Text

2010/09/10 Watts Bar 2 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)
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1 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 JustinC.PooleProjectManagerNRR/DORL/LPWBU.S.NuclearRegulatoryCommission(301)4152048email: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 TVA's 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. Let's try to fill these cells after we receive TVA's 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 2 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.

SamirDarbaliElectronicsEngineerNRR/DE/EICBRoom:O9D113014151360 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 001 EICB (Carte) 11/19/2009 The Watts Bar Nuclear Plant FSAR red-line for Unit 2 (Agency wide Documents Access and Management System Accession Number ML080770366) lists changes to the Unit 1 FSAR and depicts how Chapter 7 of the Unit 2 FSAR will appear at fuel load. Have additional changes been made to Chapter 7 of the Unit 2 FSAR beyond those indicated in ML080770366? Which of the changes identified correspond to digital instrumentation and controls (I&C) components and systems that have not been previously reviewed and approved by the NRC? 12/15/2009 Presentation Slides This item was partially addressed during the December 15, 2009 meeting.

TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 1 on Page 1 of 15): TVA responded to this request for additional Information.

Closed Date: 3/15/2010 RAI response received. Closed November 19, 2010 ML093230343 RAI 1 3/12/2010 NNC 11/19/09: The FSAR contains mostly description of the function that the various TVA systems must perform. Therefore this question was asked to determine how the systems have been changed.

NNC 4/15/10: The response addresses many systems and should be read by all EICB reviewers.

002 EICB (Carte) 11/19/2009 Are there I&C components and systems that have changed to a new or different digital technology without the change being reflected in the FSAR markup? Are there any not-redlined I&C components and systems that have been changed or replaced by digital base technology since Unit 1 was approved? 12/15/2009 Presentation Slides This item was partially addressed during the December 15, 2009 meeting. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 2 on Page 2 of 15): TVA responded to this request for additional Information.

Closed Date: 3/15/2010 RAI response received. Closed November 19, 2010 ML093230343 RAI 2 3/12/2010 NNC 11/19/09: The FSAR contains mostly description of the function that the various TVA systems must perform. Therefore this question was asked to determine how the systems have been changed. NNC 4/15/10: The response addresses many systems and should be read by all EICB reviewers.

003 EICB (Carte) 11/19/2009 Because a digital I&C platform can be configured and programmed for different applications, the review process can be divided between a review of the platform and a review of the application. For planning and scheduling reasons, it is important to know beforehand which platform has been used in each digital component and system. What is the base platform of each unreviewed digital I&C component and system (e.g., Common Q)? 12/15/2009 Presentation Slides This item was partially addressed during the December 15, 2009 meeting. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 3 on Page 2 of 15): TVA responded to this request for additional Information.

Closed Date: 3/15/2010 RAI response received. Closed November 19, 2010 ML093230343 RAI 3 3/12/2010 NNC 11/19/09: The FSAR contains mostly description of the function that the various TVA systems must perform. Therefore this question was asked to determine how the systems have been changed. NNC 4/15/10: The response addresses many systems and should be read by all EICB reviewers.

004 EICB (Carte) 11/19/2009

Please identify the information that will be submitted for each unreviewed digital I&C system and component and the associated docketing schedule. Responder: Webb 1/13/10 Public Meeting

TVA identified a schedule for docketing some Post Accident Monitoring System (PAMS) documentation, and the new setpoint methodology. No other documentation was discussed.

Add: By letter dated June 30, 2010, TVA docketed WNA-LI-00058-WBT-P &-NP, "PAMS Licensing Technical Report." WNA-LI-00058-WBT-P Section 4.11 addressed CCF and BTP 7-19.

TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 4 on Page 3 of 15): TVA responded to this request for additional Information Foxboro I/A Segmentation Analysis Calculation DCSSEGMENT, Rev. 0 submitted on TVA letter dated August 11, 2010.

Data Storm Testing

The procurement specification (Attachment 23) for the Foxboro I/A sytem section 3.11.2 requires the following as part of the Factory Acceptance Test:

"Tests shall include realistic message traffic on all communications networks and subnetworks. In addition, all digital interfaces to external environments such as plant computer interface shall Open Date: 3/15/2010 Re sponsibility:

NRC (All) and TVA (Hilmes)

TVA to address the question of how a Foxboro IA common mode or complete failure impacts the plant accident analysis as described in Chapter 15 of the FSAR. (Demonstrate segments are independent and how a common mode or complete failure is prevented by power supply design and segmentation.)

