockated on:

By letter dated April 8, 2010 TVA provided the PAMS enough to provide all of the date when (1) February, 5 12010, (2) March 12, Line 1: Section 11 of the Common Q topical report did Licensing Technical Report provided additional documents requested. There information will be 2010, & (3) June 18, 2010. The staff include a commercial grade dedication program, but this information. are two possible routs to review docketed. has expressed issued with all of these program was not approved in the associated SE. that the NRC can undertake: (1) compliance evaluations. The staff is Westinghouse stated that this was the program and it Attachment 3 contains the revised Common Q follow ISG6, and (2) follow the still waiting for a good compliance could now be reviewed. The NRC stated that TVA should PAMS ISG-6 Compliance Matrix, dated June 11, CQ SPM. The TVA response evaluation.

identified what they believe was previously reviewed and 2010, that addresses these items (Reference 13). that was orriginally persued was approved. to follow ISG6, but some of the By letter Dated June 18, 2010 (see Attachment 3) compliance items for ISG6 were Line 2: TVA stated the D3 analysis was not applicable to TVA providded a table, "Watts Bar 2 - Common Q addresed by referencing the PAMS, but provided no justification. The NRC asked for PAMS ISG-6 Compliance Matrix." SPM. The NRC approved the justification since SRP Chapter 7.5 identified SRM to CQ TR and associated SPM; it SECV-93-087 Item II.Q as being SRP acceptance criteria This item will be addressed in the next revision of the may be more appropriate to for PAMS. Licensing Technical Report. review the WBN2 PAMS application to for adherence to Line 3: TVA identified that the Design report for computer the SPM that to ISG6. In either integrity was completed as part of the common Q topical path chosen, the applican should report. The NRC noted that this report is applicable for a provide documents and a system in a plant, and the CQ topical report did no justification for the acceptability specifically address this PAMS system at Watts Bar Unit 2. of any deviation from the path chosen. For example, it appears NRC then concluded that TVA should go through and that the Westinghouse's CDIs provide a more complete and thorough compliance matrix. are commercial grade dedication plans, but Westinghouse maintains that they are commercial grade dedication reports; this apparent deviation should be justified or explained.

044 February 25, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE The PAMS system described in Section 7.5 of the FSAR is Date: 2/25/2010 Section 7.5.2.

implemented in various manners. TVA should identify: By letter Dated June 18, 2010 (see Enclosure 1 Item Responsibility: TVA (1) Those variables that are implemented identical to what 6) TVA provided information requested.

was reviewed and approved for Unit 1.

(2) Those variable that are implemented identical to Unit 1, but that have been changed (e.g., under 50.59) and not reviewed by the NRC.

(3) Those variables that are implemented in a manner that is unique to Unit 2 (e.g., using Common Q).

TVA should supply supporting information appropriate to the manner of implementation.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 045 February 25, 2010 Date: 5/25/10 Closed Closed EICB (Carte)

Responder: Clark For each system implemented using a digital technology, Date: 2/25/2010 please identify any communications between divisions, or There are no communications betweeen divisions. Responsibility: TVA between safety-related equipment and non-safety-related The response includes the description of equipment. Please describe the implementation of the communications and isolation between the Common TVA provided information by associated communications isolation. Q PAMS, Eagle 21 and RM-1000 rad monitors and letter dated July 30, 2010 non safety systems. (ML102160349) - See Enclosure 1 Item No. 4.

046 February 25, 2010 Date: 5/25/10 Closed Closed EICB (Carte)

Responder: Clark The Watts Bar Unit 1 Ser (Section 7.2.1, page 7-3) Date: 2/25/2010 identifies that the RTS includes a trip from the "general FSAR amendment 98, Section 7.2.2.2, page 7.2-29 Responsibility: TVA warning alarm". Please identify where this trip is described second paragraph states:

in the current FSAR, or what SSER approved its removal.

"Auxiliary contacts of the bypass breakers are connected into the SSPS General Warning Alarm System of their respective trains such that if either train is placed in test while the bypass breaker of the other train is closed, both reactor trip breakers and both bypass breakers will automatically trip."

047 4/8/2010 Responder: WEC/Hilmes Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE The PAMS System Requirements Specification (SysRS) The licensing basis for WBN Unit 2 is Regulatory TVA provided information by TVA to provode Section 7.5.2 references RG 1.97 Rev. 3 where the FSAR References Guide 1.97 Revision 2. The Common Q PAMS letter dated July 30, 2010 aditional Rev. 2. Please explain. system was designed to Regulatory Guide 1.97 (ML102160349) - See Enclosure information as Revision 3, which is why the basis for the System 1 Item No. 5. described.

Requirements Specification referencinges revision 3.

In order to resolve this discrepancy an engineering NNC 8/9/10: There are two evaluation of the Common Q PAMS was performed. aspects of this issue. The first aspect has been addresed by Attachment 2 contains an engineering evaluation of the response. The second the Common Q PAMS design against the aspect is: How could requirements of Reg. Guide 1.97 Rev. 2. The Westinghouse Design, and TVA evaluation concluded that the Common Q PAMS approve a design to the wrong meets all requirements of Reg Guide 1.97 Rev. 2. requirement?

This evaluation will be added to design criteria WB-DC-30-7, Post Accident Monitoring Instrumentation by October 1, 2010.

048 April 8, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: WEC Monitoring Instrumentation - SE Reference 16 of the PAMS System Requirements Date: 4/8/2010 Section 7.5.2 Specification (SysRS) is the Unit 1 precautions Limitations To ensure technical fidelity with the Unit 1 ICCM-86 Responsibility: TVA and Setpoints document. When and how will the transition system, the Unit 1 PLS was used as an input to the to the unit 2 document be made. Common Q PAMS System Requirements Requested information was Specification. This was done to ensure the Unit 2 provided.

PAMS had at a minimum the same capabilities and accuracy as the unit 1 system.

The Unit 2 Common Q PAMS PLS section was developed based on the actual Common Q PAMS system design as reflected in the System Requirements Specification. As such, the Common Q PAMS PLS section is an output of the Common Q PAMS System Requirements Specification.

Therefore, no transition from the Unit 1 to the Unit 2 PLS is required.

The Unit 2 PLS is scheduled to be issued December 13, 2010.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 049 4/8/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE Please provide 00000-ICE-30156 Rev. 6. The PAMS Per Westinghouse letter WBT-D-2024 (Reference 7), This information must be on the TVA to revise Section 7.5.2 SysRS incorporates sections of this document by this document is available for audit at the docket. response or other reference. Westinghouse Rockville office. documentation.

This document is being submitted this week. TVA to provide date when information will be docketed.

050 4/8/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE How should the "shall" statements outside of the bracketed These sections are descriptive text and not TVA response is inconsistent TVA to revise Section 7.5.2 requirements be interpreted? requirements. The next revision of the Watts Bar (e.g., WNA-DS-01667-WBT Rev. response or other Unit 2 PAMS System Requirements Specification will 1 page 1-1, Section 1.3.1 implies documentation.

remove shall from the wording in those sections. A that "SysRS Section ###" has date for completing the next revision of the System requirements. See also TVA to provide Requirements Specification will be provided no later SDS4.4.2.1-1 on page 4-32). date when than August 31, 2010. information will be Is there a requirement on the docketed.

The System Requirements Specficiation will be shall referenced above??

revised by September 30, 2010 and submitted within two of receipt from Westinghouse.

051 April 15, 2010 Date: 5/25/10 Closed Closed EICB (Garg)

Responder: Craig/Webb NRC staff has issued RIS 2006-17, to provide guidance to Date: 4/15/2010 This item is closed the industry regarding the instrument setpoint methodology This item is addressed as follows: Responsibility: TVA as it will be which complies with 10CFR50.36 requirements. The staff reviewed under has requested all the licensees for the existing license to 1. FSAR Amendment 100 which was submitted on This item is to be worked with item 154. FSAR demonstrate how they meet the guidance provided in this TVA letter to the NRC dated August __, 2010 item 108. Amd 100 RIS. The staff consider WBN 2 as a license amendment incorporates as-found and as-left setpoint tolerance for all the setpoints in the TS. Provide the information on discussion into section 7.1.2.1.9, adds EEB-TI-28, how WBN 2's setpoint methodology meets the guidance of Setpoint Methodology to the section 7.1 references RIS 2006 -17. You may also consider the guidance and adds a reference to 7.1.2.1.9 to section provided in TSTF - 493, rev.4 as a basis for meeting the 7.2.1.1.10.

RIS 2006 -17 guidance.

2. TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February 2, 2010.

3. Refer to TVA to NRC letter dated August 25, 2008.

052 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Darbali)

Responder: Slifer Monitoring Instrumentation - SE Please identify the systems that will use the RM-1000 Date: 4/19/2010 Section 7.5.2 radiation monitors. As identified in TVA letter dated March 12, 2010, Responsibility: NRC Enclosure 1, item 3 the RM-1000 radiation monitors are used for the Containment High Range Post Accident Monitors.

053 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Darbali)

Responder: Slifer Monitoring Instrumentation - SE Please identify all FSAR sections that apply to the RM- Date: 4/19/2010 Section 7.5.2 1000. The containment high range post accident radiation Responsibility: NRC monitors are discussed in FSAR amendment 98 sections 7.5 and 12.3.

054 (SB 4/19/2010 Responder: Slifer Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE in

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Please describe all the different environments in which the The only safety-related application for the RM-1000 NRC Review Section 7.5.2 RM-1000 will be required to operate. Please group these is the Containment High Range radiation monitors.

environments into two categories (a) Harsh environment, The Containment High Range radiation monitors will per 10 CFR 50.49, and (b) Mild Environment. be installed in the Main Control Room, a mild environment. The detectors will be installed remotely in the containment.

For WBN Unit 2, a mild environment is defined as:

A defined room or building zone where (1) the temperature, pressure, or relative humidity resulting from the direct effects of a design basis event (DBE)

(e.g, temperature rise due to steam release) are no more severe than those which would occur during an abnormal plant operational condition, (2) the temperature will not exceed 130°F due to the indirect effects of a DBE (e.g., increased heat loads from electrical equipment), (3) the event radiation dose is less than or equal to 1 x 104 rads, and (4) the total event plus the 40 year TID (total integrated dose) is less than or equal to 5 x 104 rads. (Reference 3).

055 4/19/2010 Responder: Slifer Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Singh)

Monitoring Instrumentation - SE The "Qualification Test Report Supplement, RM-1000 The detectors for these loops will be located in a NRC Review Section 7.5.2 Upgrades," Document No. 04508905-1SP Rev. A states harsh environment (inside containment). The RM-that the qualification was done in accordance with IEEE 1000 will be located in the main control room, which 323-1974 and -1983. Please describe and justify all is a mild environment. The RM-1000 and associated differences in this qualification methodology and that I/F converters have been tested to the requirements endorsed by Regulatory Guide 1.209. Specifically address present in IEEE Std. 323-1983 and -1974, as well as EMI and RFI the System Requirements including EPRI TR 102323 (Sept. 94) in the design basis.

Electro-Magnetic-Interference and Radio Frequency Interference (EMI-RFI) testing was performed (the results of the testing are included in the Equipment Qualification Test Report submitted under TVA letter dated March 12, 2010, Reference 4). Since RG 1.209 was not issued until 2007, General Atomics test reports do not reference it.

For WBN Unit 2, a harsh environment is defined as:

A defined room or building zone where either (1) the temperature, pressure, and relative humidity resulting from the direct effects of a DBE (e.g.,

temperature rise due to steam release) are more severe than those which would occur during an abnormal plant operational condition, (2) the temperature will exceed 130°F due to the indirect effects of DBE (e.g., increased heat loads from electrical equipment), (3) the event radiation dose is greater than 1 x 104 rads, or (4) the total event plus the 40-year TID is greater than 5 x 104 rads.

(Reference 3) 056 April 19, 2010 Date: 5/25/10 Closed Closed Sorrento Radiation Monitoring EICB Responder: Slifer The "RM-1000 Version 1.2 Software Verification and Date: 4/19/2010 (Darbali) Validation Report," Document No. 04508006 Rev. A, is an The initial draft Software Verification and Validation Responsibility: NRC incremental report. That is to say it addresses the (V&V) report document, version 1.0, was never verification an validation for changes that resulted in issued. TVA provided the requested

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Version 1.2; therefore, the NRC has not received a Software V&V Report.

software verification and validation report for all other Attachment 4 contains the latest complete aspects of the software. Please provide the last complete proprietary version 1.1 Software V&V report verification and validation report, and all incremental (04508005). The non-proprietary version and reports after the complete report. withholding affidavit will be submitted by July 14, 2010. Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 119.

The latest proprietary version is 1.2, (an incremental report that addresses the differences from the version 1.1 report) was submitted by TVA Letter dated March 12, 2010 (Reference 4). Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 101, due June 30, 2010.

057 4/19/2010 Responder: TVA I&C Staff Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Singh)

Monitoring Instrumentation - SE Please describe the ability to change the software of the Firmware/software changes are done by connecting Requested information provided. Response path Section 7.5.2 RM-1000 at site, including all required equipment and a laptop to a port on the front of the RM-1000 and NRC to review. acceptable. TVA administrative controls (e.g., temporary digital placing the Operate/Calibrate switch in the Calibrate Further Information Requested: to submit the connections). position. The first physical barrier to access is the Please confirm that the laptop is information for location of the RM-1000 in the main control room secure and access to this laptop docketing.

which has limited access. The RM-1000 is commensurate with the Operate/Calibrate switch is located behind the access to the equipment for hinged front panel. The front panel must be opened which it will be used. Is the (held closed by two thumbscrews) to access the laptop dedicated for calibration switch. This provides a physical barrier to of radiation monitors? If the inadvertent switch operation. The system laptop is used for more than one malfunction alarm is visible locally and will application then please describe annunciate on the control board when the switch is in the equipment for which the the Calibrate position. laptop may be used. In addition please explain how software Administrative control of software/firmware updates security is assured and that only is in accordance with TVA Standard Specification the software intended for the SS-E18.15.01, Software Requirements for Real- specific application is used. Is Time Data Acquisition and Control Computer the connection to the radiation Systems, and TVA procedures SPP-9.3, Plant monitors made via a special Modifications and Engineering Change Control, and cable/connectors? Please SPP-2.6, Computer Software Control. Approved confirm that the RS-232 changes to software/firmware are implemented communication port of the utilizing the TVA work order process. radiation monitors will only be used for calibration purposes.

(1) A laptop is not used to calibrate the monitor. All Also please confirm that the TVA in-house activities (calibration, alarm setpoint radiation monitor will not be in adjustment, etc.) are performed using the touchpad operation during the calibration on the monitor. An external computer (laptop etc.) is mode. In addition please only used to perform software or firmware updates. confirm that password protection TVA does not perform software or firmware updates is provided for logging on to the using in-house resources therefore no TVA computer laptop prior to start of calibration.

is ever connected to the monitor. If software or firmware updates are required, they are approved via the TVA design change process previously described and implemented by a vendor representative under the TVA work order and Quality Assurance processes.

(2) A laptop is not used to calibrate the monitor.

(3) See the response to Item 1.

(4) See the response to Item 1.

(5) No. The connection between the computer and

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date the RM-1000 is made via a standard RS-232 cable.

(6) The RS-232 connection on the RM-1000 is used to upload new software versions and is not for calibration.

(7) A physical control switch is located behind the front panel on the front edge of the Output Board to change between Operate and Calibration modes on the RM-1000. Placing the switch in the Calibrate position makes the monitor inoperable.

(8) See the response to Item 1.

058 April 19, 2010 Date: 5/25/10 Closed Closed See FSAR Section 7.5 Instrumentation EICB (Darbali)

Responder: Slifer ML101940236, Systems Important To Safety - SE Please describe all digital communications used in the Date: 4/19/2010 Encl 1, Item 13 Section 7.5.0 installed configuration. There are no digital communications between the Responsibility: NRC RM-1000 and any other plant system or component.

Requested information provided.

NRC to review.

059 April 19, 2010 Date: Closed Closed FSAR Section 7.5.1 Post Accident EICB (Darbali)

Responder: Slifer Monitoring Instrumentation - SE Previously TVA provided the "RM-1000 Digital Radiation Date: 4/19/2010 Section 7.5.2 Processor Technical Manual," Document No. 04508100- (a) The technical manual is applicable to versions Responsibility: NRC 1TM Revision C dated October 2003. The "RM-1000 1.1 and 1.2 of the software.

Version 1.2 Software Verification and Validation Report," Requested information provided.

Document No. 04508006 Rev. A is dated April 2008. (a) (b) Version 1.2 was implemented April 1, 2008 NRC to review.

What software version does the technical manual address? (b) When was Version 1.2 implemented?

060 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE The PAMS System Requirements Specification (SysRS) Date: 4/19/2010 Section 7.5.2 references RG 1.97 Rev. 3 where the FSAR References Duplicate of Item 47 Responsibility: NRC Rev. 2. Please explain.

061 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE Reference 16 of the PAMS System Requirements Date: 4/19/2010 Section 7.5.2 Specification (SysRS) is the Unit 1 precautions Limitations Duplicate of Item 48. Responsibility: NRC and Setpoints document. When and how will the transition to the unit 2 document be made.

062 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE Please provide 00000-ICE-30156 Rev. 6. The PAMS Date: 4/19/2010 Section 7.5.2 SysRS incorporates sections of this document by Duplicate of Item 49 Responsibility: NRC reference.

063 April 19, 2010 Date: 5/25/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE How should the "shall" statements outside of the bracketed Date: 4/19/2010 Section 7.5.2 requirements be interpreted? Duplicate of Item 50 Responsibility: NRC 064 3/12/2010 Responder: Webb Date: 4/8/2010 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target By letter dated March 12, 2010 TVA stated that the TVA provided roughly a page of TVA to provide Section 7.5.2 submittal date for the D3 Analysis was April 2, 2010. target submittal date for the D3 Analysis was April 2, description as to why a D3 requested 2010. analysis is not required. The information.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date NRC requires additional information to determine the TVA to provide acceptability of this response. date when information will be docketed.

065 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target WEC to provide the P version ASAP. Awaiting for document to be Due 9/15/10 Section 7.5.2 submittal date for the FMEA was August 31, 2010. docketed by TVA.

066 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the target Per Westinghouse letter WBT-D-1961 (Reference 8), Regulations require that the TVA to provide Section 7.5.2 submittal date for the "Watts Bar 2 PAMS Software Design these items are available for audit at the NRC review be based on remaining Description (two documents, one for flat panel display and Westinghouse Rockville office. docketed material. The SRP information.

one for AC160)" was March 31, 2010. directs that reviewer to review

• WNA-SD-00250-WBT Rev. 0 (AC160) was the Software Design NRC to review submitted on TVA letter to the NRC dated August __, Specification (softimes called an information 2010 (Reference 7). SDD). provided.

• WNA-SD-00248-WBT, Rev. 0 (FPDS) was submitted on TVA letter to the NRC dated SEPT 2, NNC 8/25/10: By letter dated 2010 ( Reference 8 ). august 20, 2010, one (Reference

7) SDD has been provided.

067 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the target The following status is from the revised WB2 Regulations require that the TVA to provide Section 7.5.0 & 7.5.2 submittal date for the "Commercial Grade Dedication Common Q PAMS ISG-6 Compliance Matrix NRC review be based on requested Instructions for AI687, AI688, Upgraded PC node box and submitted in response to Item 43: docketed material. information.

flat panels." was September 28, 2010.

a. AI687, AI688 - Scheduled for September 28, 2010 TVA to provide date when

b. Upgraded PC node box and flat panel displays - information will be Per Westinghouse letter WBT-D-2024 (Reference 7), docketed.

these items are available for audit at the Westinghouse Rockville office.

c. Power supplies - Per Westinghouse letter WBT-D-2035 (Reference 12), these items are available for audit at the Westinghouse Rockville office.

To be addressed during 9/20-9/21 audit 068 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the target The following status is from the revised WB2 Awaiting for document to be TVA to provide Section 7.5.2 submittal date for the "Summary Report on acceptance of Common Q PAMS ISG-6 Compliance Matrix docketed by TVA. requested AI687, AI688, Upgraded PC node box, flat panels, and submitted in response to Item 43: information.

power supplies." was September 28, 2010.

a. AI687, AI688 - Scheduled for September 28, 2010 TVA to provide date when

b. Upgraded PC node box - Per Westinghouse letter information will be WBT-D-2024 (Reference 7), this item is available for docketed.

audit at the Westinghouse Rockville office.

c. Flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), this item is available for audit at the Westinghouse Rockville office.

d. Power supplies - Per Westinghouse letter WBT-D-2035 (Reference 12), these items are available for audit at the Westinghouse Rockville office.

To be addressed during 9/20-9/21 audit

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 069 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Awaiting for document to be Due 11/30/10 Section 7.5.2 submittal date for the "Watts Bar 2 PAMS Specific FAT docketed by TVA.

Report" was October 2010.

070 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the target Per Westinghouse letter WBT-D-1961, (Reference 8) Regulations require that the NRC to review Section 7.5.2 submittal date for the "Concept and Definition Phase V&V this document is available for audit at the NRC review be based on information Report" was March 31, 2010. Westinghouse Rockville office. docketed material. Awaiting for provided document to be docketed by WNA-VR- 00283-WBT, Rev 0 was submitted on TVA TVA.

letter to the NRC dated August __, 2010 (Reference 7). NNC 8/25/10: Requirements Phase SVVR provided by TVA V&V did not address the RTM and did not letter dated 8/20/10.

summarize anomilies. To be addressed at the 9/15 public meeting at NRC.

071 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 9/23/10 Section 7.5.2 submittal date for the "Design Phase V&V Report" was matrix against update WEC schedule. docketed by TVA.

July 30, 2010.

072 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 10/15/10 Section 7.5.2 submittal date for the "Implementation Phase V&V Report" matrix against update WEC schedule. docketed by TVA.

was September 30, 2010.

073 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 11/15/10 Section 7.5.2 submittal date for the "Integration Phase V&V Report" was matrix against update WEC schedule. docketed by TVA.

October 29, 2010.

074 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 12/15/10 Section 7.5.2 submittal date for the "Final V&V Report" was November matrix against update WEC schedule. docketed by TVA.

30, 2010.

075 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 10/15/10 Section 7.5.2 submittal date for the "Watts Bar 2 PAMS Specific FAT matrix against update WEC schedule. docketed by TVA.

Procedure" was September 30, 2010.

076 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the target Verify schedule dates for the next submittal of this Awaiting for document to be Due 9/15/10 Section 7.5.2 submittal date for the "Watts Bar 2 PAMS Specific matrix against update WEC schedule. docketed by TVA.

Processor Module Software Test" was August 31, 2010.

077 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the target The availability dates for these documents are Open TVA to provide Section 7.5.2 submittal date for seven other documents was "TDB". included in the revised WBN2 Common Q ISG-6 requested Please provide a schedule for the docketing of the Compliance Matrix submitted in response to item 43. Regulations require that the information.

remaining documents. As stated in the March 12, 2010 letter (Reference 4), NRC review be based on the dates in the matrix are the dates the documents docketed material. Awaiting for TVA to provide will be available to TVA to prepare for submittal or document to be docketed by date when being Available for Audit. They do not reflect the TVA. information will be dates the documents will be submitted to the NRC. docketed.

Expected submittal date is two weeks after TVA receives the document.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Note: There is a typo in the matrix in line item 33.

The power supply entry date says TBD. Per Westinghouse letter WBT-D-2035 (Reference 12) this item is complete and the documents are available for audit at the Westinghouse Rockville office.