NNC 8/19/10: The justification for not performing and D3 analysis contained in the CQ PAMS Licensing Technical Report is not acceptable. TVA to docket a D3 analysis for the CQ PAMS. This will be responded to in Item 64.

NNC 8/25/10: The segmentation analysis has been read. Please explain why it is believed that faliure will not propagate over Open TVA to docket a D3 analysis for the Common Q PAMS.

NNC 8/19/10: TVA segmentation analysis has been received - NRC to review. November 19, 2010 ML093230343 RAI 4 January 13, 2010 March 12, 2010 June 30, 2010 August 11, 2010 NNC 11/19/09: LIC-110 Rev. 1 Section 6.2.2 states: "Design features and administrative programs that are unique to Unit 2 should then be reviewed in accordance with current staff positions-.TVA will supply a description of the changes implemented at Unit 1 but have not been reviewed for Unit 2 by the NRC technical staff...TVA will also provide the applicable portion of the FSAR

and the proposed TSs...In addition, the staff should review items that are identical for WBN Units 1 and 2 that have not previously been reviewed and approved by the NRC staff. These items are changes in the design and licensing basis for WBN Unit 1 that TVA has implemented without NRC prior approval under the 10 CFR 50.59 process." NNC 4/15/10: The response addresses many systems and should be read by all EICB reviewers..

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments be tested to withstand broadcast storm events without degradation in the control systems performance. Also, the control system shall be tested for broadcast storm events resulting from component failures on internal communication networks without degradation in the control systems performance."

the peer-to-peer network.

Looking for an architectural description of the network interconnections similar to the ICS overview, identification of 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 7.1.3.1 EICB (Garg) December 11, 2009 By letter date February 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML080770366) TVA provided a "red-lined" version of the FSAR for WBN Unit 2. The purpose of this FSAR "red-line" version was to depict how the Unit 2 FSAR will appear at fuel load. This letter identified "significant FSAR changes" and provided a "X-REF" number for each.

Change 7.3-1 refers to the following two Summary Reports: TVA Letter, P. L. Pace to NRC, dated February.9, 1998, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59(b)(2), Changes, Tests and Experiments Summary Report TVA Letter, P. L. Pace to NRC, dated September 30, 2005, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59, Changes, Tests and Experiments Summary Report" Please submit the 50.59 Evaluations for each of these Summary Reports and identify which parts are relevant to the Unit 2 Setpoint Methodology. Responder: Craig/Webb TVA Letter Dated February 5, 2010: TVA provided the Unit 2 setpoint methodology (WCAP-177044-P Revision 0 - dated December).

TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 5 on Page 5 of 15): TVA responded to this request for additional Information This item is addressed as follows:

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.

TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February 2, 2010. Closed Date: 3/15/2010 Responsibility: NRC (Garg) and TVA (Hilmes and Crouch)

RAI response received. This item is closed as this is covered under item 154 later on.

This item requires futher discussion between TVA and the staff concening the setpoint methodology employed for WBN2. See Item 8. Closed FSAR Amd 100 ML093431118, RAI 5 NNC 4/15/10: Related to setpoints and SE Section 7.1.3.1.

006 EICB (Garg) December 11, 2009 (ML093431118, RAI 6) Amendment 95 of the FSAR, Chapter 7.3, shows that change 7.3-1 consists of updating a reference from revision 5 to revision 7 and making it applicable to Unit 1 only, while adding a new reference, applicable only to Unit

2.

Reagan, J. R., "Westinghouse Setpoint Methodology for Protection Systems, Watts Bar Units 1 and 2, Eagle 21 Version," WCAP-12096 Rev. 7, (Westinghouse Proprietary Class 2). Unit 1 Only

WCAP "Westinghouse Setpoint Methodology for Protection System, Watts Bar Unit 2, Eagle 21 Version, WCAP-17044-P. Unit 2 Only.

Please provide both setpoint methodology documents identified above.

By letter dated February 5, 2010: TVA provided the Unit 2 setpoint methodology (WCAP-177044-P Revision 0 - dated December 2009).

TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 6 on Page 7 of 15): TVA responded to this request for additional Information.

a. TVA to docket Rev. 8 and identify that Rev. 8 is the current revision for Unit 1. TVA to identify any NRC approval of Rev. 8.

In accordance with item 2, below, there is no change to the methodology, therefore revision 8 is not included in this response.

Westinghouse letter WAT-D-10502 (Attachment 1) describes the two changes to WCAP-12096 Revision. 8. The first change addresses the containment sump level transmitter replacement.

This change was submitted under 50.59 summary Open Date: 2/16/2010

The Westinghouse Setpoint methodology document (WCAP-17044-P Revision 0) identifies that the intermediate and source range calculations were performed by TVA (2-NMD-092-0131). Please provide the intermediate and source range calculations performed by TVA (2-NMD-092-0131).

The Westinghouse Setpoint methodology document (WCAP-17044-P Revision 0) identifies that the undervoltage and underfrequency calculations were performed by TVA (2-27-Open TVA to reference TI-28 for as found and as left value.

Also provide the reference to FSAR Section 7.1 for the setpoint methodology. NNC: WCAP-12096 Rev. 7 (ML073460281) is in ADAMS.

NNC: WCAP-12096 Rev. 8 is the current revision for Unit 1.

NNC 4/15/10: Hukam, please update this open item as appropriate.

TVA to docket Rev. 8 and identify that Rev. 8 is the current revision for Unit 1. TVA to identify any NRC approval

of Rev. 8.

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.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments report (ML073460444, Page 77). The second change is to delete the power range negative flux rate trip. This item was submitted as a Technical Specification change (ML073201052). The Technical Specification change was subsequently approved.

The current revision of Unit 1 WCAP-12096 is 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.

068-0031). Please provide the undervoltage and underfrequency calculations performed by TVA (2-27-068-0031).

Work with Item 7 for WCAP-12906 issues.

007 EICB (Garg) December 11, 2009 (ML093431118, RAI 7)

The setpoint methodology has been reviewed and approved by the NRC staff in Section 7.1.3.1 of NUREG-0847 (ML072060490), NUREG-0847 Supplement No.4 (ML072060524), and NUREG-0847 Supplement No. 15 (ML072060488).

Please describe all changes from the methodology that has been reviewed and approved by the staff. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 7 on Page 7 of 15): TVA responded to this request for additional Information.

a. TVA will submit WCAP-12096, Rev. 8 if there is a change to the methodology.

No change in methodology, therefore WCAP-12906, Revision 8 is not submitted.

b. TVA will supply the 50.59 letter for Rev. 8

Westinghouse letter WAT-D-10502 (Attachment 1) describes the two changes to WCAP-12096 Revision. 8. The first change addresses the containment sump level transmitter replacement. This change was submitted under 50.59 summary report (ML073460444, Page 77). The second change is to delete the power range negative flux rate trip. This item was submitted and approved as a Technical Specification change (ML073201052).

c. TVA to locate transmittal letter that submitted Rev.

7.

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. Open Date: 1/13/2010 RAI response received. NRC to review response.

TVA will submit WCAP-12096, Rev. 8 if there is a change to the methodology.

TVA will supply the 50.59 letter for Rev. 8

TVA to locate transmittal letter that submitted Rev. 7.

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

Work with Item 6 for WCAP-12906 issues. Open Same as Item 6 above. NNC 4/15/10: Related to setpoints and SE Section 7.1.3.1.

NNC 4/15/10: Hukam, please update this open item as appropriate.

TVA to provide Rev. 8 of the Unit 1 document (which is the current one) if there is a change in methodology and identify how the Unit 2 document differs from it.

008 7.3 (GDecember 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments There are several staff positions that provide guidance on setpoint methodology (e.g., Reg Guide 1.105, BTP 7-12, RIS-2006-17 and TSTF-493 Rev. 4). Please identify how the Unit 2 setpoint methodology addresses staff guidance. No. 8 on Page 7 of 15): TVA responded to this request for additional Information This item is addressed as follows:

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. FSAR Amd 100.