The Licensing Technical Report now includes a SPM compliance matrix. Submit a revised response.

078 4/26/2010 Responder: Clark Date: 5/25/10 Open Open EICB (Garg)

FSAR Section 7.1.2.1.8 adds a reference 6 to the FSAR. (Q1) The cross reference information is corrected in Awaiting TVA response. FSAR Amd 100 However, Reference 6 is for instrument setpoint and has FSAR Amendment 100 submitted to the NRC on SSER 13 for unit 1 nothing to do with the diversity discussion on the FSAR TVA letter to the NRC dated August __, 2010 references rev. 1 of Section. We believe the TVA wants to add reference 7 (Reference 2). WCAP 13869.

which is the diversity document, WCAP 13869, "Reactor Rev. 2 is used for Protection System Diversity in Westinghouse Pressurized (Q2) WCAP-13869 Rev. 1 was previously reviewed Unit 2. Identify all Water Reactors." Please confirm this and add under WBN Unit 1 SER SSER 13 (Reference 9). the differences commitment to revise FSAR to correct the reference. (Q1) Need to identify differences to Revision 2. between Rev.1 and Also, confirm whether this WCAP has been reviewed by Rev.2 and justify NRC, if yes, provide reference and if not, then submit the (Q3) Westinghouse confirmed the applicability of this their acceptability.

WCAP to NRC. (Q2) Also provide the justification for this WCAP to Watts Bar Unit 2 in letter WBT-D-1321, reference to WBN2. (Q3) Final Response to WBT-TVA-0713 Unit 2 WCAP Reviews, dated December 2, 2009 (Reference 10).

079 4/26/2010 Responder: Clark Date: 5/25/10 Closed Closed EICB (Garg)

FSAR Section 7.1.2.1.9, Trip Setpoints, adds reference to (Q1) WBN Unit 2 is licensed based on WBN Unit 1. This item is closed 3, 4, and 5. However, reference 3 was deleted by FSAR The WBN Unit 1 licensing basis is ISA-DS-67.04- as it will be amendment 81. Reference 4 has been changed to ISA- 1982. Therefore this methodology is used for the reviewed under DS-67.04-1982. Justify applicability of this standard for same SSDs for WBN Unit 2. This maintains item 154. FSAR WBN 2.(Q1) Why the latest ISA standard endorsed by consistency in the licensing bases for both units. Amd 100 NRC has not been used? (Q2) Also reference 5 is a topical report for Eagle 21, system. Please confirm that (Q2) Please refer to the response to Q1.

this topical report also discusses the setpoint for Eagle 21 system and whether it meets the recent guidance for the (Q3) FSAR Reference 4 is the Eagle 21 Topical setpoint issued by the staff. (Q3) Also, W setpoint Report. FSAR Reference 5, WCAP-17044, methodology do not provide discussion on the AS Found Westinghouse Setpoint Methodology for Protection Tolerance and As left value determination and how these Systems Watts Bar Unit 2 submitted under TVA values are used for the instrument operability, therefore, letter to the NRC dated February 12, 2010 add the discussion of these topics in the FSAR. (Q4) and (Reference 11) discusses the setpoint methodology add reference to other documents if it is discussed in some used for Eagle 21 loops.

other document. (Q5) Provide this document to the staff for review and approval. (Q6) (Q4) (Q4) FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August __,

2010 (Reference 2) incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

(Q5) Please refer to the response to Q4.

(Q6) EEB-TI-28, Setpoint Methodology was submitted in TVA letter to the NRC dated May 13, 2010 (Reference 12).

080 4/26/2010 Responder: WEC Open Open EICB (Singh) FSAR Table 7.1-1, Note 12 has been added to the table A revised note was included in the 7/30 letter along NRC review.

but it's justification has not been provided to the staff for with justification for the note.

review and approval.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 081 5/6/2010 Responder: Merten/WEC Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE The PAMS Licensing Technical Report (WNA-LI-00058- The codes and standards documents listed in ML101600092 Item No.1: There TVA to provide Section 7.5.2 WBT Rev. 0, Dated April 2010), in Section 7, lists codes Section 7 of the Common Q PAMS Licensing are three sets of regulatory requested and standards applicable to the Common Q PAMS. This Technical Report are the documents that the criteria that relate to a Common information.

list contains references to old revisions of several Common Q platform was licensed to when the NRC Q application (e.g. WBN2 regulatory documents, for example: approved the original topical report and issued the PAMS): TVA to provide (1) RG 1.29 - September 1978 vs. March 2007 approved SER. The WBN Unit 2 Common Q PAMS (a) Common Q platform date when (2) RG 1.53 - June 1973 vs. November 2003 is designed in accordance with the approved components - Common Q TR information will be (a) IEEE 379-1994 vs. -2000 Common Q topical report and approved SER and the (b) Application Development docketed.

(3) RG 1.75 - September 1975 vs. February 2005 codes and standards on which the SER was based. Processes - Common Q SPM (a) IEEE 384-1992 vs. -1992 Since the current versions referenced are not (c) Application Specific - current (4) RG 1.100 - June 1988 vs. September 2009 applicable to WBN Unit 2, there is no basis for a regulatory criteria (a) IEEE 344-1987 vs. -2004 comparison review. The Common Q Topical Report (5) RG 1.152 - January 1996 vs. January 2006 and associated appendices (a) IEEE 7-4.33.2-1993 vs. -2003 Bechtel to develop a matrix and work with primarily addressed (a) and (b).

(6) RG 1.168 - September 1997 vs. February 2004 Westinghouse to provide justification. The Common Q SER states:

(a) IEEE 1012-1986 vs. -1998 (b) IEEE 1028-1988 vs. -1997 Appendix 1, Post Accident (7) IEEE 279-1991 vs. 603-1991 Monitoring Systems, provides (8) IEEE 323-1983 vs. -1974 (RG 1.89 Rev. 1 June 1984 the functional requirements and endorses 323-1974) conceptual design approach for However, LIC-110, "Watts Bar Unit 2 License Application upgrading an existing PAMS Review," states: "Design features and administrative based on Common Q programs that are unique to Unit 2 should then be components (page 58, Section reviewed in accordance with the current staff positions." 4.4.1.1, Description)On the Please identify all differences between the versions basis of the above review, the referenced and the current staff positions. Please provide staff concludes that Appendix 1 a justification for the acceptability PAMS with respect to does not contain sufficient these differences. information to establish the generic acceptability of the proposed PAMS design (page 56, Section 4.4.1.3, PAMS Evaluation)

The NRC did not approve the proposed PAMS design. Section 6, References, and Section 7, Codes and Standards Applicable to the Common Q PAMS, of the PAMS Licensing Technical Report contain items that are not the current regulatory criteria.

Please provide an explanation of how the WBN2 PAMS conforms with the application specific regulatory criteria applicable to the WBN2 PAMS design. For example IEEE Std. 603-1991 Clause 5.6.3, Independence Between Safety Systems and Other Systems, and Clause 6.3, Interaction Between the Sense and Command Features and Other Systems, contain application specific requirements that must be addressed by a PAMS system.

Awaiting TVA Response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 082 5/6/2010 Responder: WEC Date: 6/18/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE The PAMS Licensing Technical Report (WNA-LI-00058- These components can be found in the Summary Regulations require that the Updated Section 7.5.2 WBT Rev. 0, Dated April 2010), in Section 2.3, lists Qualification Report Of Hardware Testing For NRC review be based on compliance matrix hardware/software changes to the Common Q PAMS Common Q Applications, 00000-ICE-37764, Rev 3 docketed material. Awaiting for provided. Awaiting previously reviewed by the NRC. However the Common Q and document to be docketed by WEC submittal of ISG-6 Compliance Matrix does not contain activities that TWICE Qualification Status Report, WNAQR-00011- TVA. documents to TVA.

address qualification of all changes specifically: SSP Per Westinghouse letter WBT-D-2024, (Reference __) dated June 9, 2010, these NNC 8/9/10: per telephone documents are available for audit at the conversation on 8/5/10, it is not Westinghouse Rockville Office. clear how Westinghouse Commercial Grade Dedication TVA provided information by letter dated July 30, Plans and Reports for Digital 2010 (ML102160349) - See Enclosure 1 Item No. 7. I&C. Westinhouse agree to present to the NRC in a public Revision 1 of the Licensing Technical Report meeting on August 17, 2010, provides additional detail on the platform specific to and explanation of how their WBN2 and references to the evaluation system addreses regulatory documentation. criteria for both commercial grade dedication and equipment qualification.

NNC 8/25/10: In the August 17, 2010 public meeting Westinghouse stated that the CDi were the plans. The NRC requested that the plans and associated reports be docketed.

083 May 6, 2010 Date: 6/18/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: WEC Monitoring Instrumentation - SE Please identify all FPGAs in the new or changed PAMS Date: 5/6/2010 Section 7.5.2 hardware. The FPGAs used in the Common Q PAMS AC160 Responsibility: TVA module are listed in Westinghouse letter WBT-D-2166, (Attachment 5), which provides both the proprietary and non-proprietary information.

Attachment 6 (provided by Reference 11) contains the affidavit for withholding for WBT-D-2166-P-Attachment (contained in Attachment 5)..

Additionally, Westinghouse states in, Westinghouse Letter WBT-D-2170, (Reference 10) that their review of Flat Panel displays and PC Node Boxes concluded that they do not contain any FPGAs.

084 May 6, 2010 Date: 6/18/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Carte)

Responder: Clark Monitoring Instrumentation - SE Please provide: TVA Design Criteria WB-DC-30-7 Rev. 22, Date: 5/6/2010 Section 7.5.2 Post Accident Monitoring Instrumentation. Attachment 5 contains Design Criteria WB-DC-30-7 Responsibility: TVA Rev. 22, Post Accident Monitoring Instrumentation.

Document received 085 5/6/2010 Responder: WEC Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE Please provide a detailed description of the PAMS MTP Is the WEC ISG4 evaluation inadequate? A response will be provided by Need WEC to Section 7.5.2 data link to the plant computer. This description should 10/31/10 provide make and identify all equipment (model & version) and describe the Operation of the MTP as a barrier device. MTP Fails model information functions that each piece of equipment performs. This as a barrier device. Describe what prevents a MTP NNC 8/11/10: Design after FAT.

description should be of sufficient detail for the NRC to failure from propagating to the AC160? information should be avaialble

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date independently evaluate the statements made in WNA-LI- now. By letter dated July 30, NNC 8/25/10:

00058-WBT Rev. 0, Section 5.3. Node loss on the bus? Bus loss? 2010 (ML102160349) TVA Disagree with path stated that the MTP was forward input by Revise the ISG4 section of the Licensing Technical connected to a Red Hat Linux TVA above. An Report (Rev. 2) to provide a more detailed Server (see Enclosure 1, Item explanation is description of the MTP as a barrier device. No. 14 part b.). It is presumed about the design is that this server is not safety- needed.

related. IEEE 603-1991 Clause 5.6.3(1) states, "Isolation devices used to affect a safety system boundry shall be classified as part of the safety system."

Please describe how the MTP serves as the isolation device.

086 5/6/2010 Responder: WEC Date: 5/24/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE The PAMS Licensing Technical Report (WNA-LI-00058- The regulatory documents listed in the Common Q The response does not address TVA to provide Section 7.5.2 WBT Rev. 0, Dated April 2010), in Section 6, lists PAMS Licensing Technical Report are the the request. This request was requested references applicable to the Common Q PAMS. This list documents that the Common Q platform was regarding guidance that did not information.

contains references to old revisions of several regulatory licensed to when the NRC approved the original exist at the time that the CQ documents, for example: topical report and issued the approved SER. The topical report was reviewed. The TVA to provide (1) DI&C-ISG04 - Rev. 0 (ML072540138) vs. Rev. 1 WBN Unit 2 Common Q PAMS is designed in WBN2 PAMS applicaton must date when (ML083310185) accordance with the approved Common Q topical address current regulatory information will be However, LIC-110, "Watts Bar Unit 2 License Application report and approved SER and the regulatory criteria. docketed.

Review," states: "Design features and administrative documents on which the SER was based. Since the programs that are unique to Unit 2 should then be current versions referenced are not applicable to reviewed in accordance with the current staff positions." WBN Unit 2, there is no basis for a comparison Please identify all differences between the versions review.

referenced and the current staff positions. Please provide a justification for the acceptability PAMS with respect to Rev 0 of the Licensing Technical Report references these differences. Rev. 1 of ISG4 087 May 6, 2010 Date: 5/24/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Darbali)

Responder: Slifer Monitoring Instrumentation - SE Regarding the Sorrento RM-1000 Digital Radiation Date: 5/6/2010 Section 7.5.2.

Processor: Please identify the model and version to be The rate meter is model RM-1000. The software is Responsibility: TVA installed. Please include explicit identification of software version 1.2 version.

088 May 6, 2010 Date: 5/24/10 Closed Closed FSAR Section 7.5.1 Post Accident EICB (Darbali)

Responder: Slifer Monitoring Instrumentation - SE Regarding the Sorrento RM-1000 Digital Radiation Date: 5/6/2010 Section 7.5.2.

Processor: Please provide prior software V&V reports. See response to item 56 Responsibility: TVA The latest report only addresses Version 1.2.

089 5/6/2010 Responder: Clark Open Open NNC: Docketed response states that EICB (Carte) the applicable FSAR Sections are:

What FSAR functions are implemented using Foxboro The list of FSAR functions is listed in TVA letter NRC review 5.6 -

Intelligent Automation (IA)? dated March 12, 2010, Enclosure 1, item 12 7.2.2.3.2 - Garg 7.2.2.3.3 - Garg FSAR Section 7.7.11 will add a discussion of the 7.2.2.3.4 - Garg DCS. 7.2.2.3.5 - Garg 7.2.3 - Garg

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date See item 4 for questions on failure modes and mesh 7.6.8 -

network. 7.7.1.6 -

7.7.1.7 -

7.7.1.8 -

9.3.4.2.1.C -

10.4.7.2 -

090 5/6/2010 Responder: Clark Date: 5/25/10 Open Open EICB (Carte)

What FSAR Systems are implemented using Foxboro The list of FSAR functions is listed in TVA letter NRC review Intelligent Automation (IA)? dated March 12, 2010, Enclosure 1, item 12 FSAR Section 7.7.11 will add a discussion of the DCS.

See item 4 for questions on failure modes and mesh network.

091 May 20, 2010 Date: 5/25/10 Closed Closed EICB (Darbali)

Responder: Clark TVA to submit excerpts of EDCRs 52421, 52987, 52321, Two EDCRs have been Item is Closed and 52351 and 52601 1. Attachment 6 contains the EDCR 52421 excerpt submitted. TVA has agreed to replaced by items submit the remaining EDCRs. 103, 104 and 118.

2. Attachment 7 contains the EDCR 52987 excerpt

3. EDCR 52321 is scheduled to be issued Oct 13, 2010. Submittal of EDCR 52321 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 103 due October 31,2010.

4. EDCR 52351 is scheduled to be issued November 30, 2010. Submittal of EDCR 52351 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 104 due December 15, 2010.

5. Attachment 8 contains the EDCR 52601 (RVLIS) excerpt. The RVLIS EDCR has been split into two EDCRs. The second EDCR is 55385. Submittal of EDCR 55385 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 118 due November 15, 2010.

092 5/20/2010 Responder: Hilmes Open Open DORL (Bailey) TVA to review Licensee Open Item list and determine Next review due 6/18/10 Continuous review which items are proprietary. as items are added 093 May 20, 2010 Date: 5/25/10 Closed Closed EICB (Garg)

Responder: Knuettel TVA to submit a letter committing to include setpoint methodology discussion in the FSAR no later than Letter Sent 5/25/10 amendment 100.

094 5/20/2010 Responder: Clark Date: 5/25/10 Closed Closed EICB (Garg) TVA to locate and provide information on the TMI action This item is described in FSAR amendment 98, NRC staff will review.

item to add an anticipated reactor trip on turbine trip to the Section 7.2.1.1.2 item 6 page 7.2.9, and Table 7.2-1 design bases in the FSAR item 14, page 7.2-39.

095 B (D May 20, 2010 Date: Closed Closed Responder:

ar

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date TVA to review SER supplements 5 and 14 item 7.8.1 and Response is satisfactory. Item NRC Review supplement 4 item 7.8.4 and confirm if they are identical to Q1: Monitoring of the reactor coolant system relief closed.

Unit 1. If not provide differences. valve position is the same as Unit 1.

Q2: The reactor trip on turbine trip is the same as Unit 1.

096 5/20/2010 Responder: Open Open EICB (Darbali)

TVA to provide information on implementation of IEN 79- IEN 79-22 is not specifically listed or discussed in the Response provided. NRC staff This items will be 22 and how it is addressed in the FSAR WBN Unit 1 UFSAR or Unit 2 FSAR. IEN 79-22 is to review response. closed upon the one of the precursors to 10CFR50.49 environmental resolution of item qualification. The initial SQN and WBN Unit 1 See Follow up question 283. 283.

response was developed prior to TVA implementing 10CFR50.49. As such, the discussion of safety-related actuations is no longer valid. In implementing 10CFR50.49, TVA upgraded susceptible safety-related devices located in harsh environments to fully qualified devices. For WBN Unit 2, only fully qualified safey-related devices are installed in areas susceptible to a high energy line break. The non-safety-related device/systems within the scope of IEN 79-22 are:

1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

Failure of these systems/devices due to a high energy line break is fully addressed in Chapter 15, Accident Analysis of the WBN Unit 2 FSAR.

097 May 20, 2010 Date: Closed Closed EICB (Darbali)

Responder:

TVA to review SER Supplement 7 item 7.4.25 deviation on Response is satisfactory. Item Aux Control Room display of RCS cold leg temperature for The deviation to not have RCS cold leg temperature closed.

applicability to Unit 2. displayed in the Auxiliary Control Room was approved as part of the WBN Unit 1 initial license.

WBN Unit 2 complies with the WBN Unit 1 Llicensing basese and this deviaition is applicable to Unit 2.

098 May 25, 2010 Date: Closed Closed EICB (Darbali)

Responder:

Unit 1 SER Supplement 7, RCS Cold Leg Temperature Response is satisfactory. Item instrumentation. How does Unit 2 address this change? Refer to the response to Item 13 11 above. closed.

099 April 12, 2010 Date: Closed Closed Closed to Item 129 DORL (Bailey)

Responder: WEC TVA will provide non-proprietary versions of the following Common Q attached proprietary documents and the affidavits for the proprietary documents by June 30, 2010.

1. System Design Specification WNA-DS-01667-WBT, Rev. 1

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date

2. System Requirements Specification WNA-DS-01617-WBT, Rev. 1

3. Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix dated March 4, 2010

4. Watts Bar Unit 2 (WBN2) Post Accident Monitoring System (PAMS) Licensing Technical Report LTR-RCPL-10-XX

5. Software Requirements Specification WNA-SD-00239-WBT, Rev. 1 100 5/20/2010 Responder: WEC Closed Closed EICB (Carte)

The following Common Q proprietary documents listed in The documents, and affidavits for withholding for the TVA has not yet docketed all the response and the affidavits for the proprietary listed documents were submitted to the NRC on TVA items requested.

documents will be provided by April 9, 2010. letter to the NRC dated April 8, 2010.

1. System Design Specification WNA-DS-01667-WBT, Rev. 1

2. System Requirements Specification WNA-DS-01617-WBT, Rev. 1

3. Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix dated March 4, 2010

4. Watts Bar Unit 2 (WBN2) Post Accident Monitoring System (PAMS) Licensing Technical Report LTR-RCPL-10-XX

5. Software Requirements Specification WNA-SD-00239-WBT, Rev. 1 101 4/12/2010 Responder: Slifer Open Open TVA is working with the vendor to DORL (Bailey) meet the 6/30 date, however there is The non-proprietary versions of the following RM-1000, The documents, and affidavits for withholding for the NRC review the potential this will slip to 7/14.

Containment High Range Post Accident Radiation Monitor listed documents were submitted to the NRC on TVA documents will be provided by June 30, 2010. letter to the NRC dated July 15, 2010.

1. V&V Report 04508006A

2. System Description 04508100-1TM

3. Qualification Reports 04508905-QR, 04508905-1 SP, 04508905-2SP, 04508905-3SP

4. Functional Testing Report 04507007-1TR 102 May 24, 2010 Date: 5/24/10 Closed Closed EICB (Carte)

Responder: WEC Provide a schedule for resolution of items 80, 82 and 83 Date:

Item 80 - no later than July 23, 2010 Responsibility:

Item 82 - no later than July 23, 2010 Item 83 - no later than July 23, 2010 103 EICB 5/27/2010 Responder: Clark Date: 5/27/10 Open Open Submittal date is based on current (Darbal EDCR scheduled issue date.

i) TVA to submit excerpts of EDCR 52321 EDCR is scheduled for issue Due 10/31/10 10/13/10 104 EICB 5/27/2010 Responder: Clark Date: 5/27/10 Open Open Submittal date is based on current (Darbal EDCR scheduled issue date.

i) TVA to submit excerpts of EDCR 52351 EDCR is scheduled for issue Due 12/15/10 11/30/10 105 April 29, 2010 Date: Closed Closed EICB (Garg)

Responder: Langley Provide As-Found/As-Left methodology procedure Date: 5/27/10 Submitted copy of TI-28 May 14/2010. Responsibility: NRC Replaced with new open item 176.

106 EIC May 6, 2010 Date: 5/25/10 Closed Closed B

(Cart Responder: Davies e)

Confirm that the Unit 1 and Unit 2 CERPI systems utilize Date:

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date the same processor (AC110 or AC160). Westinghouse Unit 2 Drawing 6D31420, Watts Bar Responsibility:

2- CERPI AC160 Chassis Configuration, Rev. 2, shows the processors are model AC160, which are the same that are utilized for Unit 1, as shown on Westinghouse drawing 2D82995 Rev. 0, Watts Bar CERPI AC 160 Chassis Configuration.

107 May 6, 2010 Date: 5/28/10 Closed Closed EICB (Darbali)

Responder: Clark Describe any control functions associated with the RM- Requested information provided. See 1000 radiation monitors. The RM-1000 radiation monitors do not provide any NRC to review. ML101940236, control functions. Encl 1, Item 29.

108 May 6, 2010 Date: 5/25/10 Closed Closed EICB (Garg)

Responder: Webb/Hilmes We are requested to docket the fact that the appropriate This item is to be worked with This item is closed sections of chapter 7 of the FSAR will be updated to This item is addressed as follows: item 51. as it will be include references to: reviewed under 109. FSAR Amendment 100 which was item 154. FSAR

a. TI-28 to address as-found/as-left issues submitted on TVA letter to the NRC dated Amd 100

b. RISC 2006-17 August __, 2010 incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

2. TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February 2, 2010.

109. 5/6/2010 Responder: NA Open Open EICB b

(Carte) The reviewer was unable to identify the sections of the TVA Provided response J. Wiebe accepted this action. NRC Action FSAR that correspond to the standard review plan sections7.9.

109. 5/6/2010 Responder: NA Open Open a EICB The reviewer was unable to identify the sections of the TVA Provided response J. Wiebe accepted this action. NRC Action (Darbali) FSAR that correspond to the standard review plan sections 7.8.

110 May 6, 2010 Date: Closed Closed EICB (Garg)

Responder: Clark The reviewer was unable to locate the Eagle 21 WCAPs 12374 and 12375 for review within the NRC records. We These items were docketed under ML073550386 agreed to provide the ADAMS numbers for the submittal.