Closed as it will be covered under item 154 RAI 8 009 EICB (Darbali) December 11, 2009 Change 7.3-2, identified in Watts Bar Nuclear Plant FSAR red-line for Unit 2 (ADAMS Accession Number ML080770366), refers to the following Summary Report: TVA Letter, P. L. Pace to NRC, dated September 20, 2002, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59, Changes, Tests and Experiments Summary Report" Please provide the 50.59 Evaluation summarized in this Summary Report. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 9 on Page 8 of 15): TVA responded to this request for additional Information Closed Date: 3/15/2010 Responsibility: NRC (Darbali) 50.59 evaluation was submitted in the RAI response. NRC to review. Closed ML093431118, RAI 9 NNC 4/15/10: Related SE Section 7.3.

010 EICB (Darbali) December 11, 2009 (ML093431118, RAI 10)

The original SER on Watts Bar (NUREG-0847) documents that the scope of the review of FSAR Section 7.3, "Engineered Safety Features Actuations System," included: "included single-line, function logic and schematic diagrams, and descriptive information for the ESFAS and those auxiliary supporting systems that are essential to the operation of either the ESFAS or the ESF systems. The review included the applicant's design 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 system s 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. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 10 on Page 8 of 15): TVA responded to this request for additional Information.

TVA Letter (ML073550386) dated FEB 26 1992:

docketed WCAP-12374 Rev. 1 (ML080500664). Open Date: 3/15/2010 NRC evaluating TVA response.

NRC to discuss document requirements and provide additional information to resolve this item. Open NRC Review NNC 4/15/10: Related SE Section 7.3.

011 EICB (Darbali) December 11, 2009 (ML093431118, RAI 11)

NUREG-0847 Supplement No. 2 Section 7.3.2 includes an evaluation of a change in containment sump level measurement. Provide information to demonstrate that Unit 2 implements the containment sump level indication as described and evaluated in NUREG-0847 Supplement No. 2, Section 7.3.2, for Unit 1.

TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 11 on Page 13 of 15): TVA responded to this request for additional Information Closed Date: 3/15/2010 Responsibility: NRC (Darbali)

Requested information was submitted in the RAI response. Closed NNC 4/15/10: Related SE Section 7.3.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 012 EICB (Darbali) December 11, 2009 (ML093431118, RAI 12)

The original SER on Watts Bar (NUREG-0847) documents that the scope of the review of FSAR Section 7.4, "Systems Required for Safe Shutdown," included single-line and schematic diagrams: "The scope of the review of the systems required for safe shutdown included the single-line and schematic diagrams and the descriptive information for these systems and for the auxiliary systems essential for their operation." Please provide the single-line and schematic diagrams for the systems required for safe shutdown that are applicable to Unit 2, and include a description of all changes since these diagrams were reviewed and approved by the NRC staff. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 12 on Page 13 of 15): TVA responded to this request for additional Information A revised response was included in the 7/30 letter that provides the requested information.

Closed Date: 3/15/2010 TVA provided the following:

1. Description of what is different from Unit 1

2. Road map between functions listed in 7.4 and the FSAR section that describes the equipment that performs the function. Item Closed. Closed NNC 4/15/10: Related SE Section 7.4.

013 EICB (Garg) December 11, 2009 (ML093431118, RAI 13)

Chapter 7 and Chapter 16 of Amendment 95 to the FSAR do not include any setpoint values. Please describe how and when setpoint values (e.g., TS allowable values) will be provided for Unit 2.

Please describe the information that will be provided to justify the acceptability of these values. TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 13 on Page 14 of 15): TVA responded to this request for additional Information Closed Date: 3/15/2010 RAI response received. Westinghouse is completing the setpoint calculations which will be completed by May 11, 2011. NRC to review response. Closed This item is closed for chapter 7. NRC will review T.S. under different chapter. TS have been docketed.

NNC 4/15/10: Related to setpoints and SE Section 7.1.3.1.

NNC 4/15/10: Hukam, please update this open item as appropriate.

Related to SE Section 7.1.3.1.

014 EICB (Carte) December 22, 2009 (ML093560019, item 1)

Provide the justification for any hardware and software changes that have been made since the previous U.S. Nuclear Regulatory Commission (NRC) staff review for Eagle 21 and other platforms Date: 4/27/10 Responder: TVA By letter dated April 27, 2010: TVA responded to this request for information (Enclosure, Item No. 1) stated: "In discussion with the staff, TVA's understanding is that the focus of this question is the Eagle 21 system. Please refer to Reference 2 [TVA Letter Dated March 12, 2010], Question 10, and TVA letter to NRC dated August 25, 2008, 'Watts Bar Nuclear Plant (WBN) - Unit 2 - Westinghouse Eagle 21 Process Protection System, Response to NRC I&C Branch request for additional information' (Reference 3 [TVA letter dated August 25, 2008]) for the discussion of changes to the Eagle 21 system."

A listing of changes to other platforms was provided in TVA letter dated April 27, 2010, Enclosure 1, items 21 and 23.

Closed Date: 4/27/10 Responsibility: NRC (Carte)

NNC: I do not recall saying that the NRC is not interested in changes in other platforms. Please provide a description of changes to other platforms (e.g., SSPS). For Eagle 21, this response points to Open Item No. 10.

Response understood. Additioanl material will be requested separately to understand the systems described. Closed NNC 4/30/10: Related to Eagle 21; therefore Garg is responsible.

015 EICB (Garg) December 22, 2009 (ML093560019, item 2)

Verify that the refurbishment of the power range nuclear instrumentation drawers resulted in only like-for-like replacements.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 2).

Closed Date: 4/27/10 Responsibility: NRC (Garg)

Response acceptable. Close Closed 016 EICB (Carte) December 22, 2009 (ML093560019, item 3)

Identify the precedents in license amendment requests (LARs), if any, for source range monitors or intermediate range monitors.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 3).

Closed Date: 4/27/10 Responsibility: NRC (Garg)

Acceptable. Close Closed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 017 EICB (Darbali) December 22, 2009 (ML093560019, item 4)

Identify precedents in LARs, if any, for the solid state protection system. Also, identify any hardware deviation from the precedent. Date: 4/27/10 By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 4). Open Date: 4/27/10

Awaiting NRC evaluation of response. Open NRC Review 018 EICB (Garg) December 22, 2009 (ML093560019, item 5)

Identify any changes made to any instrumentation and control (I&C) system based on prior knowledge of failures.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 5).

Closed Date: 4/27/10 Responsibility: NRC (Garg)

Acceptable. Close Closed 019 EICB (Garg) December 22, 2009 (ML093560019, item 6)

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

Response unacceptable. Should discuss all changes.

Open NRC Review 020 EICB (Garg) December 22, 2009 (ML093560019, item 7)

Provide environmental qualification information pursuant to Section 50.49 of Title 10 of the Code of Federal Regulations (10 CFR) for safety-related actuation transmitters.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 7).

Closed Date: 4/27/10 Responsibility: NRC (EEEB)

Garg to coordinate with Weibi to ensure EEEB takes responsibility for this one. Closed NNC 4/30/10: SRP Section 7.0 states: "The organization responsible for the review of environmental qualification reviews the environmental qualification of I&C equipment. The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment." 021 EICB (Garg) December 22, 2009 (ML093560019, item 8)

For the Foxboro Spec 200 platform, identify any changes in hardware from the precedent systems. Provide the design report and the equipment qualification information. Date: 5/25/10 No vendor system description is available for the Foxboro Spec 200 system. The hardware description and qualification documents are provided on a component level basis. A TVA generated system description is provided to assist the reviewer. The hardware differences from the unit 1 systems are provided in the loop and card comparison documents. As agreed with the reviewer, the component level documents are not required to be submitted at this time, but may be required later based on the review of attached documents. The following TVA generated documents are provided (Attachment 1):

1. Analog loop comparison

2. Analog card comparison

3. Analog system description Open Date: 5/24/10

The understanding reached in the meeting on April 14, 2010, was that TVA should identify any changes, or state under oath and affirmation that there were no changes. If there were no changes, then the NRC would confirm by inspection.