111 May 6, 2010 Date: 5/28/10 Closed Closed EICB (Carte)

Responder: Clark The reviewer was unable to locate information (SER) on Date:

the plant computer or annunciator systems and asked us The annunciator system is not described in the WBN Responsibility:

to provide the location within the FSAR where these Unit 1 UFSAR. As such it is not included in the WBN systems are described. Unit 2 FSAR.

With the exception of the ERFDS functions in section 7.5, the plant computer is not described in the WBN Unit 1 UFSAR. As such it is not included in the WBN Unit 2 FSAR.

(

112 G June 1, 2010 Date: Closed Closed

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Responder: Clark What are the differences between the Unit 1 and Unit 2 Eagle 21 Systems? This information is included in TVA letter dated March 12, 2010, Enclosure 1, Item 10.

113 6/1/2010 Responder: Clark Closed Closed EICB (Garg) Are the new model Eagle 21 power supplies installed in Yes. Attachment 9 provides a work order excerpt Attachment 9 does not show the Unit 1? and unit difference form. vendor and model no. of the Revised attachment provided on 7/30 letter. Power Supply.

114 6/1/2010 Responder: WEC Open Open EICB (Garg)

Provide the resolution of the Eagle 21 Rack 5 lockup on The following non-proprietary response was The writeup shows that there NRC to review update issue. developed from proprietary Westinghouse letter was differences between Unit 1 WBT-D-2027 (Reference 11), which provided the and 2 but was not identified to resolution of this issue. Westinghouse approved this NRC in earlier response. Are non-proprietary response via e-mail from A. Drake to there any more surprises like M. Clark on June 15, 2010. this?

As documented in WBT-D-1917, Eagle-21 Rack 5 LCP Diagnostic Failures, (Reference 14), during the factory acceptance testing for the Unit 2 Eagle-21 System, Westinghouse noted an occasional diagnostic failure while performing the parameter update function on Rack 5.

Subsequently, TVA provided to Westinghouse for testing and examination, a Loop Control Processor (LCP) board removed by TVA from Unit 1 Rack 5 for life cycle-based preventive maintenance. TVA personnel familiar with Unit 1 had indicated they had not experienced problems when performing parameter updates on Unit 1 Rack 5.

Based on Westinghouse examination and testing, a difference in hardware was identified between the Unit 1 LCP shipped to Westinghouse, the new Unit 2 Rack 5 LCP, and an older LCP (older than the Unit 1 LCP) from the Westinghouse Eagle 21 test bed.

Installed on the Unit 1 LCP was a different version of an 80287 math coprocessor chip (80287 XL).

This version of the 80287 had an improved specification for calculation speed. Use of this chip on both the Unit 2 LCP and the test bed LCP allowed proper performance of the LCP when making parameter updates using the Unit 1/Unit 2 Rack 5 software. Also, use of the slower 80287 on any of the three LCP boards caused failure in parameter update with the Unit 1/Unit 2 Rack 5 software.

Through investigation of historical records, Westinghouse found that the 80287 XL chip had been evaluated and used by its former Process Control Division (now Emerson) for this application, but the current Westinghouse documentation had not been updated. This part has now been evaluated, and the Westinghouse documentation and drawing have been revised to allow use of the 80287 XL coprocessor. The 80287 XL coprocessor has been

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date installed on the Unit 2 Rack 5 LCP, and the appropriate factory acceptance testing has been successfully conducted using this updated board.

Additionally, the LCP boards in the balance of the Unit 2 racks have been updated with the 80287 XL coprocessor.

115 2/25/2010 Responder: Clark Open Open EICB (Carte)

Provide a list of digital 1E systems that have a digital Response states that Eagle21 and the CQ PMAS The CQ PAMS SysRS (WNA- TVA to update communications path to non safety related systems and if MTP have communications links to non-safety- DS-01617-WBT Rev. 1 Figure response it has: related systems.. 2..1-1) shows that the OM has a

a. Been reviewed before for unit 1 TCP interface to non-safety.

b. Or installed in unit 1 under 50.59, or This item was identified during TVA review of Figure Please provide a list of ALL

c. Is unique to unit 2 2.2-1 of the PAMS Licensing Technical Report WNA- digital communications paths to LI-00058-WBT, Rev.0 and the figure was revised to non-safety-related systems.

remove the connection. It was addressed with Westinghouse at that time. However other Common NNC 8/12/10: The staff pinted Q PAMS documents had been issued before the out this inconsistency to TVA.

issue was identified to Westinghouse. The Licensing The staff could consider PAMS Technical has been corrected and the other Licensing Technical Report to documents will be corrected at the next revision be a correction if TVA specifically identified the Design change after documents were produced that inconsistency to the staff, or deleted the connection from the OM to plant identified where the error in the computer. SysRSs, SRS, & SDS had already been identified. This There are no communications from the Operators apppreas to be a feature in the Module to the plant computer or any other system. CQ TR appendix that was The Common Q PAMS SysRS WNA-DS-01617- carried forward to WBN2 PAMS WBT Rev. 1, Figure 2.1-1 will be revised to remove inappropriately this connection by April 1, 2011 and submitted to the NRC by April 15, 2011.

116 6/3/2010 Responder: WEC Open Open Letter sent to Westinghouse EICB (Garg) requesting the basis information and The Eagle 21 boards originally had a conformal coating. The response to this RAI was submitted in TVA letter How is the tin documentation for submittal to the However, the new boards do not. Provide the basis for to the NRC dated June 21, 2010. whisker issue is NRC.

deletion of the conformal coating. addressed. I think conformal coating was credited to protect against tin whisker issue.

117 6/3/2010 Responder: Webb/Powers Open Open EICB (Garg)

Does TVA use a single sided or double sided methodology TVA uses double-sided as-found and as-left TVA needs to for as-found and as-left instrument setpoint values. tolerances for trip setpoints as described in FSAR address that trip (RIS2006-7) amendment 100. setpoint and allowable value uncertainties are not reduced by the reduction factor for the single sided reduction factor.

118 6/8/2010 Responder: Clark Open Open Submittal date is based on current EICB EDCR scheduled issue date. Note:

TVA to submit excerpts from EDCR 55385 TVA has agreed to submit the Due 11/15/10 The RVLIS EDCR has been split into (Darbali) EDCR by 11/15/10. two EDCRs. The first EDCR is 52601 (Open Item 91) The second EDCR is 55385.

119 EIC June 10, 2010 Date: Closed Closed B

(Dar bali) Responder:

Submit the non-proprietary version of Sorrento/GA

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date software V&V report version 1.1 04508005 and withholding Provided 7/15/2010 Date: 07/29/10 affidavit Responsibility: NRC TVA provided the non-proprietary version of V&V report version 1.1 04508005 and the withholding affidavit via TVA letter dated July 15, 2010.

120 5/6/2010 Responder: Hilmes/Merten/Costley Closed Closed EICB (Carte)

In reviewing the Maintenance Test Panel (MTP) link to the TVA respinded by letter dated July 30, 2010 NNC 8/9/10: By letter dated July plant computer, the reviewer noted that the MTP software (ML102160349) - See Enclosure 1 Item No. 14: 30, 2010 (ML102160349) - See is not purely one directional in that it does allow low level Detailed discussion is provided including technical Enclosure 1 Item No. 14 -

handshaking to support the communications protocol. M. information on the data diode. a. TVA stated no new Merten/S. Hilmes information was found in See Item 85. TVA not crediting the data diode. Westinghouse documentation

a. The reviewer stated that this was a potential concern and that this information would and requested additional information on how the MTP ws be addressed in the V&V protected from feedback from the plant computer. reports, and that the final hardware drawing will be

b. The reviewer stated that in the Oconee review, it was provided. Neither of these two found that the non-safety related data diode was easier to documents will contain the credit than a software barrier. It was suggested we look at information requested. Please changing our position to credit the data diode provided it provide a detailed description of provided a physical barrier to feedback. Need OWL the MTP hardware connections Information SAH and the software that perform the communications.

c. During this discussion, the reviewer asked if we had b. The information provided information from Westinghouse that demonstrated the indicates that the MTP is ability of Common Q PAMs to withstand a data storm. A connected directly to a non-verbal response was that this was required by contract as safety-related Red Hat Linux part of the Factory Acceptance Test and would not be Server which is then connected available until the FAT was completed. Need to docket the to the data diode divices. Please verbal response and provide a date the information will be describe the secure available. Believe we stated this in the Tech Report. SAH development and operational environment of these Red Hat Linux Servers.

c. The answer is not complete.

A chattering node is one of the failure modes of an ethernet link.

The MTP is connected to a linux server over an ethernet link.

What prevents this link from locking up the MTP by a data storm?

121 5/6/2010 Responder: Webb/Webber Open Open EICB (Garg)

If not previously provided, provide the requested The information in the letter provides references to NRC Review information in items a, b and c for changes to all platforms previous submittals and a cross reference for the between Unit 1 and 2. (Specific request for information on Foxboro I/A system.

Foxboro IA). D. Webb/H. Webber

a. Describe the hardware differences between unit 1 and unit 2

b. Identify which systems have been transferred to the Foxboro Spec 200 system that utilize a different platform in Unit 1.

c. Identify the functions (ensure all control functions are addressed) that have been transferred to the Foxboro

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Spec 200 system that utilize a different platform in Unit 1.

122 June 14, 2010 Date: Closed Closed EICB (Carte)

Responder: WEC Provide a date for completing the next revision of the Common Q PAMS System Requirements Specification. This is a duplicate of NRC RAI Matrix Item 50 and is considered closed.

123 6/14/2010 Responder: Closed Closed EICB (Darbali)

Safety Evaluation(SE) Section 7.7.3 Volume Control Tank 1. The devices in the Volume Control Tank Level Level Control System Control System have been replaced. The Volume Follow up question is to request Control Tank Level Indication and Control functions a logic diagram 284.

1. Confirm whether or not any Instrumentation & Control have been relocated to the Foxboro IA system. The (I&C) systems or equipment have been changed in the transmitters and indicators have been replaced with Volume Control Tank Level Control System. 4-20mA technology and the transmitters have been changed to Rosemount.

2. In the original Safety Evaluation(SE), NUREG-0847 (ML072060490), Section 7.7.3, the staff addressed a 2. Upscale failure of LT-62-129A: Flow is diverted to concern that was raised by Westinghouse regarding an the holdup tank but makeup continues to maintain adverse control and protection system interaction. (a level and alarms alert the operator.

single random failure in the VCT level control system could cause the letdown flow to be diverted to the liquid holdup Upscale failure of LT-62-130A: Unlike Unit 1, the tank). Based on your responses to the staffs questions makeup control system uses inputs from both LT related to this concern, the staff considered the issue 130A and LT-62-129A. This results in a more robust resolved. Confirm that your responses are applicable to design that eliminates a single point of failure for LT-Unit 2. 62-130A. If transmitter LT-62-130A fails >20mA, the system disregards the input and uses the LT 129A signal for control. If transmitter LT-62-130A is high but <20 mA, the deviation between the two causes an alarm, and the diverter valve loop and makeup control both use the last good value of the average. Once the level goes high or low, alarms on LT-62-129A alert the operator to take action to mitigate.

124 6/14/2010 Responder: Closed Closed EICB (Darbali)

SE Section 7.7.5 IE Information Notice 79-22 Duplicate of item 96

1. In the original SE, Section 7.7.5, the staff determined that Information Notice 79-22 was resolved based on your statement that the control and logic functions of the Watts Bar plant were identical to the Sequoyah plant, thus making the Sequoyah evaluation applicable to Watts Bar.

Confirm that your statements regarding the control and logic functions are applicable to Unit 2s control and logic functions or describe any changes and why they are acceptable.

125 6/14/2010 Responder: Open Open EICB (Darbali)

SE Section 7.7.8 AMSAC 1. The AMSAC system was not previously installed Staff is reviewing response. NRC review in Unit 2. EDCR 52408 installs the system.

1. Confirm whether or not any I&C systems or equipment Attachment 3 contains excerpts from the EDCR that have been changed in the AMSAC? Describe the describe the Unit 2 system and how it differs from changes, if any. the Unit 1 system.

2. NUREG-0847, Supplement 14 (ML072060486), 2. EDCR 52408 incorporates the AMSAC system documents the staffs review of FSAR Amendment 81 that into the Unit 2 drawings.

found that the AMSAC automatic initiation signal [to start the turbine-driven and motor-driven AFW pumps] was not

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date added to the logic diagram for the AFW system shown in FSAR Figure 7.3-3, Sheet 2. The issue was resolved in Amendment 88. Confirm that this signal has been incorporated in the Unit 2 drawings.

126 June 14, 2010 Date: Closed Closed EICB (Darbali)

Responder:

SE Section 7.8 NUREG-0737 Items No I&C components or systems are affected by this

1. In the SER Cross Reference To FSAR table (06-25-09), change.

section 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12) has the following scope of change:

Common Station Service Transformers (CSST) A and B, eight (8) vital inverters vs. four, fifth DG will be removed from FSAR, Double breaker, double breaker scheme of the new Watts Bar 500kV switchyard.

Is any I&C system or component affected in the scope of this change?

127 6/16/2010 Responder: WEC/Clark Open Open EICB (Garg)

Provide the status of the Eagle 21 Rack 2 RTD accuracy The following non-proprietary response was NRC to review.

issue. developed from proprietary Westinghouse letter WBT-D-2034 (Reference 15), which provided the details of this issue. Westinghouse approved this non-proprietary response via e-mail from A. Drake to M. Clark on June 16, 2010.

During the Watts Bar Unit 2 Eagle 21 Factory Acceptance Test (FAT) of Rack 2 it was discovered that the narrow range Resistance Temperature Detector (RTD) temperature inputs were consistently reading about 0.2 °F higher than expected.

Investigation revealed that these inputs are configured in the Loop Calculation Processor software as a shared RTD. This is incorrect. Rack 2 RTD's are not shared. Racks 6, 10 and 13 RTD's are. Configuration as a shared RTD input alters the equation used for the temperature calculation. Watts Bar Unit 1 uses identical software to Unit 2.

Further investigation by Westinghouse showed this configuration error causes the Narrow Range Temperatures for only Division I to read 0.2 to 0.27

°F higher over the Narrow Range span of 510-650

°F. The 0.2 °F shift affects Thot and Tcold equally and thus will not affect the indication of Delta T.

Tavg will indicate high by 0.2 °F which will decrease the Over temperature and Overpower set points; which is in the conservative direction.

128 6/18/2010 Responder: WEC Open Open TVA Unit 1 has to address first and EICB (Garg)

Unit 2 will follow Unit 1.

Submit the report on the final resolution of the Eagle 21 Staff will issue SE Rack 2 RTD input issue with this as an open item.

Due 12/3/10 129 6/12/2010 Responder: WEC Open Open DORL (Bailey) TVA will provide non-proprietary versions of the following The documents, and affidavits for withholding for the Due 7/16/10 Common Q attached proprietary documents and the listed documents were submitted to the NRC on TVA

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date affidavits for the proprietary documents by June 30, 2010. letter to the NRC dated July 14, 2010.

1. System Design Specification WNA-DS-01667-WBT, Rev. 1 Andy to Verify the documents have been submitted

2. System Requirements Specification WNA-DS-01617- and then close this item.

WBT, Rev. 1

3. Software Requirements Specification WNA-SD-00239-WBT, Rev. 1 130 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: table 4.3-1 to FSAR Amendment 100 submitted to the NRC on FSAR Amd 100 add ID and OD nomenclature to thimble guide tube TVA letter to the NRC dated August __, 2010 added dimensions . the ID and OD nomenclature.

131 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR 3.10 FSAR Amendment 100 submitted to the NRC on FSAR Amd 100 references to eliminate (LATER) for document numbers. TVA letter to the NRC dated August __, 2010 updated the reference document number information.

132 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR 3.10 FSAR Amendment 100 submitted to the NRC on FSAR Amd 100 to correct differences between the list on page 3.10-4 and TVA letter to the NRC dated August __, 2010 the numbering refrenced by the text below the list. corrected the numbering in the text.

133 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR 3.10 FSAR Amendment 100 submitted to the NRC on FSAR Amd 100 to remove references to IEEE 344-1987. TVA letter to the NRC dated August __, 2010 removed the reference to IEEE 344-1987.

134 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR Table FSAR Amendment 100 submitted to the NRC on FSAR Amd 100 1.3-3 to reflect modifications to WBN2 . TVA letter to the NRC dated August __, 2010 updated the table to reflect the WBN2 modifications.

135 6/30/2010 Responder: Clark Closed Closed EICB TVA committed to add in Amendment 100 a reference to FSAR Amendment 100 submitted to the NRC on Amendment 100 received.

(Darbali) 7.3.1.1.1 in 6.2.5.2.b. TVA letter to the NRC dated Sept 1, 2010 added the reference.

136 6/30/2010 Responder: Clark Closed Closed EICB (Darbali)

TVA committed to replace in Amendment 100 the terms FSAR Amendment 100 submitted to the NRC on Amendment 100 received.

"service water" and "emergency raw cooling water" where TVA letter to the NRC dated Sept 1, 2010 updated they are used incorrectly with "Essential Raw Cooling the "service water" and "emergency raw cooling Water" in sections 7.4, 6.2.1, Table 3.7-25, Table 9.3-3, water" nomenclature as required to read essential Table 15.4-14, 1.9.2.7, 7.3.2.2.5 and 11.2.4. raw cooling water.

137 6/17/2010 Responder: WEC Open Open EICB (Carte)

Several WBN2 PAMS documents contain a table titled, (a) The table is to show the document hierarchy (i.e., Carte accepted this response 9/1 TVA to provide Document Traceability & Compliance. what documents are predecessors to the document date when in relationship to the design life cycle). information will be (a) Please explain the purpose of this table. docketed.

(b) This table is showing a hierarchical relationship (b) Please describe how this table is different than a between documents. These documents are also in reference list. the reference list along with other documents that have no hierarchical relationship with the document.

(c) What does it mean for a document to be listed in this table? (c) This question is similar to (a). It is to identify the documents that are predecessors to this document in relationship to the design life cycle.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date 138 6/17/2010 Responder: WEC Open Open EICB (Carte)

By letter dated February 3, 2010, Westinghouse informed To be addressed during 9/20-9/21 audit. TVA to provide TVA that certain PAMS documentation has been date when completed. information will be docketed.

(a) The draft ISG6 states that a commercial grade dedication plan should be provided with an application for a Tier 2 review.

By letter dated February 5, 2010, TVA stated that the commercial grade dedication plan was included in the Common Q Topical Report Section 11, Commercial Grade Dedication Program. Section 11 includes a description of the Common Q Commercial Grade Dedication Program, and states: A detailed review plan is developed for each Common Q hardware or software component that requires commercial grade dedication.

Please provide the commercial grade dedication plans for each Common Q hardware or software component that has not been previously reviewed and approved by the NRC.

(b) The draft ISG6 states that a commercial grade dedication report should be provided within 12 months of requested approval for a Tier 2 review.

(i) Please provide 00000-ICE-37722 Rev. 0, Commercial Grade Dedication Report for the QNX Operating System for Common Q Applications.

(ii) Please provide WNA-CD-00018-GEN Rev. 3, Commercial Dedication Report for QNX 4.25G for Common Q Applications.

139 6/17/2010 Responder: WEC Open Open WBN2 PAMS System Requirements EICB (Carte)

Specification The WBN2 PAMS System Requirements Specification (a) The table is to show the document hierarchy (i.e., TVA to provide (WBN2 PAMS SysRS) contains a table (see page iii) titled, what documents are predecessors to the document date when TVA docketed WNA-DS-01617-WBT Document Traceability & Compliance, which states that in relationship to the design life cycle). information will be Rev. 1, RRAS Watts Bar 2 NSSS the WBN2 PAMS SysRS was created to support no docketed. Completion Program I&C Projects documents. Please explain. (b) This table is showing a hierarchical relationship Post Accident Monitoring System-between documents. These documents are also in System Requirements Specification, the reference list along with other documents that dated December 2009.

have no hierarchical relationship with the document.

(c) This question is similar to (a). It is to identify the documents that are predecessors to this document in relationship to the design life cycle.

Westinghouse to revise this item to state that these are internal requirements and not intended to reference TVA documents.

140 6/17/2010 Responder: WEC Open Open WBN2 PAMS System Requirements EICB (Carte)

Specification The first requirement in the WBN2 PAMS SysRS (i.e., Addressed in the 9/15 public meeting and 9/20 - 9/21 TVA to provide R2.2-1) states: The PAMS shall be capable of operation audit. A detailed explination will be provided. date when TVA docketed WNA-DS-01617-WBT during normal and abnormal environments and plant information will be Rev. 1, RRAS Watts Bar 2 NSSS operating modes. The rational for this requirement is that docketed. Completion Program I&C Projects it is necessary to meet Regulatory Guide (RG) 1.97. Post Accident Monitoring System-System Requirements Specification,

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date What document specifies which RG 1.97 variables are dated December 2009.

implemented in the Common Q based WBN2 PAMS?

141 June 17, 2010 Date: Closed Closed WBN2 PAMS System Requirements EICB (Carte)

Responder: Specification deleted TVA docketed WNA-DS-01617-WBT Rev. 1, RRAS Watts Bar 2 NSSS Completion Program I&C Projects Post Accident Monitoring System-System Requirements Specification, dated December 2009.

142 6/17/2010 Responder: WEC Open Open WBN2 PAMS System Requirements EICB (Carte)

Specification The applicable regulatory guidance for reviewing the Addressed in the 9/15 public meeting and 9/20 - 9/21 TVA to provide WBN2 PAMS SysRS would be IEEE 830 as endorsed by audit. A detailed explination will be provided. date when TVA docketed WNA-DS-01617-WBT Regulatory Guide 1.172 and BTP 7-14 Section B.3.3.1, information will be Rev. 1, RRAS Watts Bar 2 NSSS Requirements Activities - Software Requirements docketed. Completion Program I&C Projects Specifications. IEEE 830-1994 Section 4.3.8, Post Accident Monitoring System-Traceable, states: A [requirements specification] is System Requirements Specification, traceable of the origin of each of its requirements is dated December 2009.

clear How did TVA ensure the traceability of each requirement in the WBN2 PAMS SysRS.

143 6/17/2010 Responder: WEC Open Open WBN2 PAMS System Requirements EICB (Carte)

Specification The WBN2 PAMS Software Requirements Specification Addressed in the 9/15 public meeting and 9/20 - 9/21 TVA to provide (WBN2 PAMS SRS - ML101050202) contains a table (see audit. A detailed explination will be provided. date when TVA docketed WNA-DS-01617-WBT page iii) titled, Document Traceability & Compliance, information will be Rev. 1, RRAS Watts Bar 2 NSSS which states that the WBN2 PAMS SRS was created to docketed. Completion Program I&C Projects support the three documents identified (one of which is the Post Accident Monitoring System-WBN2 PAMS SysRS). Section 1.1, Overview, of the System Requirements Specification, WBN2 PAMS SRS states: This document describes dated December 2009.

requirements for the major software components (a) Please list and describe each of the major software components. Please include a description of any NRC review for each of these components.

(b) Please list and describe each of the other software components. Please include a description of any NRC review for each of these components.

(c) What other documents contain the requirements for the other software components?

The WBN2 PAMS System Design Specification (WBN2 PAMS SDS) contains a table (see page iii) titled, Document Traceability & Compliance, which states that the WBN2 PAMS SysRS was created to support the WBN2 PAMS SysRS. Section 1.1, Purpose, of the WBN2 PAMS SDS states: The purpose of this document is to define the hardware design requirements (c) Do the WBN2 PAMS SRS and SDS, together, implement all of the requirements in the WBN2 PAMS SysRS?

(d) Please briefly describe all of the documents that implement the WBN2 PAMS SysRS.

(

144 6/17/2010 Responder: WEC Open Open WBN2 PAMS Software Requirements C

a

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Specification The WBN2 PAMS Software Requirements Specification (a) The purpose of NABU-DP-00014-GEN document NRC Review and WEC to Responses to (WBN2 PAMS SRS) contains a table (see page iii) titled, is to define the process for system level design, complete response. items a and e By letter dated April 8, 2010 Document Traceability & Compliance, which states that software design and implementation, and hardware provided. Need (ML10101050203), TVA docketed the WBN2 PAMS SRS was created to support the three design and implementation for Common Q safety b-d to be addressed at public response to b-d. WNA-SD-00239-WBT, Revision 1, documents identified (two of these documents have been system development. This document supplements meeting and audit. Will require "RRAS Watts Bar 2 NSSS provided on the docket). the Common Q SPM, WCAP-16096-NP-A. The information to be docketed. Completion Program I&C Projects, scope of NABU-DP-00014-GEN includes the design Software Requirements Specification (a) Please describe the third document (i.e., NABU-DP- and implementation processes for the application for the Post Accident Monitoring 00014-GEN Revision 2, Design Process for Common Q development. For a fuller description of the design System, dated February 2010 Safety Systems). process described in NABU-DP-00014-GEN please (ML101050202).

refer to the Design Process for AP1000 Common Q (b) Please describe the flow of information between these Safety Systems, WCAP-15927 on the AP1000 three documents. docket. This document describes the process used for the WB2 PAMS.

(c) Does the PAMS SRS implement the requirements in these three documents? (b) - (d) pending (d) Please describe if and how these three documents are (e) WBN2 PAMS Software Requirements used in the development of the PAMS Software Design Specification (WNA-SD-00239-WBT, Rev. 1) refers Description. to Document Traceability & Compliance table on page iii. This table has three entries; Design Process (e) Do the WBN2 V&V activities include verification that for Common Q Safety Systems (NABU-DP-00014-the requirements of these three documents have been GEN, Rev. 2), RRAS Watts Bar 2 NSSS Completion incorporated into the WBN2 PAMS SRS. Program I&C Projects Post Accident Monitoring System - System Requirements Specification (WNA-DS-01617-WBT, Rev. 1), and RRAS Watts Bar 2 NSSS Completion Program I&C Projects Post Accident Monitoring System - System Design Specification (WNA-DS-01667-WBT, Rev. 1).

IV&V performed a Requirements Traceability Assessment during which it reviewed Software Requirements Specification (WBN2 PAMS SRS, WNA-SD-00239-WBT, Rev. 1) against System Requirements Specification (WNA-DS-01617-WBT, Rev. 1) and System Design Specification (WNA-DS-01667-WBT, Rev. 1). Requirements within Software Requirements Specification that are referring to NABU-DP-00014-GEN, Rev 2, Design Process for Common Q Safety Systems, have also been reviewed for traceability and compliance. During IV&V's RTA effort the anomaly reports V&V-769 and V&V- 770 have been initiated and reported in the IV&V Phase Summary Report for the System Definition Phase, WNA-VR-00283-WBT, Rev. 0.

IV&V has verified that the requirements in SRS are derived from the specified documents listed in the Document Traceability and Compliance Table of WBN2 PAMS SRS.

145 6/17/2010 Responder: WEC Open Open WBN2 PAMS System Design EICB (Carte)

Specification The WBN2 PAMS System Design Specification (WBN2 Addressed in the 9/15 public meeting and 9/20 - 9/21 TVA to provide PAMS SDS) contains a table (see page iii) titled, audit. A detailed explination will be provided. date when TVA docketed WNA-DS-01667-WBT Document Traceability & Compliance, which states that information will be Rev. 1, RRAS Watts Bar 2 NSSS the WBN2 PAMS SDS was created to support the WBN2 docketed. Completion Program I&C Projects PAMS SysRS. Post Accident Monitoring System-System Design Specification, dated (a) Does the WBN2 PAMS SDS implement all of the December 2009.

hardware requirements in the WBN2 PAMS SysRS?

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date (b) Please briefly describe all of the documents that implement the hardware requirements of the WBN2 PAMS SysRS.

146 6/17/2010 Responder: Closed Closed PAMS System Requirements EICB (Carte)

Specifications deleted WBN2 PAMS documents reference generic PAMS documents, for example: WBN2 PAMS SysRS

References:

00000-ICE-30156 Rev.

6, System Requirements Specification for the Common Q Post Accident Monitoring System, and 00000-ICE-30155, Rev. 9, System Requirements Specification for the Common Q Generic Flat Panel Display 147 6/17/2010 Responder: Closed Closed PAMS System Requirements EICB (Carte)

Specifications deleted WBN2 PAMS documents reference generic PAMS documents, for example: WBN2 PAMS SysRS

References:

00000-ICE-30156 Rev.

6, System Requirements Specification for the Common Q Post Accident Monitoring System, and 00000-ICE-30155, Rev. 9, System Requirements Specification for the Common Q Generic Flat Panel Display 148 6/17/2010 Responder: Closed Closed PAMS System Requirements EICB (Carte)

Specifications deleted WBN2 PAMS documents reference generic PAMS documents, for example: WBN2 PAMS SysRS

References:

00000-ICE-30156 Rev.

6, System Requirements Specification for the Common Q Post Accident Monitoring System, and 00000-ICE-30155, Rev. 9, System Requirements Specification for the Common Q Generic Flat Panel Display 149 6/25/2010 Responder: Tindell Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR Section 7.1.1.2(2), Overtemperature delta T and In FSAR amendment 96 the equations were revised In FSAR amendment 96, the TVA to provide Overpressure delta T equations have been simplified and to agree with the Unit 1 UFSAR which is the basis values of the constants have date when many values are removed from the FSAR. Provide the document for the Unit 2 FSAR. This resulted in the been moved to TS or plant information will be justification for this change. equations being simplified and the removal of the procedures. Need to document docketed.

values for the constants. The equations were the basis for this change.

revised to match those used in the Technical Specifications. The values for the constants are contained in the Technical Specifications and were removed as redundant.

150 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB System (Garg) Many of the changes were based on the Westinghouse System description N3-99-4003, Reactor Protection TVA to provide document N3-99-4003. Provide this document for staffs System is contained in Attachment __ date when review so the staff can determine the basis for these information will be

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date changes. docketed.

151 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System Provide the EDCR 52378 and 54504 which discusses the EDCR 54504 has been voided and replaced with TVA to provide basis for many changes to this FSAR section. EDCR 52378 which is contained in (Attachment ___ date when

) and EDCR 52671 is contained in (Attachment ___ information will be

). docketed.

152 6/25/2010 Responder: Merten/Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System Deleted portion of FSAR section 7.2.3.3.4 and moved to The text was revised to match the Unit 1 UFSAR. TVA to confirm if FSAR section 7.2.1.1.5. However, the FSAR section The Unit 1 text was modified in Amendment 1 by this description is 7.2.1.1.5 does not include the discussion of ambient FSAR Change Package 1553 S00 which is the same as for temperature and also on the calibration of the sealed contained in Attachment 30. The basis for the Unit 1. If it is same reference leg system. No justification was provided for change in the change package is: as Unit 1 then why deleting this discussion. Please explain the bases for this was shown as deletion of this information. 16 The update to Section 7.2.1.1.5 is taken from text change in redline in Section 7.2.2.3.4 with clarifications and editorial version of FSAR changes. The relocated discussion of the pressurizer Amendment 96.

water level instrumentation Is more appropriately included in this section than Section 7.2.2.3.4, which TVA to provide deals with control and protection system interaction. date when The changes to 7.2.1.1.5 are based on a general information will be description of the Westinghouse pressurizer level docketed.

design, channel independence, and actual installation attributes found on TVA physical drawings. Also, the hydrogen gas entrainment issue documented in NRC Information Bulletin No. 92-54, Level Instrumentation Inaccuracies Caused by Rapid Depressurization, is retained and clarified. Similar clarification is made to Reactor Protection System Description N3-9g.4003 Section 3.1.1.2(d). The original text in 7.2.2.3.4 provides some information that is too detailed and is not pertinent to the subject of discussion. It also includes a statement that the error effect on the level measurement during a blowdown accident would be about one inch. The basis for this value is not known; however, the worst case reference leg loss of fill error due to a rapid RCS depressurization event Is no more than 12 inches elevation head. This value is based on the relative elevation difference between the condensing chamber and the reference leg sensor bellows. The Westinghouse Owners Group response to this issue is found in RIMS # L44930216800. The channel error value discrepancy is documented in WBPER980417. The remaining text in 7.2.2.3.4 is revised to clarify the control and protection system interaction discussion.

153 6/25/2010 Responder: Craig/Webb Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.1.1.7 added the reference to FSAR Add alternate method of RCS cooldown using TVA will send section 10.4.4.3 for exception to P-12. However, FSAR additional steam dump valves after entering Mode 4, 50.59.

section 10.4.4.3 states bypass condition is not displayed by disabling the P-12 Interlock. Operators use and it is not automatically removed when conditions for additional condenser dump valves to aid in TVA to provide bypass are no longer met. Provide the basis for this. maintaining a cooldown rate closer to the date when administrative limit established by operating information will be procedure. docketed.

Refer to Unit 1 UFSAR Amendment 3 Change Package 1676 S00 (Attachment 6) for the safety evaluation and basis for this change.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date The 50.59 for the change is included in the Change Package.

154 6/25/2010 Responder: Craig/Webb Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.1.1.10, setpoints: NRC staff has issued (Q1) Refer to the response to letter item 13, RAI FSAR Amd 100.

RIS 2006-17 to provide guidance to the industry regarding Matrix Item 51. Since all the the instrument setpoint methodology which complies with setpoint and 10 CFR 50.36 requirements. Provide the information on (Q2) EEB-TI-28's single sided methodology allowable value for how the WBN2 setpoint methodology meets the guidance conforms with WBN's design basis commitment to Unit 2 is calculated of RIS 2006-17 and include this discussion in this section. ensure that 95% of the analyzed population is and added to TS, Also, by letter dated May 13, 2010, TVA provided Rev. 7 of covered by the calculated tolerance limits as defined TVA needs to EEB-TI-28 to the staff. The staff noted that section 4.3.3.6 in NRC Reg Guide 1.105, Revision 2, 1986 that was address the latest of EEB-TI-28 discusses the correction for setpoints with a in affect during WBN Unit 1 licensing. criteria and that single side of interest. It should be noted that the staff has include 95/95 not approved this aspect of setpoint methodology for Unit criteria.

1. The staff finds this reduction in uncertainties is not justified unless it can be demonstrated that the 95/95 criteria is met. Therefore, either remove this reduction factor for single sided uncertainties or justify how you meet the 95/95 criteria given in RG 1.105.

155 June 25, 2010 Date: Closed Closed FSAR Section 7.2, Reactor Trip EICB (Garg)

Responder: Stockton System Summary of FSAR change document section 7.2 states TVA to provide that sections 7.2.1.1.9 and 7.2.2.2(4) are changed to show The change package summary were the changes date when that these activities will occur in future. However, no recommended by Engineering. TVA Licensing is information will be changes were made to the FSAR sections. Please responsible for the actual submittal and elected not docketed explain. to incorporate these recommendations. The activities are complete and the text in Amendment 99 of the FSAR is correct.

156 6/25/2010 Responder: WEC Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.1.1 states that dashed lines in Figure Per Westinghouse letter WBT-D-2340, TENNESSEE TVA to provide 15.1-1designed to prevent exceeding 121% of VALLEY AUTHORITY WATTS BAR NUCLEAR date when Response on hold pending power.The value of 121% is changed from 118%. PLANT UNIT 2 FSAR Markups Units I and 2 118% information will be Westinghouse review.

The justification for this change states that this was done vs 121 % and Correction to RAI Response SNPB docketed to bring the text of this section in agreement with section 4.3.2-7, (Reference 17) the 118% value should be 4.3.2.2.5, 4.4.2.2.6 and table 4.1-1. However, Table 4.1-1 121%. Depending on the use in the FSAR either and section 4.3.2.2.5 still show this value as 118%. Justify 118% or 121% are the correct values. As a result of the change. the question, Westinghouse reviewed all locations where either 118% or 121% are used and the context of use and provided a FSAR markup to reflect the correct value at the specific location.

These changes will be incorporated in a future FSAR amendment.

157 6/25/2010 Responder: Tindell Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.1.1, fifth paragraph was deleted The condition is defined in the preceeding discussion TVA to provide except for the last sentence. The last sentence states as operating with a reactor coolant pump out of date when that, The P-8 interlock acts essentially as a high nuclear service and core power less than 25%. information will be power reactor trip when operating in this condition. This docketed sentence is confusing because the condition is not defined. Please clarify this discrepancy.

158 6/25/2010 Responder: Tindell Open Open EICB (Garg)

FSAR section 7.2.2.1.1, paragraph six was changed to FSAR Amedment 99 reflects the change to Criterion TVA to provide state that the design meets the requirements of Criterion 23. date when 23 of the 1971 GDC instead of the Criterion 21 of the information will be GDC. The Criterion 21 is about protection system docketed reliability and testability, while Criterion 23 is about

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date protection system failure modes. Since this paragraph deals with the evaluation of design with respect to common-mode failure, the staff believes that Criterion 23 is the right reference for this paragraph. Please clarify.

159 6/25/2010 Responder: Craig Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.1.2 discusses reactor coolant flow Elbow taps are used to measure reactor coolant flow TVA to provide measurement by elbow taps. However, it further states for both Unit 1 and 2. However the method used to date when that for Unit 2, precision calorimetric flow measurement verify reactor coolant flow, as required by the information will be methodology will be used. If elbow taps are not used for Technical Specifications, is not the same. Unit 1 docketed Unit 2, then why does this section discuss this uses a simplified methodology based on elbow tap methodology? It is the staffs understanding that TVA P measurements correlated with precision plans to use elbow taps methodology in the future for Unit calorimetric data over several cycles of operation as

2. Please revise this section to describe the current plant described in Reference 17, WCAP-16067, Rev 0, design/methodology. RCS Flow Measurement Using Elbow Tap Methodology at Watts Bar Unit 1.

Unit 2 will verify reactor coolant flow Technical Specification requirements using the precision flow calorimetric methodology until sufficient data is collected to correlate elbow tap P measurements with actual flow. There is no change to the Unit 2 reactor coolant elbow tap measurement design.

Look at what needs to be kept on elbow tap and remove as required.

160 6/25/2010 Responder: Tindell Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.2(7) deleted text which has references The text was revised to match the Unit 1 UFSAR. TVA to provide 12 and 14. These references are not included in the The Unit 1 text was modified in Amendment 1 by date when revised text. Provide the basis for the deletion of these FSAR Change Package 1553 S00 which is information will be references. Also, the revised text states that typically this contained in Attachment 30. The basis for the docketed requirement is satisfied by utilizing 2/4 logic for the trip change in the change package is:

function or by providing a diverse trip. Provide any exception to this and their basis for acceptability. 23. (page 7.2-24): Portions of the discussion of control and protection system interaction are revised to clarify the requirement. The discussion of how the SG low-low water level protective function and the control system Median Signal Selector satisfy this requirement is deleted since it Is redundant to the information provided In Section 7.2.2.3.5. Reactor Protection System Description N3-99-4003 is also revised to move and clarify the discussion of the requirements for control and protection system Interaction from Section 3.1.1.2 to Section 2.2.11, where the Issue is also discussed.

161 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.3 states that changes to the control FSAR Amendment 99 reflects the changes TVA to provide function description in this section are expected to be associated with the Foxboro I/A system design. date when required after vendor design of the Unit 2 Foxboro IA information will be design is complete. Provide the schedule for the docketed completion of the design and when this information will be available to the staff for review and approval.

162 6/25/2010 Responder: Tindell Open Open FSAR Section 7.2, Reactor Trip

( EICB (Garg)

System FSAR section 7.2.2.2(14) states that bypass of a The Bypassed and Inoperable Status Indication TVA to provide protection channel during testing is indicated by an alarm System (BISI) compliance with Reg. Guide 1.47 is date when G

in the control room. Explain how this meets RG 1.47. described in detail in FSAR Section 7.5.2.2. information will be docketed 163 June 25, 2010 Date: Closed Closed FSAR Section 7.2, Reactor Trip

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Responder: System deleted 164 6/25/2010 Responder: Perkins Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.2(20) has been revised to include the The primary purpose of the plant computer is to TVA to provide plant computer as a means to provide information read out present plant process and equipment status date when for all signals which can cause a reactor trip. Justify the information to the control room operators to assist information will be use of the plant computer for this function. Include the them in the normal operations of the unit, and inform docketed discussion on the effect of plant computer failure on the them of any abnormal conditions. The plant system functions. computer obtains real-time plant parameter information via Data Acquisition Systems(DAS)(multiplexers, etc.) by scanning preassigned analog, pulse, and contact sensors located throughout the plant. The computer is not defined as being primary safety-related and it is not required to meet the single failure criterion or be qualified to IEEE criteria for Class 1E equipment.

The plant computer system acquires, processes, and displays all data to support the assessment capabilities of the Main Control Room (MCR). To help ensure that reactor trip and other information presented to the Operations staff is reliable:

• The data undergoes several validation steps before being presented to the operators. When redundant sensors are used, the data received by the computer can be processed by software to determine if the quality of one or more points is questionable.

• Any software associated with the computer and the DAS must meet the quality requirements of plant procedure SPP-2.6, Computer Software Control which is based on requirements in NUREG/CR-4640, the Watts Bar Nuclear Quality Assurance Plan, and SS-E18.15.01 - Software Requirements for Real-Time Data Acquisition and Control Computer Systems, which complies with IEEE Std. 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations. The computer software is controlled by a Software Quality Assurance Plan.

• One of the requirements in 10 CFR 50, Appendix A states that Appropriate controls shall be provided to maintain variables monitored and systems within prescribed operating ranges. Periodic maintenance and calibration will be performed on the computer and DAS. In addition, calibration procedures for instrumentation which is used for input to the computer include verification of the computer input signal at the DAS and as displayed on the display stations.

• The software and associated hardware undergoes a detailed Factory Acceptance Test prior to installation in the plant. After installation in the plant, a Site Acceptance Test (SAT) will be conducted. The SAT will include several tests: computer accuracy,

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date analog input accuracy, calculated value accuracy, computer performance, system response times, all input/output (from termination strip to display stations/printers), all data ports, and computer power supplies.

• In order to minimize the possibility of bad sensor inputs to the Safety Parameter Display System (SPDS) and/or inaccurate SPDS display of sensor inputs, routine instrument loop calibration of sensors that provide input to the SPDS will include verification that the SPDS-displayed values are correct. WBN's instrument surveillance instructions will incorporate these verifications.

Effect of plant computer failure on system functions The WBN Unit 2 is designed on the basis that it can still operate when the plant computer is inoperable.

The computer is not required for safe shutdown of the plant during external design basis events such as tornadoes, floods, rain, and transportation accidents.

Operators are trained to respond to accidents both with and without the computer information available.

The control room instrumentation provides the operators with the information necessary for safe reactor operations under normal, transient, and accident conditions.

The DAS is mechanically and electrically isolated from the safety systems to avoid degradation of the systems should the computer and/or DAS fail.

The computer is not expected to perform any nuclear safety-related function, therefore, the computer need not be designed to meet nuclear safety-related Class 1E, single-failure criteria. The computer is not designed to safety system criteria and therefore is not to be used to perform functions essential to the health and safety of the public.

165 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.3.2, last paragraph of this section has The reference to Section 7.2.2.2 for the general TVA to provide been deleted. The basis for this deletion is that discussion discussion for control and protection interactions is date when regarding the compliance with IEEE-279, 1971 and GDC provided in Section 7.2.2.3. The reference in information will be 24 is covered in section 7.2.2.2. However, there is no Section 7.2.2.3 is applicable to all Sub-Section docketed reference to this section in 7.2.2.3.2 to direct the reader to paragraphs, including 7.2.2.3.2. An additional 7.2.2.2. Please revise 7.2.2.2 accordingly. reference in this section is not necessary and would be redundant to the Section 7.2.2.3 reference.

166 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System Changes to FSAR section 7.2.2.2(20) are justified based EDCR 52322, Design, Procure And Construct An TVA to provide on the statement that the integrated computer system is Intergrated Computer System (Ics) For Watts Bar date when implemented through EDCR 52322. Provide a copy of Nuclear Plant Unit 2. Provide All Appropriate information will be EDCR 52322 for staff review. Documentation To Support Design Input. Generate docketed Or Revise All Official Drawings To Represent Final Constuction Configuration is contained in Attachment 167 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB System (Garg) FSAR section 7.2.2.4, provide an analysis or reference to Continuous rod withdrawal events are analyized in TVA to provide chapter 15 analysis which demonstrate that failure of rod FSAR sections 15.2.1 and 15.2.2. While the rod date when

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date stop during a rod withdrawal event will not affect the safety stops a mentioned, they are not credited in the information will be limit. analysis. docketed 168 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR table 7.2-4, item 9 deleted loss of offsite power to This this change is in accordance with the Unit 1 TVA to provide station auxiliaries (station blackout) based on the fact that UFSAR. The change was made by FSAR Change date when station blackout is not listed in AAPC events. Explain what Package 1553 S00 (Attachment __). The information will be are AAPC events and how it justifies deleting this accident justification for the change is: docketed from the list.

38 (Table 7.2-4): This table lists the reactor trips and the various accident analyses for which each trip could provide protection. The intent of the table is to demonstrate the diversity of and comprehensive protection provided by the reactor trip system against various postulated events and to correlate the trip functions with the analyses in which they may be utilized, either as a primary or secondary protective function. Chapter 15, along with the Accident Analysis Parameters Checklist, WB-OC-40-70, provides the accident analysis discussion and identifies the protection system functions which provide accident mitigation. The additions and deletions to the table are made for consistency with the safety analyses of record as reflected in the design and licensing basis and do not represent analysis changes or protection system changes.

Therefore. they are considered to be non-significant as discussed at the beginning of this section.

Neutron Monitoring System Description N3-85-4003 Table 2 is also revised for consistency with WB-DC-40-70.

169 6/18/2010 Responder: Clark Closed Closed EICB (Garg)

Describe the design changes which were made to Unit 1 This is a duplicate of items 2, 10, 11 and 44 by 10CFR50.59 process and which significantly affect the instrumentation and controls systems discussed in FSAR Chapter 7.

170 6/17/2010 Responder: Clark Closed Closed EICB (Garg)

TVA needs to document that Arnold Magnetics power This is a duplicate of item 113.

supplies have been used and environmentally qualified at Unit 1 and therefore meet the licensing basis for Unit 2. If these power supplies are not used and qualified in Unit 1, then TVA will have to discuss the qualification of these power supplies based on the guidance provided in RG 1.209 (Open Item # 2 of Eagle 21 audit.)

171 6/17/2010 Responder: Craig Open Open EICB (Garg)

An external unidirectional communications interface was This item requires further discussion. It has been TVA to provide installed between the Eagle 21 test subsystem and the deleted from the current letter. date when plant process computer. TVA should confirm that testing information will be has demonstrated that two way communication is docketed impossible with the described configuration. (Open Item #

3 of Eagle 21 audit) 172 6/17/2010 Responder: Craig Closed Closed

( EICB (Garg) During a FAT diagnostic test, the Loop Calculation This is a duplicate of the rack 5 update issue item Processor (LCP) failed while performing a parameter 114.