A revised response was requested at the 5/24/10 public meeting. Open NRC Review Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 022 EICB (Darbali) December 22, 2009 (ML093560019, item 9)

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

The control function of the Auxiliary Feedwater (AFW) Flow for Steam Generator Level is the same as Unit 1. The controllers and signal modifiers/conditioners are Foxboro SPEC 200 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 Fo xboro 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 Open Date: 4/27/10 TVA should confirm if Woodward Governer is the only change.

See Item 285 for follow up question. Open NRC Review Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) December 22, 2009 (ML093560019, item 10)

Provide environmental qualification (10 CFR 50.49) information for safety-related control transmitters and complete the deviation section of the table.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 10).

Closed Date: 12/22/09 Responsibility: NRC (EEEB)

Garg to coordinate with Weibi to ensure EEEB takes responsibility for this one. Closed NNC 4/30/10: SRP Section 7.0 states: "The organization responsible for the review of environmental qualification reviews the environmental qualification of I&C equipment. The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment." 024 EICB (Carte) December 22, 2009 (ML093560019, item 11)

Provide a schedule by the January 13, 2010, meeting for providing information in accordance with I&C Interim Staff Guidance (ISG) 6. During the January 13, 2010 meeting, TVA presented a schedule for completing various documents for the PAMS system. This schedule did not support TVA's desired schedule. TVA was so informed and said they would work on improving the schedule. TVA said that the setpoint methodology would be provided shortly. No other systems of documentation was discussed.

By letter dated February 5, 2010 (see enclosure 1), TVA provided a list of documents and associated availability for PAMS.

By letter dated April 27, 2010 TVA responded to this 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."

Closed Date: 4/27/10 The explanations provided by TVA (that certain information is not required) are unacceptable.

NNC 8/18/10: The TVA agreement in the Comments column conflicts with the TVA responses to other open items where TVA states that information is available for audit.Closed Closed to Item 43

NNC 4/30/10: Carte to address response with respect to PAMS and Darbali to address response with respect to RM1000.

TVA has agreed to submit the requested information on the docket.

025 EICB (Singh) December 22, 2009 (ML093560019, item 12)

For the containment radiation high radiation monitor, verify that the information provided by TVA is consistent with the information provided with the previously-approved license Date: 4/27/10 By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 12). Open Date: 07/28/2010

NRC review in progress. Open NRC Review FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) December 22, 2009 (ML093560019, item 13)

Provide environmental qualification (10 CFR 50.49) information for safety-related monitoring transmitters.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 13).

Closed Date: 12/22/09 Responsibility: NRC (EEEB)

Garg to coordinate with Weibi to ensure EEEB takes responsibility for this one. Closed NNC 4/30/10: SRP Section 7.0 states: "The organization responsible for the review of environmental qualification reviews the environmental qualification of I&C equipment. The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment." 027 EICB (Carte) December 22, 2009 (ML093560019, item 14)

For Foxboro I/A provide information regarding safety/non-safety-related interaction, common cause failures, and communication with safety related equipment in accordance with ISG 4.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 14): "There is no digital communications or interactions between Foxboro Intelligent Automation (IA) and any Safety-related system." Closed Date: 4/27/10 Responsibility: NRC (Carte)

Closed 028 EICB (Garg) December 22, 2009 (ML093560019, item 15)

For the turbine control AEH system, verify that the refurbishment results in a like-for-like replacement. Responder: Mark Scansen Date: 4/27/10 By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 15).

The requested 50.59 is included in Attachment __. Open Provide 50.59 evaluation. Response acceptable. Open Provide 50.59 029 EICB (Carte) December 22, 2009 (ML093560019, item 16)

For the rod control system, verify that the refurbishment results in a like-for-like replacement.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 (ML101230248) TVA 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.

Closed Date: 4/27/10 Responsibility: NRC (Carte)

Closed 030 EICB (Garg) December 22, 2009 (ML093560019, item 17)

Regarding the refurbishment of I&C equipment, identify any component digital upgrades and, if so, provide the supporting design information. Responder: Clark Date: 4/27/10

By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 17).

There are no other I&C upgrades which contain an imbedded digital processor. Open Date: 4/27/10

Does not state if there are no other upgrade which contain imbedded digital processor.