G update. TVA should identify the cause and fix for the problem encountered. (Open Item # 1 of Eagle 21 audit) 173 6/17/2010 Responder: Craig/Webb/Powers Open Open

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date EEB-TI-28 discusses the correction for setpoints with a TVA to provide single side of interest. The staff finds this correction factor date when is not justified. TVA should justify this correction factor information will be and demonstrate that, with this correction, factor 95/95 docketed criteria identified in RG 1.105 is met.

174 6/28/2010 Responder: Hilmes/Craig Closed Closed EICB (Garg)

Placeholder: The staff has identifed questions regarding Duplicate of 171 unidirectional communications interface. The staff will keep this item open until TVA confirms testing has demonstrated that two way communication is impossible with the described configurations.

175 June 28, 2010 Responder: Closed Closed EICB (Garg)

Placeholder: The staff has identified questions regarding WCAP-13869 rev.2. is submitted in response to item In FSAR amendment 98, This item is diversity. The staff will keep this item open until TVA reference 6 added a new WCAP- covered under item provides the related WCAP to the staff for its review and 13869 rev.2. Has this WCAP 78.

approval. been reviewed by the staff. If not then provide the copy of TVA to provide WCAP for staff review. date when information will be docketed.

176 6/28/2010 Responder: Craig/Webb Open Open EICB (Garg)

Placeholder: The staff has identified questions regarding TVA to provide instrument setpoints. The staff will keep the instrument date when setpoint methodology issue open until TVA provides information will be additional information regarding RIS 2006-17 and single docketed sided correction factor for uncertainty determination.

177 7/15/2010 Responder: Clark Open Open EICB (Garg)

FSAR Amendment 99 Section 7.5.1.2 states: "Type A The type A variables are the same in Unit 1 and Unit August 19, 2010 - TVA to submit TVA to docket Variables Those variables that provide primary information 2. See calculation WBNOSG4047 Rev. 4 calculation. calculation.

to the MCR operators to allow them to take preplanned (Attachment )

manually controlled actions for which no automatic action is provided and that are required for safety systems to accomplish their safety functions for Chapter 15 design basis events. Primary information is information that is essential for the direct accomplishment of specified safety functions."

Clarify whether Unit 2 has the same Type A variables as Unit 1.

178 EICB 7/15/2010 Responder: Clark Open Open (Marcu s) Please provide WBN-OSG4-047, "PAM Type A Variable See response to item 177 above. August 19, 2010 - TVA to submit TVA to docket Determination." calculation. calculation.

179 7/15/2010 Responder: WEC Open Open EICB (Carte)

An emphasis is placed on traceability in System Steve Clark to look at how to combine traceability TVA to provide Requirements Specifications in the SRP, in the unmodified items. date when IEEE std 830-1993, and even more so given the information will be modifications to the standard listed in Regulatory Guide Will be addressed to during the 9/15 meeting and docketed 1.172, which breaks with typical NRC use of the word 9/20 - 9/21 audit.

should regarding backwards traceability to say Each identifiable requirement in an SRS must be traceable backwards to the system requirements and the design bases or regulatory requirements that is satisfies Discuss how TVA has ensured that the re is traceability

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date (and particularly backward traceability) for each requirement. If requirements are not traceable, please explain how the SRS complies with the regulations that underlie the SRP.

180 7/15/2010 Responder: WEC Open Open EICB (Halverson)

The SRP, BTP 7-14, Section B.3.3.1 states that Steve Clark to look at how to combine traceability TVA to provide Regulatory Guide 1.172 endorses, with a few noted items. date when exceptions, IEEE Std 830-1993. IEEE Recommended information will be Practices for Software Requirements Specifications. Will be addressed to during the 9/15 meeting and docketed 9/20 - 9/21 audit.

Clarify whether the WBU2 Post Accident Monitoring Systems Software Requirements Specification adheres to IEEE std 830-1993 as modified by Regulatory Guide 1.172?

If yes, please provide an evaluation that includes an identification and description of all differences proposed from the modified standard. Please describe how the alternatives provide an acceptable method of complying with those regulations that underlie the corresponding SRP acceptance criteria.

If no then please provide an evaluation that includes an identification and description of all differences proposed from the acceptance criteria given in SRP , BTP 7-14, Section B.3.3.1. Please describe how the alternatives provide an acceptable method of complying with those regulations that underlie the corresponding SRP acceptance criteria.

181 7/15/2010 Responder: WEC Open Open EICB (Halverson)

An emphasis is placed on traceability in System Steve Clark to look at how to combine traceability TVA to provide Requirements Specifications in the SRP, in the unmodified items. date when IEEE std 830-1993, and even more so given the information will be modifications to the standard listed in Regulatory Guide Will be addressed to during the 9/15 meeting and docketed 1.172, which breaks with typical NRC use of the word 9/20 - 9/21 audit.

should to say Each identifiable requirement in an SRS must be traceable backwards to the system requirements and the design bases or regulatory requirements that is satisfies Explain the source(s) of the requirements present in the Post Accident Monitoring Systems Software Requirements Specification. To clarify, many documents have requirements that are incorporated by reference into the SRS, but what served to direct the author to include those various documents in the SRS or, if the requirement is based on the System Requirments Specification, what directed the author to include the requirement there?

182 7/15/2010 Responder: WEC Open Open EICB (Halverson)

Characteristics that the SRP states that an Software Somewhat redundant with question on Shalls outside TVA to provide Requirements Specifications should have include of the "requirements" sections. date when unambiguity, verifiability, and style, part of the latter is that information will be Each requirement should be uniquely and completely Shalls included in non-numbered sections and docketed defined in a single location in the SRS. general discussions.

Clarify whether the unnumbered paragraphs in the Post Accident Monitoring Systems Software Requirements Specification, such as in the section headings, or are all

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date such sections simply considered to be informative?

Does the same apply to documents referenced by the SRS? Such as WCAP-16096-NP-A, Rev. 1A, Software Program Manual for Common Q Systems, which is incorporated by reference in requirement R2.3-2 in the SRS.

R2.3-2 [The PAMS software shall comply with the requirements and guidelines defined in WCAP-16096-NP-A, Software Program Manual for Common Q Systems (reference 5).]

If any requirements are expressed in such unnumbered paragraph form instead of individually identified requirements, please list them, describe why they satisfy the fundamental requirement of unambiguity, and describe how they were verified.

183 7/15/2010 Responder: WEC Open Open EICB (Halverson)

An emphasis is placed on traceability in System Steve Clark to look at how to combine traceability TVA to provide Requirements Specifications in the SRP, in the unmodified items. date when IEEE std 830-1993, and even more so given the information will be modifications to the standard listed in Regulatory Guide Will be addressed to during the 9/15 meeting and docketed 1.172, which breaks with typical NRC use of the word 9/20 - 9/21 audit.

should to say Each identifiable requirement in an SRS must be traceable backwards to the system requirements and the design bases or regulatory requirements that is satisfies On page 1-2 of the Post Accident Monitoring Systems Software Requirements Specification in the background section, is the sentence Those sections of the above references that require modification from the generic PAMS are defined in the document referring purely to the changes from WNA-DS-01617-WBT Post Accident Monitoring System-System Requirements Specification or is it saying that there are additional changes beyond those and that the SRS defines them?

If there are additional changes, what is their origin?

184 7/15/2010 Responder: WEC Open Open EICB (Halverson)

The NRC considers that a System Requirements Steve Clark to look at how to combine traceability TVA to provide Specification is the complete set of requirements used for items. date when the design of the software, whether it is contained within information will be one document or many. In order to evaluate an SRS Will be addressed to during the 9/15 meeting and docketed against the guidance in the SRP the staff needs access to 9/20 - 9/21 audit.

all the requirements.

Are there any sources of requirements in parallel with the Post Accident Monitoring Systems Software Requirements Specification? Meaning does the SRS contain, explicitly or by reference, all the requirements that were used in the design phase for the application specific software, or do software design phase activities use requirements found in any other source or document? If so, what are these sources or documents?

185 B 7/15/2010 Responder: WEC Open Open (Hal vers An emphasis is placed on the traceability of requirements Steve Clark to look at how to combine traceability TVA to provide

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date in Software Requirements Specifications in the SRP, in items. date when the unmodified IEEE std 830-1993, and even more so information will be given the modifications to the standard listed in Regulatory Will be addressed to during the 9/15 meeting and docketed.

Guide 1.172, which breaks with typical NRC use of the 9/20 - 9/21 audit.

word should to say Each identifiable requirement in an SRS must be traceable backwards to the system requirements and the design bases or regulatory requirements that is satisfies Also the NRC considers that the SRS is the complete set of requirements used for the design of the software, whether it is contained within one document or many. In order to evaluate an SRS against the guidance in the SRP the staff needs access to all the requirements.

References 12, 27, 29, and 31-44 in the Post Accident Monitoring Systems Software Requirements Specification are various types of Reusable Software Element.

These references are used in the body of the SRS, for example:

R5.3.14-2 [The Addressable Constants CRC error signal shall be TRUE when any CAL CRC's respective ERROR terminal = TRUE (WNA-DS-00315-GEN, "Reusable Software Element Document CRC for Calibration Data"

[Reference 12]).]

They are also included via tables such as found in requirement R7.1.2-1

[The Watts Bar 2 PAMS shall use the application-specific type circuits and custom PC elements listed in Table 7.1-1.]

Do the referenced reusable software element documents include requirements not explicitly stated in the SRS? If so what is their origin?

186 7.7.8 7.7.1.1 7/15/2010 Responder: Perkins/Clark Open Open EICB (Darbali) 2 Along with Amendment 96, TVA submitted a list of Bechtel This change will be included in FSAR Amendment Response is satisfactory. Issue Once FSAR changes for each section. Change number 45 addresses 101. date of Amendment 101 is not Amendmet 101 is a change to section 7.7.1.12, AMSAC, however, the yet determined. received, the item EDCR 52408 Summary:

Justification column states This change is not included. will be closed.

EDCR 52408 installs the AMSAC in Unit 2. It does not A Purchase Order was issued to Nutherm Open International to provide a Unit 2 cabinet with the have a trouble alarms. The existing words better reflect the operation of the system. same functions as the current Unit 1 AMSAC. EDCR Response is acceptable awaiting 52408 will install the cabinet and route/install cabling FSAR amendment submittal.

Even thought this change was not included in Amendment to provide the necessary inputs/outputs for/from the 96, will it be included in a future amendment? AMSAC cabinet. The EDCR will only route and install cables from the cabinet to the field side of a Also, please submit a summary of EDCR 52408. terminal block in the Main Control Room panel 2-M-

3. These cables will provide the AMSAC NOT ARMED and AMSAC ACTUATED signals to annunciator windows.

Two pressure transmitters will also be installed in two local panels. Cables will be routed to the transmitters to provide the signal and power. Four cables will be routed to a local panel to provide steam generator level signals. Other cables will be routed to provide an output signal to start a Motor Driven Auxiliary Feedwater Pump and to provide an

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date output signal to trip the turbine.

This work will make the Unit 1 and 2 Main Control Room panel inputs to plant computer and annunciator light box windows nomenclature identical to each other.

187 7/20/2010 Responder: Clark Open Open Are these connections already EICB (Carte) docketed?

By letter dated June 18, 2010, TVA docketed responses to 1) The original design was to allow printing from both NNC 8/25/10: Why did TVA not NRC requests for information. the Operator Module (OM) and Maintenance and catch this on the review of the Test Panel (MTP) via the plant computer. This PAMS SysRS or SRS? Does

1) Enclosure 1, Item No. 33 of the TVA letter dated June required both to be connected to the plant computer. TVA check that the CQ PAMS 18, 2010, did not identify any connection from the PAMS Westinghouse did not perceive this as an issue, system meets the requirements Operator Modules (OMs) to the plant computer and because the standard Common Q PAMS design in its purchase specifications?

printers; however, Figure 2.1-1 of the PAMS System includes both the flat panel displays and individual Requirements Specification (WNA-DS-01617-WBT Rev. 1 control panel indicators. The Westinghouse

- ML101680578) shows a TCP connection from the OMs Common Q team did not realize that WBN does not to the plant computer and printer. Please explain. use the individual control panel indicators. As a result, the original design documents provided by

2) Please clarify whether any digital safety-related systems Westinghouse included the connection from the OM or components have a digital communications path to non- to the plant computer.

safety-related systems or with safety related systems in another division. If so, NRC staff will need these paths The TVA team did not realize that the Westinghouse identified on the docket. design relied on the OM and MTP to be qualified isolation devices that protected the AC160 functions and individual control panel indicators from interference from the plant computer. It was not until a meeting was held to discuss the design of the OM that the issues came to light. That was when Westinghouse understood that the OM was the PAMS display and WBN did not use individual control panel indicators and TVA understood that the OM was being credited as the qualified isolation device. It became apparent at the meeting to both TVA and Westinghouse that the original design was not acceptable. The team then agreed deleting the OM connection to the plant computer was the best option to resolve the problem.

2) This is a duplicate of closed RAI Matrix Item 45.

188 7/20/2010 Responder: Clark Open Open EICB (Carte)

By letter dated June 30, 2010, TVA docketed, Tennessee 1) The original design was to allow printing from both NNC 08/25/10: See Open Item TVA to respond or Valley Authority (TVA) Watts Bar Unit 2 (WBN2) - Post- the Operator Module (OM) and Maintenance and No. 187. provide proposed Accident Monitoring System (PAMS) Licensing Technical Test Panel (MTP) via the plant computer. This date of response.

Report, (Document Number WNA-LI-00058-WBT- P, required both to be connected to the plant computer.

Revision 0, June 2010) (Westinghouse Proprietary Class Westinghouse did not perceive this as an issue, 2). because the standard Common Q PAMS design includes both the flat panel displays and individual

1) Figure 2.2-1 of the PAMS Licensing Topical Report control panel indicators. The Westinghouse does not show any connection between the Operators Common Q team did not realize that WBN does not Modules and the plant computer or printer; however, use the individual control panel indicators. As a Figure 2.1-1 of the PAMS System Requirements result, the original design documents provided by Specification (WNA-DS-01617-WBT Rev. 1 - Westinghouse included the connection from the OM ML101680578) shows a TCP connection from the OMs to to the plant computer.

the plant computer and printer. Please explain.

The TVA team did not realize that the Westinghouse

2) Section 5.3, Response to individual criteria in DI&C- design relied on the OM and MTP to be qualified ISG-04, of the PAMS Licensing Topical Report does not isolation devices that protected the AC160 functions address the TCP connection between the OM and non- and individual control panel indicators from safety components depicted in Figure 2.1-1 of the PAMS interference from the plant computer. It was not until

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date System Requirements Specification (WNA-DS-01617- a meeting was held to discuss the design of the OM WBT Rev. 1 - ML101680578). Please explain. that the issues came to light. That was when Westinghouse understood that the OM was the PAMS display and WBN did not use individual control panel indicators and TVA understood that the OM was being credited as the qualified isolation device. It became apparent at the meeting to both TVA and Westinghouse that the original design was not acceptable. The team then agreed deleting the OM connection to the plant computer was the best option to resolve the problem.

2) This is a duplicate of closed RAI Matrix Item 45.

189 7.6.7 7/20/2010 Responder: Clark Closed Closed EICB (Singh) FSAR Section 7.6.7States: Conformance with Regulatory This is a typographical error. The correct reference NNC 8/25/10: Acceptable By FSAR Guide 1.133, Revision 1 is discussed in Table 7.1-7. is Table 7.1-1. The reference will be corrected in response. Amendment 100, FSAR Chapter 7 does not contain any such numbered FSAR Amendment 100. page 7.6-4.

table. Please explain.

190 7.9 7/20/2010 Responder: Clark Open Open EICB (Singh)

NUREG-0800 Chapter 7, Section 7.9, "Data 1) TSR 3.3.6.3 specifies 18 months as the calibration TVA to revise Communication Systems" contains review criteria for data frequency. response.

communication systems. The WBN2 FSAR did not include any description of data communications systems. 2) Per the Technical Requirements Manual (TRM)

1) Please identify all data communications systems. Bases 3.3.6 (Attachment __) the surveillance

2) Please describe each data communications system requirements and frequency are provided in identified above. Regulatory Guide 1.133, "Loose-Part Detection

3) Please provide a regulatory evaluation of each data Program for the Primary System of Light-Water-communications system against the applicable regulatory Cooled Reactors."

criteria.

3) TRM section 3.3.6 and its bases are contained in Attachment __.

191 7.9 7/20/2010 Responder: Jimmie Perkins Open Open EICB (Carte)

NUREG-0800 Chapter 7, Section 7.9, "Data WBN Unit 2 is in compliance with the regulatory NNC 8/25/10: Information Communication Systems" contains review criteria for data requirements for data communications systems as received, and read.

communication systems. The WBN2 FSAR did not include described in Attachment 33 (Data Communications any description of data communications systems. Systems Description and Regulatory Compliance

1) Please identify all data communications systems. Analysis).

2) Please describe each data communications system identified above. See item 4 192 7.5 7/20/2010 Responder: Clark Open Open EICB (Marcus)

The NRC Staff is using SRP (NUREG-0800) Chapter 7 11. At WBN Unit 1 and 2, there is a single computer August 19, 2010 - NRC to review NRC to review Section 7.5, Instrumentation Systems Important to system named the Integrated Computer System or TVA response. response.

Safety, to review the WBU2 FSAR Section 7.5, ICS. That system is sometimes described as the Instrumentation Systems Important to Safety. The Plant Computer System, the Process Computer, following requests are for information that the SRP directs the Technical Support Center Data System (TSCDS) the reviewers to evaluate. or the Emergency Response Facility Data System (ERFDS). At one time, the TSCDS and ERFDS The role of the EICB Technical reviewer is to determine if were separate computers on unit 1 but their there is reasonable assurance that the equipment will functions were all incorporated into the ICS when it perform the required functions. The WBU2 FSAR, Section was installed.

7.5.2, Plant Computer System, does not contain any description of the equipment that performs the functions 2. The Watts Nuclear Plant ICS is a non-safety described in the section. Enclosure 1 Item 3 of letter dated related system, is designed as a single, large-scale March 12, 2010, TVA stated that the platform of the nuclear plant computer system which integrates Process Computer was, Hewlett Packard RX2660 and balance of plant (BOP) monitoring with extensive Dell Poweredge R200 servers with RTP Corp 8707 I/O. In nuclear steam supply system (NSSS) application addition TVA provided (a) two pages of marketing software into a comprehensive computer based tool

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date literature by DELL on the Poweredge R200 Server, (b) the for plant operations. The system is comprised of the HP Integrity rx2660 Server Unser Service Guide, and (c) following major components:

the Integrated Computer System Network Configuration

• Remote multiplexers in the Computer Room, Connection Diagram (2-45W2697-1-1 dated 8/27/09). Auxiliary Instrument Room and 480V Board rooms.

This provided information is not sufficient for evaluating

• Redundant Central Processing Units (CPUs) whether the equipment will, with reasonable assurance,

• Data Storage Devices perform the functions described in the FSAR.

• Man-Machine Interfaces (MMI) - Satellite Display Stations (SDS) terminals in the Main Control Room

1) Is the Plant Computer System another name for the (MCR), Technical Support Center (TSC) and Process Computer? Computer Room.

• Networking equipment including switches, firewalls

2) Please provide an architectural description of the Plant and terminal servers Computer System.

• Printers

• Data Links to other plant computer devices (serial

3) Please describe the relationship between the Plant and network)- These systems or devices include but Computer System and the Integrated Computer System. are not limited to:

o System Foxboro I/A Systems (unit 2 only) o Arreva Beacon core monitoring systems o Multi-pen recorders o Landis & Gyr switchyard monitoring system o Computer Enhanced Rod Position Inidication (CERPI) o Eagle 21 o Ronan Annunicator o Leading Edge Flow Meter (LEFM) o Bently-Nevada vibration monitoring system o Inadequate Core Cooling Monitor (ICCM) (unit 1 only) o Common Q (unit 2 only) o WinCISE (unit 2) o Plant Engineering Data System (PEDS)

In support of normal plant operations, each units ICS:

• Scans and converts analog and digital plant process inputs to engineering units for displaying, alarming and reporting.

• Receives analog and digital inputs as pre-processed values from other digital systems for displaying, alarming, archiving, and reporting.

• Performs data validity checking.

• Performs calculations to obtain parameters such as difference, flows, and rates.

• Displays alarms when data point value exceeds predefined set points.

• Displays alarms received from the digital Annunciator system.

• Generates periodic station logs and pre-selected special logs.

• Performs BOP and NSSS related calculations.

• Provides graphical and digital trending displays of plant data.

• Provides graphical P&ID type displays of plant data.

In support of emergency plant operations each units ICS:

• Provides plant emergency support with the Safety Parameter Display System (SPDS) functions based upon the Westinghouse Owners Group CSF status trees and historical data collection, storage, and

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date retrieval functions required to support NUREG-0737 and NUREG-0737, Supplement 1 category 1 variables (except for containment isolation).

• Provides SPDS and Emergency Response Data System (ERDS) data to the Emergency Offsite Facilities via PEDS.

• Provides BISI functions (not including operating and trip bypasses of RPS and ESFAS).

• Provides continuous monitoring of RHR system performance when RHR is in use.

ICS is not required to be safety-related and is not required to meet IEEE single-failure criteria for Class 1E equipment.

3. The Plant Computer System and the Integrated Computer System are the same system.

193 7.5.2 7/20/2010 Responder: Clark Open Open EICB (Marcus)

The WBU2 FSAR, Section 7.5.2, Plant Computer There is a single set of hardware that incorporates TVA to respond or System, contains three subsections, the functionality of Safety Parameter Display System provide proposed 7.5.2.1, Safety Parameter Display System (SPDS), Bypass and Inoperable Status Indication date of response.

7.5.2.2, Bypassed and Inoperable Status Indication System (BISI) and the Technical Support Center System (BISI) (TSC).

7.5.2.3, Technical Support Center and Nuclear Data Links Also refer to the response to item 71.

Are there three separate sets of hardware that implement The function of the Nuclear Data Links or Emergency these functions, or are these three functions that are Response Data System (ERDS) is actually provided implemented on a single set of hardware? by the TVA Central Emergency Control Center (CECC) which acts as the Emergency Offsite Facility (EOF) for all of TVAs nuclear units. Plant data will be sent on a periodic basis from the ICS to the CECC via PEDs. That data is then available to be sent from the CECC to the NRC.

194 7.5.2.1 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus)

The WBU2 FSAR Section 7.5.2.1, Safety Parameter The principal purpose and function of the SPDS is to TVA to respond or Display System, contains a description of the Safety aid control room personnel during abnormal and provide proposed Parameter Display System. emergency conditions in determining the safety date of response.

status of the plant and in assessing if abnormal SRP Section 7.5, Subsection II, Acceptance Criteria conditions require corrective action by the operators states: to avoid a degraded core. It also operates during Requirements applicable to the review of SPDS10 CFR normal operations, continuously displaying 50.55a(a)(1), Quality Standards. information from which the plant safety status can be readily and reliably accessed.

Please provide a description of how SPDS meets this regulatory requirement. To ensure quality, the design, testing, and inspection of the SPDS is controlled by qualified personnel and by using TVA procedure SPP-2.6, Computer Software Control. The procedure details controls and processes required for the development, modification, and configuration management of computer software used to support the design, operation, modification, and maintenance of TVAs nuclear power plants consistent with the Nuclear Quality Assurance Plan.

This ensures that the design and operation of the SPDS complies with the 10 CFR 50.55a(a)(1) quality standards requirements. The controls and processes

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date outlined in the procedure provide assurance that the SPDS will perform its intended function correctly.

The plant Integrated Computer System(ICS) provides the SPDS for WBN. Any changes to the SPDS software must be documented and controlled using a Software Service Request(per SPP-2.6) and must be implemented under the engineering design change process(Design Change Notice, DCN).

Controls in SPP-2.6 guide the development and testing of the SPDS changes.

Other controls put in place by this procedure to further maintain quality standards are:

• Changes to SPDS software from remote locations is prohibited.

• The application custodian implements controls to prevent unauthorized changes to the software.

• Changes are made in a non-production environment and validation testing takes place before the change is installed on the ICS.

• Once validation testing begins, the source code is placed under configuration control.

• When the modifications are installed on the ICS, an operability test is performed to demonstrate that the software is installed correctly and is functioning correctly in its operating environment.

• All documentation related to the SPDS software changes are QA records.

• The software source code is kept in a physically secure, environmentally controlled space to prevent inadvertent changes.

• Cyber security considerations are also considered in the storage environment.

The data goes through several validation steps before being presented to the operators. When redundant sensors are used, the data received by the computer can be processed by software to determine if the quality of one or more points is questionable.

195 7.5.2.2 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus)

Bypassed and Inoperable Status Indication (BISI) The BISI system is a computer based system that TVA to respond or provides automatic indication and annunciation of provide proposed The WBU2 FSAR Section 7.5.2.2, Bypassed and the abnormal status of each ESFAS actuated date of response.

Inoperable Status Indication System (BISI), contains a component of each redundant portion of a system description of the Bypassed Inoperable Status Indication that performs a safety-related function.

System (BISI).

To ensure quality, the design, testing, and inspection SRP Section 7.5, Subsection II, Acceptance Criteria of the BISI system is controlled by qualified states: personnel and by using TVA procedure SPP-2.6, Requirements applicable to bypassed and inoperable Computer Software Control. The procedure details status indication 10 CFR 50.55a(a)(1), Quality controls and processes required for the Standards. development, modification, and configuration management of computer software used to support Please provide a description of how BISI meets this the design, operation, modification, and maintenance regulatory requirement. of TVAs nuclear power plants consistent with the Nuclear Quality Assurance Plan.

This ensures that the design and operation of the

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date BISI System complies with the 10 CFR 50.55a(a)(1) quality standards requirements. The controls and processes outlined in the procedure provide assurance that the BISI system will perform its intended function correctly.

The plant Integrated Computer System(ICS) provides the BISI system for WBN. Any changes to the BISI software must be documented and controlled using a Software Service Request(per SPP-2.6) and must be implemented under the engineering design change process(Design Change Notice, DCN). Controls in SPP-2.6 guide the development and testing of the BISI changes.

Other controls put in place by this procedure to further maintain quality standards are:

• Changes to BISI software from remote locations is prohibited.

• The application custodian implements controls to prevent unauthorized changes to the software.

• Changes are made in a non-production environment and validation testing takes place before the change is installed on the ICS.

• Once validation testing begins, the source code is placed under configuration control.

• When the modifications are installed on the ICS, an operability test is performed to demonstrate that the software is installed correctly and is functioning correctly in its operating environment.

• All documentation related to the BISI software changes are QA records.

• The software source code is kept in a physically secure, environmentally controlled space to prevent inadvertent changes.

• Cyber security considerations are also considered in the storage environment.

196 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus)

Bypassed and Inoperable Status Indication (BISI) Section C of the Regulatory Guide lists the following TVA to respond or six regulatory positions for guidance to satisfy the provide proposed The NRC staff is performing its review in accordance with NRC requirements with respect to the bypassed and date of response.

LIC-110, Rev. 1, Watts Bar Unit 2 License Application inoperable status indication(BISI) for nuclear power Review. LIC-110 directs the staff to review systems plant safety systems:

unique to Unit 2 in accordance with current staff guidance.

Regulatory Guide (RG) 1.47 Revision 1, Bypassed and 1. Administrative procedures should be Inoperable Status indication for Nuclear Power Plant supplemented by an indication system that Safety Systems, is the current regulatory guidance for automatically indicates, for each affected safety BISI. Please provide a regulatory evaluation of BISI system or subsystem, the bypass or deliberately against the current RG. induced inoperability of a safety function and the systems actuated or controlled by the safety function. Provisions should also be made to allow the operations staff to confirm that a bypassed safety function has been properly returned to service.

Response: The BISI system provides indication(displays and annunciation) that a functional path for each train of a safety system or support system has been rendered in a state which could cause inoperability. The BISI system monitors and provides system level alarms for these plant safety-related systems:

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date

• Main and Aux Feedwater

• Safety Injection

• Residual Heat Removal

• Containment Spray

• Emergency Gas Treatment

• Essential Raw Cooling Water

• Chemical and Volume Control

• Ventilating

• Component Cooling

• Control Air( including Aux Control Air)

• Standby Diesel Generator The system level displays/indicating lights indicate the status of each systems train functional path as well as the status of any support system that might put the system in an inoperable or bypassed condition.

The BISI system software runs on the Integrated Computer System(ICS) and it provides the capability to monitor in real time the parameters required to provide a BISI system as described in the Reg Guide.

The system level display or indicating lights indicate NORMAL status when a previously bypassed system returns to normal operational status. The Operations staff will determine the impact of each alarm on the process flow path indication during plant modes of operation. The final decision of system operability is left up to the Operations staff to determine per Technical Specifications.

2. The indicating system for BISI should also be activated automatically by the bypassing or the deliberately induced inoperability of any auxiliary or supporting system that effectively bypasses or renders inoperable a safety function and the systems actuated or controlled by the safety function.

Response: The Integrated Computer System(ICS) obtains real-time plant parameter information system by continuously scanning pre-assigned analog, pulse, and contact sensors located throughout the plant to provide status information to the BISI system and automatically displays that information on the BISI terminals in the Main Control Room. Alarms are also initiated to gain the Operations staffs attention.

3. Annunciating functions for system failure and automatic actions based on the self-test or self-diagnostic capabilities of digital computer-based I&C safety systems should be consistent with Positions 1 and 2.

Response: The data goes through several validation steps before being presented to the operators. When redundant sensors are used, the data received by the computer can be processed by software to determine if the quality of one or more points is questionable.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date

4. The bypass and inoperable status indication system should include a capability for ensuring its operable status during normal plant operation to the extent that the indicating and annunciating functions can be verified.

Response: The BISI system is designed to operate during all normal plant modes of operations including startup, shutdown, standby, refueling, and power operation. The ICS is designed to provide a very high degree of reliability and the accuracy of the displayed data is not significantly less than the accuracy of comparable data displayed in the Main Control Room.

5. Bypass and inoperable status indicators should be arranged such that the operator can determine whether continued reactor operation is permissible.

The control room of all affected units should receive an indication of the bypass of shared system safety functions.

Response: A system level display via the BISI display or indicating lights is provided to the operators to indicate the status of the systems being monitored as well as any support systems. If an alarm condition exists, additional detailed information is provided to the operations staff so as to allow determination of the abnormal condition. The information provided will identify to the Operations staff the exact nature of the initiating condition for the abnormal alarm. Each BISI system point will allow the user to access a detailed system screen.

These indicators and alarms will provide critical information to help the operations staff determine whether continued reactor operation is/is not permissible. As stated previously, the final decision of system operability/inoperability is left to the Operations staff to determine per Technical Specifications.

6. Bypass and inoperable status indicators should be designed and installed in a manner that precludes the possibility of adverse effects on plant safety systems. The indication system should not be used to perform functions that are essential to safety, unless it is designed in conformance with criteria established for safety systems.

Response: The BISI system is not designed to safety system criteria and therefore is not to be used to perform functions essential to the health and safety of the public, nor are operator actions based solely on BISI indications.

Appropriate electrical and physical isolation from safety-related equipment to the non-safety system is provided to meet the requirements identified in the FSAR. The ICS is independent of existing sensors and equipment in safety-related systems.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Independence is achieved through qualified safety-related Class 1E isolators. The ICS is also isolated to preclude electrical or electronic interference with existing safety systems.

Inputs and outputs are isolated from the plant inputs such that normal faults on the plant side of the loops will have no adverse impact on the ICS other than loss of the one circuit with the fault. The inputs/outputs meet the isolation requirements of Watts Bar Design Criteria WB-DC-30-4, Separation/Isolation, which defines the design requirements for electrical separation/isolation of the distribution equipment and wiring for Class 1E electrical systems and components in the plant.

197 X Open Item 197 was never issued. Closed Closed 198 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus)

SRP Section 7.5, Subsection III, Review Procedures F. The scope of the WBN BISI indications are based TVA to respond or states: Recommended review emphasis for BISI on engineering calculation WBPEVAR8807025 Rev. provide proposed F. Scope of BISI indications - As a minimum, BISI should 7 (Attachment __). This calculation has not been date of response.

be provided for the following systems: updated for Unit 2. The calculation does include

- Reactor trip system (RTS) and engineered safety Common and Unit 2 equipment required to support features actuation system (ESFAS) - See SRP Appendix Unit 1 operation.

7.1-B subsection 4.13, Indication of Bypasses, and SRP G. Compliance to Regulatory Guide 1.47 is Appendix 7.1-C subsection 5.8.3, Indication of Bypasses. described in design criteria document WB-DC-30-29

- Interlocks for isolation of low-pressure systems from the Rev. 8, Integrated Computer System (Attachment reactor coolant system - See SRP BTP 7-1. __) which is a design input to calculation

- ECCS accumulator isolation valves - See SRP BTP 7-2. WBPEVAR8807025 Rev. 7 (Attachment __).

- Controls for changeover of residual heat removal from H. Design criteria document WB-DC-30-29 Rev. 8, injection to recirculation mode - See SRP BTP 7-6. Integrated Computer System (Attachment __),

G. Conformance with Regulatory Guide 1.47, Bypassed section 3.4.1, BISI Design and Operation states:

and Inoperable Status Indication for Nuclear Power Plant The BISI shall not be designed to safety related Safety Systems. system criteria and therefore is not to be used to H. Independence - See SRP Appendix 7.1-B subsection perform functions essential to the health and safety 4.7, Control and Protection System Interaction, and SRP of the public. Class 1E isolation is required, however, Appendix 7.1-C subsections 5.6, Independence, and 6.3, to maintain the independence of safety related Interaction Between the Sense and Command Features equipment and systems.

and Other Systems. The indication system should be I. - Response in letter from Mike Norman designed and installed in a manner that precludes the possibility of adverse effects on plant safety systems.

Failure or bypass of a protective function should not be a credible consequence of failures occurring in the indication equipment, and the bypass indication should not reduce the required independence between redundant safety systems.

I. Use of digital systems - See SRP Appendix 7.0-A and Appendix 7.1-D.

Please provide a description of how BISI meets each item above, or provide appropriate justification for not doing so.

199 7/20/2010 Responder: Costley/Norman Open Open Related SE Section 7.5.5.3 EICB (Marcus)

The WBU2 FSAR Section 7.5.2.3, Technical Support The Technical Support Center is intended to be an TVA to respond or Center and Nuclear Data Links, contains a description of accident mitigation support center and provides provide proposed the Technical Support Center and Nuclear Data Links. Satellite Display Stations (SDS) capable of date of response.

displaying information on plant systems for Unit 1, SRP Section 7.5, Subsection II, Acceptance Criteria Unit 2 or the Simulator. Stations in the TSC receive states: data from the plant Integrated Computer System Requirements applicable to the review ofERF (ICS) over the ICS network. Separate PCs receive

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date information systems, and ERDS information systems 10 data from the simulator computer over the WBN site CFR 50.55a(a)(1), Quality Standards. network to support drills and training exercises.

Those PCs can also access the Plant Engineering Please provide a description of how the nuclear data links Data System (PEDS) as a backup to ICS. The TSC meets this regulatory requirement. also has a separate computer that connects to the CECC to allow additional access to meteorological station.

The ICS data is also transmitted from the PEDS server through the PEDS Firewall over the WBN Site Network to the CECC computers (Chattanooga). The CECC computers transmit the data over the TVA Corporate Network, through the TVA Firewall (provided by NRC), through the NRC Firewall to the NRC. Transmission of this data from the ICS and Meteorological Station over data link (High Speed Communications Link) to the CECC and NRC meet the requirements of NUREG-0696, Functional Criteria for Emergency Response Facilities and NUREG-1394, Emergency Response Data System Implementation.

200 7/21/2010 Responder: Clark Open Open Related to SE Section 7.5 EICB (Carte)

Amendment 99 of the Watts Bar Unit 2 FSAR Section 7.5, The statement in SER Section 7.5.1 is supported by NRC Review Instrumentation Systems Important to Safety, does not the following:

include any description of instrumentation for normal operation; therefore, Section 7.5 of the FSAR does not I&C Systems for Normal Operation FSAR Section support statements made in the SER Section 7.5; compare Eagle 21 7.2 SER (ML072060490) Section 7.5.1 and FSAR Amendment Neutron Monitoring 7.2 99 Section 7.5. Please identify where, in the docketed Foxboro Spec 200 7.3 (List of other sections in material, information exists to support the statements in attachment 34) the SER Section 7.5.1. Foxboro I/A 7.7.11 (new section will be added by amendment 101) (other sections have been previously provided)

Plant Computer 7.5.2 Rod Control 7.7.1.2 CERPI 7.7.1.2 Control Rod Drive 7.7.1.1 Incore Neutron Monitoring 7.7.1.9 Lose Part Detection/Monitoring 7.6.7 Vibration Monitoring RCP 5.5.1.2 Control Boards 7.1.1.10 RVLIS 7.5, 5.6 201 7/21/2010 Responder: Webb Open Open Related to SE Section 7.7.1.1.1 EICB (Carte)

Amendment 99, FSAR Section 7.7.1.1.1, "Reactor Control These functions are within the scope of the Foxboro TVA to docket Input Signals (Unit 2 Only)," contains a description of I/A system. Section 7.7.11 will be added to the amendment 101.

functions performed uniquely for Unit 2. Please describe FSAR in amendment 101 to provide a discussion of the equipment that performs this function (in sufficient the DCS.

detail to support a regulatory evaluation), and evaluate this equipment against the appropriate regulatory criteria.

202 7/22/2010 Responder: WEC Open Open Relates to SE Section 7.5.2, PAMS EICB (Carte)

The letter (ML0003740165) which transmitted the Safety Revision 1 of the Licensing Technical Report will TVA to respond or Evaluation for the Common Q topical report to provide more detailed information on the changes to provide proposed Westinghouse stated: "Should our criteria or regulations the platform. date of response.

change so that our conclusions as to the acceptability of the report are invalidated, CE Nuclear Power and/or the Rev. 2 of the Licensing Technical Report wil include applicant referencing the topical report will be expected to the applicability of guidance.

revise and resubmit their respective documentation, or submit justification for continued applicability of the topical

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date report without revision of the respective documentation."

Question No 81 identified many criteria changes; please revise the respective documentation or submit justification for continued applicability of the topical report.

203 7/26/2010 Responder: Clark Open Open EICB (Marcus)

By letter datedApril 27, 2010 (ML101230248), TVA stated The plant computer system is one set of hardware. TVA to respond or (Enclosure Item No.19): "The WBN Unit 2 Itegrated The Safety Parameter Display System, Bypassed provide proposed Computer System(ICS) modification merges the ERFDS and Inoperable Status Indication System (BISI), date of response.

and plant computer into a single computer network." Technical Support Center and Nuclear Data Links are all functions of the Plant Computer System.

FSAR Section 7.5.2, "Plant Computer System," has three Historically the Westinghouse P2500 Plant Process subsections: Computer and Emergency Response Facilities Data 7.5.2.1, "Safety Parameter Dispaly System" System (ERFDS) were individual systems but were 7.5.2.2, "Bypassed and Inoperable Status Indication merged together with the implementation of DCN System (BISI)" 39911-A, implemented for WBN Unit 1 in December 7.5.2.3, "Technical Cupport Center and Nuclar Data Links" 1998, to become the Plant Integrated Computer This arrangement implies that the each of these function System (ICS). A similar system is being installed for are part of the plant computer, and not a separate sets of WBN Unit 2 based on the same software with more equipment. Please describe the equipment for each modern hardware.

function and identify any equipment common to more than one function. The ICS is composed of a number of pieces of hardware, all utilized as a system, to provide the functions listed in the FSAR sections 7.5.2.1, 7.5.2.2 and 7.5.2.3. This hardware includes but is not limited to Hewlett Packard (HP) servers (CPU), DELL servers (CPU), Fiber Optic Panels, Fiber Optic Converters, Switches, Firewalls, Network Taps, Multiplexors (RTP), LCD displays and fiber optic and copper Ethernet cables. As all the applicable hardware make up the system it is all common to more than one function and there is no separate set of equipment for any of the functions referenced in FSAR Section 7.5.2.1 and 7.5.2.2.

The Nuclear Data Link and EOF functions described in 7.5.2.3 are provided by the CECC in Chattanooga.

In order for the CECC to have access to ICS data, both the PEDS and the data diode isolating the PEDS from the ICS must be operational.

Meteorological data from the Environmental Data Station (EDS) is gathered by the Unit 1 ICS. That data is sent over to the unit 2 ICS via the inter-unit firewall.

204 7/26/2010 Responder: Costley/Norman Open Open Relates to SE Section 7.5.2, PAMS EICB (Marcus)

By letter dated March 12, 2010 (ML101680577) TVA 1. Three data diodes. TVA to respond or provided drawing No. 2-45W2697-1-1, "Integrated 2. Two provide an interface between train A and B of provide proposed Computer System Network Configuration Connection Common Q. date of response.

Diagram," that depics three "Data Diode"s. Please provide a. These are identical systems consisting of the a detailed description of the equipment, software, and following:

configurations of each "Data Diode". i. Dual DELL R200 computers ii. Red Hat Enterprise Linux software that is locked down by CTI iii. 55 Mbs Owl cards iv. Fiber optic Ethernet interface to trained Maintenance test panel

b. Software is configured to allow only specific traffic from the MTP to pass through to the ICS

c. The secure side of the data diode will initiate the

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date connection to the MTP, so there will be a bidirectional connection between the secure side of the data diode and the MTP. There will be no bidirectional data flow from the ICS to the MTP since the diode will block all incoming traffic from the ICS.

3. The third data diode is placed between the two ICS systems and the two PEDS computer systems.

a. Hardware is identical to that used by TVA in other plants

i. Dual HP DL360GS computers ii. Red Hat Enterprise Linux software that is locked down by CTI iii. 155 Mbs OWL cards iv. RJ45 Ethernet to PEDS network

b. Diode is configured to allow certain types of data to flow from the ICS network to the PEDS network.

This includes but is not limited to the following:

i. Once per second current values and qualities for all points ii. History data archived by the ICS iii. Data files

c. The data diode does not allow any data to be transferred between the PEDS network and the ICS network.

205 7/26/2010 Responder: Clark Open Open Question B related to prior NRC EICB (Garg) approval of this system or 50.59 Regarding the Foxboro Spec 200 system installed at Unit As discussed at the August 3 and 4 meeting in TVA to respond or information. This question will be 2: Knoxville between TVA and the NRC, the Foxboro provide proposed addressed in the August plant visit.

Spec 200 is not a system. The Foxboro Spec 200 date of response.

a- Is it similar to Unit 1? If not, identify the differences and analog hardware is used to replace the existing evaluation of the acceptability of these differences. obsolete hardware with the same functions. There are no interconnections between the analog loops b- deleted unless such interconnections existed prior to the replacement. This is strictly an analog to analog c- For each system which is discussed in the FSAR and upgrade due to equipment obsolescence. The utilizes the Spec 200 system, please provide the Foxboro hardware is installed in existing cabinets instrument logic diagram, loop/block diagram with which require modifications to accept the Foxboro reference to where the system is discussed in the FSAR. hardware racks.

a- A listing of the replacements and differences was previously provided as Attachment 1 to TVA letter to the NRC dated June 18, 2010. Within Unit 1, only portions of the AFW controls were replaced. In Unit 2 all safety-related analog loops were replaced. The Foxboro Spec 200 is a fully qualified industry standard for replacement of obsolete analog instrument and control loop hardware.

b- deleted c- c- The Foxboro Spec 200 hardware has not been installed. Therefore the revised drawings have not been issued. Based on this, EDCR excerpts for the logic diagrams and loop/logic drawings were provided as attachments to TVA letter to the NRC dated July 30, 2010. The cross reference between the functions upgraded as part of the Foxboro Spec 200 change is contained in Attachment 33.

206 EIC 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.5, Plant B

(Mar cus) Computer The NRC Requested a description of the plant computer (1) The Plant Computer is not just a computer but TVA to respond or

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date and TVA provided: is a system and is designated the Integrated provide proposed (1) Dell marketing literature for Dell Poweredge R200 Computer System or ICS. The ICS is composed of date of response.

Server, which can be found on the internet multiple computer CPUs, LCD displays, RTP (http://www.dell.com/downloads/global/products/pedge/en/ Multiplexer Assemblies, network fiber optic panels, pe_R200_spec_sheet_new.pdf), and fiber optic converters, Ethernet switches and network (2) HP Integrity rx2660 Server User Service guide (edition taps previously described in items 71, 81 and 82 6), which has not yet been found on the internet, but many above. For a detailed discussion of the ICS other editions have been found. functions refer to design criteria document WB-DC-This information is not adequate for answering the 30-29 Rev. 8, Integrated Computer System question. (Note: TVA also provided a network submitted under TVA letter dated August __, 2010.

configuration connection diagram, which is necessary but not sufficient.) (2) As previously discussed in item 82, there is no unique set of hardware for any specific function.

Please provide a description of the plant computer:

(1) Please include sufficinet detail so that an evaluation can be mde against the SRP acceptance criteria in SRP Section 7.7.

(2) Please identify the equipment (hardware and software) that performes each function described in the FSAR.

207 July 27, 2010 Date: Closed Closed EICB (Carte)

Responder:

deleted 208 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB (Marcus)

By letter dated June 18, 2010 (ML101940236), TVA The notes provided with the table include the change TVA to respond or responded to an NRC request for additional information. to the variable under 10 CFR 50.59. For ease of provide proposed Enclosure 1 Item No. 6 of this letter identified, for each review, the other note references have been deleted date of response.

PAM variable whether the variable was: (1) implemented for these variables and only the note dealing with the identically to Unit 1 and reviewed by the NRC, (2) Unit 1 change has been retained in the Notes implemented identically to Unit 1 but modified under 10 column of the table excerpt. The applicable notes CFR 50.59 after it was reviewed by the NRC, and (3) are highlighted in the notes list.

implemented in a manner that is unique to Unit 2. There were sixteen variables modified under 10 CFR 50.59; please describe the changes that were performed under 50.59.

209 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB (Marcus)

By letter dated June 18, 2010 (ML101940236), TVA The first eight variables in question are primary TVA to respond or responded to an NRC request for additional information. chemistry parameter. The parameters are the same provide proposed Enclosure 1 Item No. 6 of this letter identified, for each for both units, but in Unit 1, the sample is obtained date of response.

PAM variable whether the variable was: (1) implemented via the post accident sampling system, while in Unit identically to Unit 1 and reviewed by the NRC, (2) 2 the sample is obtained using a grab sample via the implemented identically to Unit 1 but modified under 10 normal sample system.

CFR 50.59 after it was reviewed by the NRC, and (3) implemented in a manner that is unique to Unit 2. There The last variable was somewhat difficult to were nine variables that were identified as both Unique to characterize. The method of detection and the Unit 2 and identical to what was reviewed and approved hardware manufacturer is the same in both units.

on Unit 1. Please explain. However, due to obsolescence some of the parts are different than what is installed in Unit 1. The differences are described in Note 21 of the original response.

210 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB By letter dated June 18, 2010 (ML101940236), TVA The design basis for Unit 2 is to match Unit 1 as TVA to respond or (Marcus) responded to an NRC request for additional information. closely as possible. This includes incorporating provide proposed Enclosure 1 Item No. 6 of this letter identified, for each changes made to Unit 1 after licensing under 10 date of response.

PAM variable whether the variable was: (1) implemented CFR 50.59. The changes in question fall into this

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date identically to Unit 1 and reviewed by the NRC, (2) category and are described in the Notes for each implemented identically to Unit 1 but modified under 10 variable in the original submittal.

CFR 50.59 after it was reviewed by the NRC, and (3) implemented in a manner that is unique to Unit 2. There were seven variables that were identified as both identical to Unit 1 and changed under 10 CFR 50.59. Please explain.

211 7/27/2010 Responder: Clark Open Open Relates to SE Sections:

EICB (Carte) 7.5.5, Plant Computer FSA Table 7.1-1 shows: "The extent to which the The WBN 2 FSAR Section 7.5 defines the following TVA to respond or 7.6.10, Loose Part Monitoring recommendations of the applicable NRC regulatory guides systems as important to safety provide proposed 7.7.1, Control System Description and IEEE standards are followed for the Class 1E date of response. 7.7.2, Safety System Status instrumentation and control systems is shown below. The 1. Post Accident Monitoring including: Monitoring System symbol (F) indicates full compliance. Those which are not a. Common Q Post Accident Monitoring System 7.7.4, Pzr & SG Overfill fully implemented are discussed in the referenced sections(Safety-Related) 7.9, Data Communications of the FSAR and in the footnotes as indicated." i. Reactor Vessel Level ii. Core Exit Thermocouples Please describe how systems that are important to safety, iii. Subcooling Margin Monitor but not 1E, comply with 10 CFR 50.55a(a)1: "Structures, b. Eagle 21 indications (Safety-Related) systems, and components must be designed, fabricated, c. Foxboro Spec 200 indications (Safety-Related) erected, constructed, tested, and inspected to quality d. Neutron Monitoring (Source and Intermediate standards commensurate with the importance of the safety Range) (Safety-Related) function to be performed." e. Radiation Monitors (Safety-Related)

f. Unit 1 and Common shared indications (Safety-Related)

g. Foxboro I/A indications (Non-Safety-Related)

h. Radiation Monitors (Non-Safety-Related)

i. CERPI (Non-Safety-Related)

j. Integrated Computer System (Non-Safety-Related)

k. Unit 1 and Common shared indications (Non-Safety-Related)

Post Accident Monitoring Instrumentation Design Criteria, WB-DC-30-7, Rev. 22, Appendix A provides the minimum quality requirements for each Category (1, 2 or 3) of variable. By definition, no Category 1 variable can be non-safety-related. Therefore, non-safety-related variables and the source equipment are limited to category 2 or 3. Since some variables are designated as having more than 1 category, the requirements of the highest category apply.

Additional design criteria information for specific systems is contained in:

g. Foxboro I/A - Site-Specific Engineering Specification WBN Unit 2 NSSS and BOP Controls Upgrade Specification Rev. 1 (Attachment 23)

h. CERPI - Rod Control System Description, N3 4003, Rev. 12 Section 2.2, Design Requirements

i. Radiation Monitors - Design Criteria Document WB-DC-40-24, Radiation Monitoring - (Unit 1 / Unit 2), Rev. 21

j. Integrated Computer System - Design Criteria Document WB-DC-30-29 Plant Integrated Computer System (ICS), Rev. 8 (Submitted under TVA to NRC letter dated August __, 2010)

2. Plant Computer (Integrated Computer System) -

See Item j above.

The WBN 2 FSAR Section 7.6, defines the following non-safety-related systems as other systems

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date required for safety

1. Foxboro I/A - While not specifically described, functions performed by the system are described in this section. The qualify requirements are described above.

2. Lose Part Monitoring System - Design Criteria Document WB-DC-30-31, Loose Parts Monitoring System, Rev. 4, provides the quality requirements for this system.

Installation is performed in accordance with the quality requirements of either the Bechtel or TVA work order processes based on the quality classification of the equipment being installed.

Vendor testing is performed in accordance with procurement specification requirements which are based on the type and quality classification of the equipment. Preoperational testing is performed in accordance with Chapter 14 of the FSAR.

212 7/27/2010 Responder: WEC Open Open Relates to SE Section 7.5.2 EICB (Carte)

By leter dated June 18, 2010 (ML101940236) TVA stated Application specific requirements for testing. This TVA to respond or (Enclosure 1, Attachment 3, Item No. 3) that the PAMS cannot be addressed in a topical report. Evaluation provide proposed system design specification and software requirements of how the hardware meets the regulatory date of response.

specification contain information to address the "Design requirements.

Report on Computer Integrity, Test and Calibration..." The staff has reviewed these documents, and it is not claer WEC to provide the information and determine how this is the case. where the information will be located.

(1) Please describe how the infomation provided demonstrates compliance with IEEE 603-1991 Clauses 5.5, 5.7, 5.10, & 6.5.

(2) Please describe how the infomation provided demonstrates conformance with IEEE 7-4.3.2-2003 Clauses 5.5 & 57.

213 7/27/2010 Responder: WEC Open Open Relates to SE Section 7.5.2 EICB (Carte)

By leter dated June 18, 2010 (ML101940236) TVA stated Carte to review and revise this TVA to respond or (Enclosure 1, Attachment 3, Item No. 3) that the PAMS question. provide proposed system design specification and software requirements date of response.

specification contain information to address the "Theory of Operation Description." The staff has reviewed these documents, and it is not claer how this is the case. The docketed material does not appear to contain the design basis information that is required to evaluaate compliance with the Clause of IEEE 603.

(1) Please provide the design basis (as described in IEEE 604 Calsue 4) of the Common Q PAMS.

(2) Please provide a regulatory evaluation of how the PAMs complies with the applicable regulatory requirements for the theory of opration.

For example: Regarding IEEE 603 Clause 5.8.4 (1) What are the manually controled protective actions? (2) How do the documents identified demonstrate compliance with this clause?

214 7/27/2010 Responder: WEC Open Open EICB (Carte) By leter dated June 18, 2010 (ML101940236) TVA stated According to "The Software Program Manual for WEC References Common Q TVA to respond or (Enclosure 1, Attachment 3, Item No. 10) that the Common Q Systems," WCAP-16096-NP-1A, the PAMS preliminary hazards provide proposed approved Common Q Topical Report contains information Software Safety Plan only applies to Protection class analysis is referenced in the date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date to address the "Safety Analysis." The Common Q SPM software and PAMS is classified as Important-to- SRS. WEC to delete.

however states that a Preliminary Hazards Analysiss safety. Exhibit 4-1 of the SPM shows that PAMS is Report and the V&V reports document the software classified as Important-to-Safety hazards analysis. Please Provide these documents.

215 7/29/2010 Responder: WEC Open Open DORL (Bailey)

By letter dated June 18, 2010, TVA provided a talbe Close this item TVA to respond or showing the documents that had been completed and provide proposed were available for staff review. In a conference call on date of response.

July 27, 2010, TVA agreed to submit the requested documents on the docket. Please provide the schedule for submitting the documents.

216 7/29/2010 Responder: Clark Open Open EICB (Marcus)

By letter dated March 12, 2010 (ML101680577), TVA 1) EDCR 52322 is contained in Attachment 7. TVA to respond or stated that it would provide five documents to describe the 5) The design change referred to is the addition of a provide proposed Process computer: (1) EDCR 52322 Rev. A excerpts, (2) data diode. This has not been incorporated into the date of response.

HP RX2660 Users Guide AB419-9002C-ed6, (3) Dell drawing. Please see the response to letter item 88 Poweredge R200 Server sheet November 2007, (4) RTP (RAI Matrix Item 224).

Corp 8707 I/O Brochure RTP 8707-02, 2004, and (5)

Integrated Computer System Drawing.

217 7/6/2010 Responder: Clark Open Open EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that Attachment 7 contains excerpts of the following NRC Review provide the block and logic diagrams for the Foxboro Spec change documents:

200 implementation.

DCN 52376 Note: These changes are scheduled to be implemented after Unit 2 Fuel Load DCN 52641 NOTE: DCN 52376 and 52641 impact loops already in service for Unit 1 ansd as such are implemented under 10CFR50.59.

EDCR 52343 EDCR 52427 218 7/6/2010 Responder: Clark Open Open EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that The excerpt of work order WO 08-813412-000 Attachment 8 contains the NRC Review provide the block and logic diagrams for the Foxboro Spec provided with the June 18 letter did not contain the required correct work order 200 implementation. information showing that the new type (Arnold) excerpt.

power supplies had been installed in the Unit 1 Eagle 21 system. Please provide the necessary pages of the work order to verify the installation of Arnold power supplies in the Unit 1 Eagle 21 System.

219 8/4/2010 Responder: TVA Licensing Open Open EICB (Garg) Transmit copy of February 8, 2008 FSAR Red-Line for Unit A copy was hand carried by Mr. W. Crouch and Check what sent by Terry 2 letter with attachments [CD]. delivered to Stewart Bailey at the August 17 meeting missing attachments.

at NRC headquarters.

220 8/4/2010 Responder: Ayala Open Open EICB (Garg)

For Safety Related SSPS, submit letter justifying delta The Westinghouse ARLA latch attachment is Are there any open issues? TVA to respond or between U1 [utilizing ARs] & U2 [utilizing ARs and MDRs]. obsolete. In order to provide a latching relay for Unit Docket plant specific responses provide proposed

[Requires TS change ???] 2 Solid State Protection System (SSPS), a MDR to the individual. date of response.

latching relay must be used. MDR relays are currently in use and shown to be reliable as SSPS Slave Relays in other Westinghouse plants.

The Technical Specification (TS) Bases was updated in Amendment B to indicate acceptability of testing

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date MDR ESFAS Slave relays on an 18-month interval based on the assessment done in WCAP-13878-P-A, Revision 2, Reliability Assessment of Potter &

Brumfield MDR Series Relays.

An initial Unit 2 ESFAS SSPS Slave Relay Service Life and Contact Load study similar to that done in Unit 1 has been completed to show that Unit 2 satisfies the conditions of WCAP-13877-P-A, Revision 2, Reliability Assessment of Westinghouse Type AR Relays used as SSPS Slave Relays, and WCAP-13878, Revision 2, Reliability Assessment of Potter & Brumfield MDR Series Relays. The Contact Load study also identifies locations in which MDR relays are not acceptable for use.

221 8/4/2010 Responder: Trelease Open Open EICB (Garg) Submit EDCR Technical Evaluation for the source and The EDCR _____ Source and Intermediate Range, TVA to respond or intermediate range updated electronics for Unit 2 Scope and Intent, Unit Difference and Technical provide proposed Evaluations are contained in Attachment __. date of response.

222 8/4/2010 Responder: Clark Open Open EICB (Garg) Submit updated list for Foxboro Spec 200 [replacement of The updated listing of Foxboro Spec 200 loop Bailey and Robert-Shaw electronics functions is contained in Attachment 34.

223 8/4/2010 Responder: Clark Closed Closed EICB (Garg)

Submit EDCR Technical Evaluationn for Foxboro I/A Duplicate of item 233.

replacing obsolete non-safety related Foxboro H-Line analog electronics with a digital CDS. [selected single point failures being addressed in design]

224 8/4/2010 Responder: Norman (TVA CEG) Open Open EICB (Marcus)

Mike Norman [TVA Computer Eng. Group] will check The Data diode to isolate the WBN Unit 1 and Unit 2 TVA to respond or status of DCN/50.59 for Integrated Computer System ICS computers from the WBN PEDS computers will provide proposed upgrade that will install the data diode between the WBN be installed in PIC 56278 as part of DCN 54971. date of response.

PEDS and the Unit 1 and Unit 2 ICS. This DCN is scheduled for implementation in Spring 2011. This date was included in the Cyber Security Plan Implementation Schedules submitted to the NRC on July 23.

225 8/4/2010 Responder: Scansen Open Open EICB (Garg)

Provide EDCR Technical Evaluation Justify/explain The requested information is contained in the Scope TVA to respond or updated hardware [functionally equivalent to Unit 1] for the and Intent, Unit Difference and Technical provide proposed RCP and Turbine Generator vibration monitoring Evaluations for EDCRs 52420 (Attachment __) and date of response.

equipment. 53559 (Attachment __)

226 8/4/2010 Responder: TVA Licensing Closed Closed See also Open Item Nos. 41 & 270.

EICB (Carte/Singh)

Submit the Foxboro I/A segmentation analysis and ICS These documents were submitted under TVA letter NNC 8/25/10: Segmentation Design Criteria documents on an expedited separate dated August 11, 2010. analysis has been received and letter. Provide a date when the Segmentation analysis will read. Please describe why a be revised based on discussions at the meeting. failure or error will not propagate over the -peer-to-peer network, and cause more than one segment to fail.

227 8/4/2010 Responder: Clark Open Open EICB (Garg)

Provide copies of 50.59s for the following Unit 1 changes A. CERPI, initial installation DCN 51072 and 2009 TVA to respond or upgrade DCN 52957 (Attachment __) provide proposed

a. CERPI (initial installation and 2009 upgrade) B. Upgrade of RCP, TG and FW pumps vibration date of response.

b. Vibration monitoring (RCP, TG and FW pumps to monitoring to Bentley-Nevada 3300, DCN 39242,

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Bentley-Nevada 3300) DCN 39506, DCN 39548, and DCN 50750

c. Containment Sump Level Transmitter replacement (Attachment __)

d. Turbine Servo Control Valve Card replacement C. Containment Sump Level Transmitter

e. Pressurizer Heater deletion of Backup Heaters on for replacement, DCN 39608, (Attachment __)

PZR High Level D. Turbine Servo Control Valve Card replacement,

f. AMSAC DCN 38993, (Attachment 1)

g. Significant ESFAS changes E. Pressurizer Heater deletion of Backup Heaters on for PZR High Level, DCN 51102 (Attachment __)

F. AMSAC DCN 50475 (Attachment __)

G. Significant ESFAS changes

i. Relocate containment isolation valve functions on relays K002 and K626 to prevent plant shutdown during routine surveillance testing. DCN 38238, (Attachment __)

ii. Revise OT T and OP T turbine runback setpoints, DCN 38842 (Attachment __)

iii. Install Integrated Computer System (ICS), DCN 50301 (Attachment __)

228 8/4/2010 Responder: Clark Open Open EICB (Carte/Sin Submit rod control system description N3-85-4003 The Rod Control Systemt Desciption N3-85-4003 is TVA to respond or gh) contained in Attachment 21. provide proposed date of response.

229 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit Annunciator system description/design criteria Condition Status/Alarm Design Criteria Document NNC 8/25/10: Document not yet TVA to respond or WB-DC-30-21 is contained in Attachment 22. received. provide proposed date of response.

230 8/4/2010 Responder: Webb Open Open EICB (Carte) Submit Foxboro I/A Procurement Specification excerpts The requested Foxboro I/A Procurement NNC 8/25/10: Document not yet TVA to respond or that provide system description information Specificaition is contained in Attachment 23. received. provide proposed Discuss with Steve Hilmes 1 page description date of response.

231 8/4/2010 Responder: Clark Open Open EICB (Garg)

Update FSAR Amendment 100 Section 7.1.1.2 markup FSAR section 7.1.1.2 is revised in FSAR FSAR Amd 100 based on discussion with Hukam Garg. Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 includes the requested clarifications.

232 8/4/2010 Responder: Clark Open Open EICB (Garg) Submit EDCR Technical Evaluation for LPMS EDCR The EDCR 52418 Lose Part Monitoring Scope and TVA to respond or Intent, Unit Difference and Technical Evaluations are provide proposed contained in Attachment 24. date of response.

233 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit EDCR Technical Evaluation for Foxboro I/A EDCR Foxboro I/A EDCRs 52378 and 52671 Scope and NNC 8/25/10: Documents NRC to review Intent, Unit Difference and Technical Evaluations are received. documents.

contained in Attachment 25.

234 8/4/2010 Responder: Closed Closed EICB (Carte) Bechtel to perform D3 analysis for Common Q PAMS Duplicate of Item 64 which will be incorporated into Westinghouse Licensing Technical Report.

235 8/4/2010 Responder: TVA Licensing Closed Closed EICB (Garg) TVA to ensure Stewart Bailey is on cc: for all Chapter 7 Stewart Bailey has been added to the standard RAI response letters. response letter template used for Chapter 7 responses.

(

236 G 8/4/2010 Responder: Clark Open Open

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Submit EDCR Technical Evaluation for Foxboro Spec 200 Foxboro Spec 200 EDCRs 52343, 52427 and 52641, TVA to respond or EDCRs Scope and Intent, Unit Difference and Technical provide proposed Evaluations are contained in Attachment 26. date of response.

237 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit EDCR Technical Evaluation for Annunciator The Annunciator EDCR 52315 Scope and Intent, NNC 8/25/10: Documents not yet TVA to respond or EDCR Unit Difference and Technical Evaluations are received. provide proposed contained in Attachment 27. date of response.

238 8/4/2010 Responder: Webb/Hilmes Closed Closed EICB (Carte) Discuss with TVA adding a description of the Foxboro I/A Duplicate of item 201 system to chapter 7 of the FSAR.

239 8/4/2010 Responder: Hilmes Closed Closed EICB (Carte) Plan a meeting with TVA the NRC and Westinghouse to meeting held 8/17/10 review Common Q PAMS documentation.

240 8/4/2010 Responder: Clark Open Open EICB (Garg) Submit EDCR Technical Evaluation for Vibration The Scope and Intent, Unit Difference and Technical TVA to respond or Monitoring EDCR(s) Evaluations for EDCRs 53559 and 52420 are provide proposed contained in Attachment 28. date of response.

241 8/4/2010 Responder: Davies Open Open EICB (Singh)

Review CERPI WCAPs for system description information CERPI was designed after Westinghouse stopped TVA to respond or to be submitted to the NRC. using WCAPs. The documents that provides the provide proposed most detailed information are the CERPI System date of response.

Requirements Specification WN-DS-00001-WBT Rev. 2. This document is containted in Attachment 242 8/4/2010 Responder: Hilmes Open Open EICB (Garg) TVA to make firm decision on date of transfer (before or The Unit 2 loops in service for Unit that are TVA to respond or after initial startup) of Unit 2 loops in service for Unit 1 to scheduled to be transferred to the Foxboro Spec 200 provide proposed new Foxboro Spec 200 hardware hardware will be transferred prior to Unit 2 fuel load. date of response.

243 8/3/2010 Responder: WEC Open Open EICB (Carte)

Section 8.2.1 of the Common Q SPM (ML050350234) WEC to address at the 9/15 meeting TVA to respond or states that the System Requirements Specification provide proposed (SysRS) includes the system design basis. Section 1.2, date of response.

"System Scope," of the WBN2 PAM SysRS (ML101680578) includes a description of the PAMS design bases that does not meet the requirments of IEEE 603-199 Clause 4. Please provide a description of the PAMs design bases that conforms to the requirements of IEEE 603-1991 Clause 4.

244 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the Section 8.2.2 of the Common Q SPM (ML050350234) WEC agreed to remove process related items from TVA to respond or information relied upon in the SE must states that the Software Requirements Specification (SRS) all docs. Close to previous item and revise previous provide proposed be docketed correspondence."

shall be develped using IEEE 830 and RE 1.172. Clause item to include all documents. date of response.

4.8, "Embedding project requirements in the SRS," of the LIC-101 Rev. 3 states: "The safety IEEE 830 states that an SRS should address the software analysis that supports the change product, not the process of producing the software. In requested should include technical addition Section 4.3.2.1 of the SPM states "Any information in sufficient detail to alternatives to the SPM processes or additional project enable the NRC staff to make an specific information for the ...SCMP...shall be specified in independent assessment regarding the PQP. the acceptability of the proposal in terms of regulatory requirements and Contrary to these two statements in the SPM, the WBN2 the protection of public health and

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date PAMS SRS (ML101050202) contains many process safety."

related requirments, for example all seventeen requirements in Section 2.3.2, "Configuration Control,"

address process requirements for configuration control.

Please explain how the above meets the intent of the approved SPM.

245 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the Section 5.8 of the Common Q SPM (ML050350234) Relates to the commitment to provide the test plan TVA to respond or information relied upon in the SE must identifies the required test documentation for systems and the SPM compliance matrix provide proposed be docketed correspondence."

developed using the Common Q SPM. Please provide date of response.

sufficient information for the NRC staff to independently LIC-101 Rev. 3 states: "The safety asssess whether the test plan for WBN2 PAMS, is as analysis that supports the change described in the SPM (e.g., Section 5.8.1). requested should include technical information in sufficient detail to enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

246 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the Section 4.3.2.1, "Initiation Phase" of the Common Q SPM There is a PQP and SPM compliance matrix will be TVA to respond or information relied upon in the SE must (ML050350234) requires that a Project Quality Plan (PQP) referenced in the Licensing Technical Report. provide proposed be docketed correspondence."

be developed. Many other section of the SPM identify that date of response.

this PQP should contain information reuired by ISG6. WEC to identify the elements of the SPM in the LIC-101 Rev. 3 states: "The safety Please provide the PQP. If "PQP" is not the name of the compliance matrix analysis that supports the change documentation produced, please describe the requested should include technical documentation producted and provide the information that information in sufficient detail to the SPM states should be in the PQP. enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

247 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the As part of the Common Q topical report development The documents will be identified in Rev. 1 of the TVA to respond or information relied upon in the SE must effort, Westinghouse developed the Software Program Licensing Technical Report in the compliance matrix. provide proposed be docketed correspondence."

Manual for Common Q Systems (ML050350234) to WEC to make the documents available ASAP in date of response.

address software planning documentation. The NRC Rockville. May require later submittal. LIC-101 Rev. 3 states: "The safety reviewed the SPM and concluded: the SPM specifies analysis that supports the change plans that will provide a quality software life cycle process, requested should include technical and that these plans commit to documentation of life cycle information in sufficient detail to activities that will permit the staff or others to evaluate the enable the NRC staff to make an quality of the design features upon which the safety independent assessment regarding determination will be based. The staff will review the the acceptability of the proposal in Implementation of the life cycle process and the software terms of regulatory requirements and life cycle process design outputs for specific applications the protection of public health and on a plant-specific basis. Please identify the safety."

implementation documentation produced as a result of following the SPM, and state what information will be docketed.

248 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the As part of the Common Q topical report development The documents will be identified in Rev. 1 of the TVA to respond or information relied upon in the SE must effort, Westinghouse developed the Software Program Licensing Technical Report in the compliance matrix. provide proposed be docketed correspondence."

Manual for Common Q Systems (ML050350234) to WEC to make the documents available ASAP in date of response.

address software planning documentation. The NRC Rockville. May require later submittal. LIC-101 Rev. 3 states: "The safety

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date reviewed the SPM and concluded: the SPM specifies analysis that supports the change plans that will provide a quality software life cycle process, requested should include technical and that these plans commit to documentation of life cycle information in sufficient detail to activities that will permit the staff or others to evaluate the enable the NRC staff to make an quality of the design features upon which the safety independent assessment regarding determination will be based. The staff will review the the acceptability of the proposal in Implementation of the life cycle process and the software terms of regulatory requirements and life cycle process design outputs for specific applications the protection of public health and on a plant-specific basis. Please identify the design safety."

outputs produced as a result of following the SPM, and state when what information will be docketed.

249 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the The SVVP in the SPM describes the V&V implementation Close to previous items to provide the V&V Reports. TVA to respond or information relied upon in the SE must tasks that are to be carried out. The acceptance criterion provide proposed be docketed correspondence."

for software V&V implementation is that the tasks in the date of response.

SVVP have been carried out in their entirety. LIC-101 Rev. 3 states: "The safety Documentation should exist that shows that the V&V tasks analysis that supports the change have been successfully accomplished for each life cycle requested should include technical activity group. Please provide information that shows that information in sufficient detail to the V&V tasks havebeen successfully acomplished for enable the NRC staff to make an each life cycle actifity group. independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

250 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the The SPM describes the software and documents that will Westinghouse develops Software Release TVA to respond or information relied upon in the SE must be created and placed under configuration control. The Reports/Records and a Configuration Management provide proposed be docketed correspondence."

SCMP (e.g., SPM Section 6, Software Configuration Release Report. Describe the documents and when date of response.

Management Plan) describes the implementation tasks they will be produced. Sumarize guidance on how to LIC-101 Rev. 3 states: "The safety that are to be carried out. The acceptance criterion for produce these records, focus on project specific analysis that supports the change software CM implementation is that the tasks in the SCMP requirements in SPM etc. requested should include technical have been carried out in their entirety. Documentation information in sufficient detail to should exist that shows that the configuration management enable the NRC staff to make an tasks for that activity group have been successfully independent assessment regarding accomplished. Please provide information that shows that the acceptability of the proposal in the CM tasks have been successfully accomplished for terms of regulatory requirements and each life cycle activity group. the protection of public health and safety."

251 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB (Carte)

"Safety Evaluation" states: "the The SPM describes the software testing and documents Addressed by SPM Compliance matrix in Rev. 1 of TVA to respond or information relied upon in the SE must that will be created. The SPM also describes the testing the Licensing Technical Report. provide proposed be docketed correspondence."

tasks that are to be carried out. The acceptance criterion Norbert is looking for guidance on how to ask for date of response.

for software test implementation is that the tasks in the less. LIC-101 Rev. 3 states: "The safety SPM have been carried out in their entirety. Please analysis that supports the change provide information that shows that testing been requested should include technical successfully accomplished. information in sufficient detail to enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

252 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section 4, EICB "Safety Evaluation" states: "the (Carte) The SPM contain requirements for software requirements Explain response to AP1000 audit report. Read ML091560352 TVA to respond or information relied upon in the SE must traceability analysis and associated documentation (see RTM docketed NRC awaiting V&V evaluation of provide proposed be docketed correspondence."

Section 5.4.5.3, Requirements Traceability Analysis). RTM. date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Please provide information that demonstrates that LIC-101 Rev. 3 states: "The safety requirements traceability analysis has been successfully analysis that supports the change accomplished. requested should include technical information in sufficient detail to enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

253 8/8/2010 Responder: Clark Open Open Related to Open Item no. 83.

EICB (Carte)

TVA provided information by letter dated July 30, 2010 Identify only FPGAs in new or revised modules. If TVA to respond or LIC-110 Rev. 1 Section 6.2.2 states:

(ML102160349) - See Enclosure 1 Item No. 8 - that some none, provide a revised response. Steve Clark to provide proposed "Design features and administrative AC160 module contain FPGAs. For those modules that revise response. date of response. programs that are unique to Unit 2 have not been previously approved, please provide should then be reviewed in information to address regulatory criteria for FPGAs. accordance with current staff positions" LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

254 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

WNA-PD-00056-WBT, Rev 1 Watts Bar Unit 2 NSSS Completion I&C Projects As the indicated source of customer specific requirements for deliverables, as indicated in the project plan, this document may serve as one end of a thread audit, and may contain information relevant to evaluating the completeness of later requirements.

956080, Rev 1. Cabinet mounted electronics -

Inadequate core cool monitor (ICCM-86)

Believe this to be the source of the requirements or at least algorithms and justifications for RIVLIS.

NABU-DP-00014-GEN, rev 2 Design Process for Common Q Safety Systems. As it defines the scope of other documents we are reviewing, it may clarify what documents are expected to contain what information.

255 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed The Reusable Software Elements Documents. These date of response.

contain requirements for the software.

WNA-DS-01564-GEN, Rev 1. ; WNA-DS-00315-GEN, Rev. 2 ; WNA-DS-01715-GEN, Rev 2 ; WNA-DS-01838-GEN, Rev. 3 ; WNA-DS-01839-GEN, Rev. 3 ; WNA-DS-01840-GEN, Rev 2. ; WNA-DS-01841, Rev 2. ; WNA-DS-01842-GEN Rev 2.; WNA-DS-01845-GEN Rev. 1. ; WNA-DS-01846-GEN Rev. 2 ; WNA-DS-01847-GEN Rev. 0 ;

WNA-DS-01848 Rev. 1. ; WNA-DS-01849-GEN Rev. 2. ;

WNA-DS-01994-GEN Rev. 0 ; WNA-DS-00306-GEN Rev.

5 ; WNA-DS-02065-GEN Rev. 2 ; WNA-DS-01505-GEN Rev. 0

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Further documentation for application-specific type circuits and custom PC elements are indicated by the SRS to be in 00000-ICE-3238, Rev 5 ; 00000-ICE-30140, rev 4 and 00000-ICE-30152, Rev. 5 256 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The following are documents that contain requirements used in the SRS which we incorporated by reference within that document.

Coding Standards and Guidelines for Common Q Systems, 00000-ICE-3889, Rev. 10, Westinghouse Electric Company LLC.

Application Restrictions for Generic Common Q Qualification, WNA-DS-01070-GEN, Rev. 3, Westinghouse Electric Company LLC.

System Requirements Specification for the Common Q Generic Flat Panel Display 00000-ICE-30155, Rev. 9, Westinghouse Electric Company LLC.

Software Requirements Specification for the Common Q Generic Flat Panel Display Software, 00000-ICE-3239, Rev. 12, Westinghouse Electric Company LLC.

Common Q Software Configuration Management Guidelines, NABU-DP-00015-GEN, Rev. 2, Westinghouse Electric Company LLC, Standard General Requirements for Cyber security, WNA-DS-01150-GEN, Rev. 0, Westinghouse Electric Company LLC, 257 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The following are documents that contain requirements used in the SRS which we incorporated by reference within that document.

AC160 CPU Loading Restrictions, AN03007Sp, ABB Memo, ABB Process Automation Corporation, Software Design Description for the Common Q Generic Flat-Panel Display Software, 00000-ICE-30157, Rev. 16, Westinghouse Electric Company LLC.

System Requirements Specification for the Common Q Post Accident Monitoring System, 0000-ICE-30156, Rev.

06, Westinghouse Electric Company LLC.

Software Requirements Specification for the Common Q Post Accident Monitoring System 00000-ICE-3238, Rev.

5, Westinghouse Electric Company LLC.

Commercial Dedication Report for QNX 4.25G for Common Q Applications, WNA-CD-00018-GEN, Rev. 3,

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Westinghouse Electric Company LLC, Generic Common Q Software Installation Procedure, WNA-IP-00152-GEN, Rev. 7, Westinghouse Electric Company LLC.

258 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The IV&V Phase Summary Report, (WNA-VR-00283-WBT Rev . 0 ) indicated that the IV&V team had created some information that may facilitate the approval process.

However the form the information may have taken was not indicated or referenced in the Phase Summary Report.

Information requested for the Rockville office includes:

-The excel spreadsheet described in section 2.2.2 that verifies all low level requirements have a basis in a higher one, and that all higher level requirements decompose into a lower level.

-A review of the WBU2 SysRS, SDS, and SRS for clarity, completeness, correctness and compatibility

-Comparison of the WBU2 SysRS, SDS, and SRS to source level documents

-An evaluation, per section 2.2.3, of the baseline report

-a second party peer review for the source level documents 259 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

As they may demonstrate that a number of issues raised by, or that will be raised by, the NRC staff are already being resolved by the vendor, we would like to have access to V&V-769 and V&V-770 in the Exception Reports (ER) database for common Q systems.

260 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The Source level documents for the requirements WBT-TVA-0070 Safety Related Digital Logic Cards Circuitry and Related Instrument Racks Restrictions WBT-D-0088 Transmittal Westinghouse comments on TVA specification EDSR 52451 Contract Number 65717 Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2 NSSS Completion Project WEST-WBT-2008-25 TVA Contract Word Authorization 261 8/10/2010 Responder: WEC Open Open LIC-110 Rev. 1 Section 6.2.2 states:

EICB "Design features and administrative Please provide the Requirements Traceability Matrix for WEC to make available in Rockville ASAP. May TVA to respond or programs that are unique to Unit 2 (Halverson) generic PAMS and/or any other RTMs applicable to WBN2 require later submittal per 9/15 meeting. provide proposed should then be reviewed in PAMS. Some requirements in the Software date of response. accordance with current staff Requirements Specification are simply not present in the positions" Watts Bar 2 PAMS specific RTM (WNA-VR-00279-WBT).

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

262 8/10/2010 Responder: WEC Open Open EICB (Halverson)

In order to facilityate visits to the Rockville office, please WEC Reviewing to ensure all documents are TVA to respond or make the following documents available at the Rockville available in Rockville office. provide proposed office. date of response.

Watts Bar 2 PAMS licensing technical report 00000-ICE-37722 Rev. 0 (ML003733136)

Common Q Software Programming manual (ML050350234)

Common Q topical report. (ML031830959) 263 8/11/2010 Responder: WEC Open Open EICB (Carte)

Based on an examination of document available at the Westinghouse Rockville offices (i.e., NA 7.4, WEC 7.2, Addressed in 9/20 - 9/21 audit. TVA to respond or WEC 7.3, CDI-3803, & CDI-3722) a CDI appears to provide proposed identify the verification activities for each critical date of response.

characteristic. These activities appear to be documented on the associated dedication data sheets; therefore, it appears that the Westignhouse Commercial Grade Dedication Plan is called a CDI and the completed CDI data sheets are the commercial grade desication Report.

If so, please provide the CDI for each new (not previously approved) component and the associated completed dedication data sheets.

264 8/11/2010 Responder: WEC Open Open EICB (Carte) Please provide a copy of the commercial grade survey(s) After the 9/20 - 9/21 audit. TVA to respond or applicable to each new (not previously approved) Common provide proposed Q component. date of response.

265 8/11/2010 Responder: WEC Open Open EICB (Carte) Please provide: After the 9/20 - 9/21 audit. TVA to respond or WNA-CD-00018-GEN Rev. 3 provide proposed 00000-ICE-35444 Rev. 1 date of response.

266 8/11/2010 Responder: Webb/Webber Open Open EICB (Carte)

Please provide a high level description of the Foxboro IA SER Level writeup. Steve Hilmes TVA to respond or equipment used at WBN2. This description should be provide proposed more detailed than a brochure on the product line (or date of response.

available on the web), and less detailed than a technical manual on each field replaceable unit. It is expected that such literature already exists.

267 8/11/2010 Responder: WEC Open Open EICB (Carte)

By letter dated June 18, 2010 (ML101940236) TVA stated References will be removed as appropriate. TVA to respond or that the software safety plan (SSP) was not applicable to provide proposed PAMS applications (see Watts Bar 2 - Common Q PAMS date of response.

ISG-6 Compliance matrix Item No. 10); however, reference No. 30 of the SRS (ML101050202) is: 00000-ICE-37727, Rev. 0, "Post Accident Monitoring System Softwarre Preliminary Hazard Analysis for the Common Q PAMS Project." A Preliminary Hazard Analysis is required by the SSP. Please explain.

268 EIC 8/19/2010 Responder: WEC Open Open B

(Cart e)

By letter dated March 12, 2010 (ML101680577), TVA TVA to respond or

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date stated that the application specific hardware and software Andy to see what can be done. provide proposed architecture descriptions are addressed in the WBN2 date of response.

PAMS System Design Specification (ML101680579, ML102040481, & ML102040482) and Software Requirements Specification (ML101050202, ML102040486, & ML1022040487).

Neither of these documents contain a non-proprietary figure of the architecture that can be used in the SE.

Please provide a non-proprietary figure of the architecture.

269 8/20/2010 Responder: NRC Open Open DORL (Bailey) DORL to send the Eagle-21 Audit Report to TVA.

270 8/23/2010 Responder: Clark Open Open See also Open Item Nos. 41 & 226.

EICB (Carte)

By letter dated June 18, 2009 (ML091560352) the NRC informed Westinghouse that WNA-PT-00058-GEN (see Close to items 41 and 226 Steve Clark to confirm pdf page 7 of 25) did not adequately address the test plan item references and close.

criteria of the Software Program Manual (ML050350234);

however, by letter dated June 18, 2010 (ML101940236)

TVA/Westinghouse stated that WNA-PT-00058-GEN addressed the test plan criteria of the SPM (pdf page 59 of 194, Item No. 12). Please explain.

271 8/23/2010 Responder: WEC Open Open EICB (Carte)

By letter dated August 20, 2010 TVA dockated a 9/15 meeting and 9/20 audit Requirements Traceability Matrix for the Common Q PAMS (Requirements Phase).This document does not identify the source of each requirement. The Comon Q PAMS System Requirements Specification (SysRS -

ML101680578, ML102040483, & ML102040484) does not explicitly identify the origin of each requirement. The SRP acceptance criteria for requirements specifications is that the origin of the requirements is know. Please explain how to trace each requirement in the SysRS to its origin.

272 7.5 8/26/2010 Responder: Clark Open Open EICB (Marcus)

In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations),"

(WBNP-96) for Variable 19, "Containment Hydrogem Concentration," Deviation 2 (page 19 of 41), the variable number is listed as 15. The variable number should be listed as 19.

273 7.5 8/26/2010 Responder: Clark Open Open EICB (Marcus)

In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 State samples are taken via the normal sample Variable List (Deviation and Justification for Deviations)," system.

(WBNP-96) for Variable 97g, "Reactor Coolant Sample Activity," Deviation 5 (page 21 of 41), the last two sentences of the Justification read, "TVA meets the intent of RG 1.97 recommended range by monitoring this variable using the gross activity analysis of primary coolant samples taken in the post accident sampling facility.

Samples are obtained from the post accident sampling system in Unit 1 only." Please describe how the samples are obtained for Unit 2.

274. 7.5 EICB 8/26/2010 Responder: Clark Open Open a (Marcu s) In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations),"

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date (WBNP-96) for Variable 82, "Steam Generator Level Wide Range," Deviation 10 (page 24 of 41), in the last sentence, of the Justification, SC should be SG.

274. 8/26/2010 Responder: Clark Open Open b EICB (Singh) Loose Parts Monitoring System: TR 3.3 refers to section 4.4.6 of the FSAR for description of the loose parts monitoring system. However, this section of the FSAR is not available. TVA to check the reference and respond.

275 8/27/2010 Responder: Clark Closed Closed EICB (Singh)

Loose Parts Monitoring System: RG 1.133, sections C.1.a and C.1.c address sensor locations and channel separation respectively. TR 3.3, FSAR section 7.6.7 and the DMIMMS-DX System Description do not clearly explain the location or address channel separation per the guidance of RG 1.133. Please update the documents as needed.

276 8/27/2010 Responder: Tindell Open Open EICB (Garg)

In order for the staff to review the effects of multi control systems failure, provide the summary of the analyses documenting the effect on the plant based on the following events: (1) loss of power to all control systems powered by a single power supply; (2) failure of each instrument sensor which provides signal to two or more control systems; (3) Break of any sensor impulse line which is used for sensors providing signals to two or more control systems; and (4) failure of digital system based on the common cause software failure affecting two or more control systems. For each of these events, confirm that the consequences of these events will not be outside chapter 15 analyses or beyond the capability of operators or safety systems.

277 7.6.3 8/27/2010 Responder: Clark Open Open EICB (Garg)

NUREG 0847, "Safety evaluation report Related to the operation of Watts Bar Nuclear Plant, Units 1 and 2." has section 7.6.3 which discusses the, "Upper Head Injection Manual Control" system but has been removed from the FSAR. Please provide the information regarding when this system was removed, and the justification for the removal of the system and if the NRC staff has previously reviewed and accepted the removal of the system provide the reference to the staff's SE.

278 7.6.6 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.6, provide the justification for adding valves FCV 63-8 and FCV 63-11, which require that power to be removed and will be administratively controlled prior to use of RHR system for plant cooldown. Provide the P &

ID and block diagram showing the operation of these valves.

279 7.6.6 8/27/2010 Responder: Clark Open Open

( EICB (Garg) For FSAR Section 7.6.6, provide the justification for the addition of protective covers which operator has to remove G

before he can have access to control switch to operate two additional valves FCV62-98 and FCV62-99.

280 7.6.6 8/27/2010 Responder: Clark Open Open

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date For FSAR Section 7.6.6, provide the justification for the acceptability of removing FCV 63-5 from the list of valves which has operating instructions specifying the removal of power during specific modes of plant operation.

281 7.6.8 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.8 in amendment 96, redline version has completely rewritten this section of the FSAR, however, the staff is not able to determine any changes made to the section. Explain what changes have been made to this FSAR Section.

282 7.6.9 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.9 which discusses the switch over from injection to recirculation, and is a ESF system, the compliance with IEEE 279 has been removed from the FSAR. Justify this deletion.

283 7.7.5 XX 8/27/2010 Responder: Clark Open Open This item is a followup question to EICB (Darbali) item 96.

Follow-up to item 96 On Open Item 96, regarding the implementation of IEN 79-22, part of TVAs response was:

The non-safety-related device/systems within the scope of IEN 79-22 are:

1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

Failure of these systems/devices due to a high energy line break is fully addressed in Chapter 15, Accident Analysis of the WBN Unit 2 FSAR.

Please identify the sections of FSAR Chapter 15 that address the failures of these systems.

284 7.7.3 7.4.1 8/27/2010 Responder: Troutman Open Open This item is a followup question to EICB item 123 Follow-up to item 123 (Darbali)

Please provide a readable electrical logic diagram of the Volume Control Tank Level Control System.

285 7.3 7.3 8/27/2010 Responder: Clark Open Open This item is a followup question to EICB (Darbali) item 22 Follow-up to item 22 Do the control loops meet the requirements of IEEE-279?

If not are they isolated from the circuit which meets the requirements of 279.

286 7.7.3 9.3.4.2 8/27/2010 Responder: Clark Open Open EICB (Darbali)

.4 SE 7.7.3, Volume Control Tank Level Control System In FSAR section 9.3.4.2.4 a change was made to the last paragraph of the Volume Control Tank description (page 9.3-31 of the Amendment 97 redline), where the "low-low level alarm" was changed to "low level alarm".

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date Please explain if this deletion was an editorial change to correct a typo.

287 7.7.8 7.7.1.1 8/27/2010 Open Open EICB (Darbali) 2 In Amendment 95 of FSAR section 7.3.2.3 Further Considerations, the list of signals that would start the auxiliary feedwater motor driven and turbine driven pumps was moved to table 7.3-1 item 3, Auxiliary Feedwater.

However, item (6) AMSAC was not included in table 7.3-1.

Please explain this omission or state your commitment to correct this in a future amendment.

288 7.3 9/2/2010 Responder: McNeil Open Open EICB (Garg) Can we add a section to chapter 7 giving a brief overview of the Foxboro Spec 200 in Section 7.3?

289 9/2/2010 Responder: Mather Open Open EICB (Singh) Provide an ISG4 diversity analysis for the containment high range accident monitors RM-1000.

290 7.7 9/7/2010 Responder: Clark Open Open EICB (Carte) The equation at the bottom of Amendment 99 page 7.7-3 is wrong. There are two ways that this equation is inconsistent with the text above it.

291 7.7 9/7/2010 Responder: Clark Open Open EICB (Carte) The equation at the bottom of Amendment 100 page 7.7-3 is wrong. There are two ways that this equation is inconsistent with the text above it.

292 7.2 9/7/2010 Open Open EICB (Garg)

FSAR Section 7.2, Steam Generator Reference Leg: By letter dated July 27, 1994, TVA had withdrawn its commitment on Unit 1 to insulate SG reference leg. TVA had provided an analysis to justify this action which was accepted by the staff. Confirm whether SG reference leg in Unit 2 are insulated and if not then confirm that the analysis which was submitted for Unit 1 is also applicable to Unit 2.

293 7.2.2.3 9/8/2010 Open Open EICB (Marcus)

.5 FSAR Amendment 100, Section 7.2.2.3.5 discusses Steam Generator Water Level and protection against low water level. However, this section does not discuss protection against Steam Generator overfill. Additionally, FSAR Section 7.2.2.3.4 discusses Pressurizer Water Level and provides minimal information concerning Pressurizer overfill. Please provide a discussion of protection against Pressurizer and Steam Generator overfill.

294 7.3 7.3.1.1 9/9/2010 Open Open

.1 EICB (Darbali) In Amendment 95 of FSAR section 7.3.1.1.1 Function Initiation, item (13) was arranged into paragraph form from

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date what used to be a listing of items (a), (b) and (c).

The second bullet under item (c) was omitted in the new paragraph.

Intitiates Phase B containment isolation of the following:

• Closure of the main steam isolation valves (MSIV) to limit reactor coolant system cooldown for breaks downstream of the MSIVs.

Please explain this omission or state your commitment to correct this in a future amendment.

295 7.3 7.3.1.1 9/9/2010 Open Open EICB (Darbali)

.2 In Amendment 95 of FSAR section 7.3.1.1.2 Process Protection Circuitry, item (3), references to sections 7.6 and 7.7 were removed.

Please explain the reason for removal.

296 7.3 7.3.1.2 9/9/2010 Open Open EICB (Darbali)

.1 In Amendment 95 of FSAR section 7.3.1.2.1 Generating Station Conditions, the new paragraph was arranged from what used to be a listing of items (1.b), (1.c), and (2.b),

leaving out items (1.a) and (2.a). Even if the paragraph contains the word include, the breaks in items (1.a) and (2.a) should be listed.

Please explain this omission or state your commitment to correct this in a future amendment.

297 7.3 7.3.1.2 9/9/2010 Open Open EICB (Darbali)

.2 In Amendment 95 of FSAR section 7.3.1.2.2 Generating Station Variables, the following sentence was erased:

Post accident monitoring requirements and variables are given in Tables 7.5-1 and 7.5-2.

Please explain the reason for removal.

298 7.3 XX 9/9/2010 Open Open EICB (Darbali)

IE Bulletin 80-06 calls for review of engineered safety features with the objective of ensuring that no device will change position solely because of the reset action.

In Supplement 3 of NUREG-0847, section 7.3.5, the staff approved the design modifications proposed by the applicant that would allow certain devices to remain unchanged upon an ESF reset. The staff also found acceptable the applicants justification for some safety-

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval RAI SE FSAR NRC Prop No. POC Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments Section Section Y/N Date related equipment that does not remain in its emergency mode after an ESF reset.

Please confirm whether or not the equipment that was determined in NUREG-0847 and its supplements to remain unchanged upon an ESF reset will still remain unchanged in Unit 2.

Open Open X X X 299 300 Open Open 301 Open Open

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