Revised response acceptable. Open 031 EICB (Carte) December 22, 2009 (ML093560019, item 18)

For the rod position indication system (CERPI), provide information in accordance with ISG 4. Need to consider cyber-security issues.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 18).

Closed Date: 4/27/10 Responsibility: NRC (Carte)

Response acceptable. Closed CERPI is non-safety related.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 032 EICB (Carte) December 22, 2009 (ML093560019, item 19)

For the process computer, need to consider cyber security issues and emergency response data system needs.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 19).

Closed Date: 4/27/10 Responsibility: NRC (Carte)

EICB will no longer consider cyber issues.

Closed 033 EICB (Carte) December 22, 2009 (ML093560019, item 20)

For the loose parts monitoring system, provide information regarding interactions with safety related equipment.

Date: 4/27/10 Responder: TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 20): Loose parts is not connected to any other system.

Closed Date: 4/27/10 Responsibility: NRC (Carte)

TVA stated that there are no interactions. Closed The loose parts monitoring system is not connected to any other system.

034 EICB (Garg) 2/4/2010 In the December 15, 2009 public meeting, TVA listed the significant changes made since the Watts Bar Unit 1 Licensing (see below). For each of the following significant changes:

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

2) If it's 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? Responder: TVA

By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 21).

Remove all references to Elbow Tap Methodology from Unit 2 Licensing Bases. Open Awaiting NRC evaluation of response. Open NRC review 034.1 EICB (Garg/Singh) Chapter 7.1 - Introduction Reactor Coolant System Flow Rate Measurement Design Basis Analysis Parameters Loose Parts Monitoring OpenOpen 034.2 EICB (Garg) Chapter 7.2 - Reactor Trip System 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 Open Open 034.3 EICB (Darbali) Chapter 7.3 - ESFAS Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump

Open Open 034.4 EICB (Carte) Chapter 7.5 - Instrumentation Systems Important to Safety Plant Process Computer Replacement Containment Sump Level Transmitter Replacement Safety Injection Systems Cold Leg Accumulator Level Measurement System Common Q/PAMs Open Open 034.5 B (Gar g/Sin Chapter 7.6 - All Other Systems Required for Safety Plant Process Computer Replacement Loose Parts Monitoring System OpenOpen Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 034.6 EICB (Garg/Darbali) Chapter 7.7 Control Systems 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)

OpenOpen 035 EICB (Singh) 2/18/2010 Please provide a system description of the Digital Metal Impact Monitoring System that contains sufficient detail to support a review of this system using current staff positions. Responder: Clark TVA Letter dated March 12, 2010 Enclosure 1, item 4 responded to this request for information.

The attached non-proprietary system description was developed from proprietary Westinghouse Watts Bar Unit 2 DMIMS-DX Operations and Maintenance Manual, 1TS3176 Rev.0 (Reference 1).

Westinghouse approved this non-proprietary response via letter WBT-D-____ dated August , 2010. The system description is contained in . Open Description provide is not of sufficient detail to allow a regulatory determination. TVA to send the proprietary information

for NRC review. At the 9-2 meeting G. Singh stated the system descriptionn provided was acceptable and the proprietary information was not required at this time. Open TVA to docket the information including proproietary information for LPMS. LIC-110 Section 6.2.2 states: "Design features and administrative programs that are unique to Unit 2 should be reviewed in accordance with the current staff positions

." Unit 2 FSAR Section 7.6.7, "Loose Part Monitoring (LPMS) system Description," describes a system design that is unique to Unit 2.

036 EICB (Carte) February 18, 2010 Please provide a system description of the Post Accident Monitoring System that contains sufficient detail to support a review of this system using current staff positions.

Date: 5/25/10 Responder: Clark In previous letters TVA has provided the Common Q documents that address this item:

Closed Date: 2/18/2010 Responsibility: TVA Closed FSAR Section 7.5.1, SE Section 7.5.2 NNC: Unit 2 FSAR Section 7.5.1, "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 EICB (Marcus) 2/18/2010

Is the plant computer a safety-related display system? Responder: Clark Date: 5/25/10

As identified in TVA letter dated March 12, 2010, Enclosure 1, item 2, the plant computer system is non-safety related.

FSAR section 7.5 describes both safety and non-safety related devices and systems. FSAR section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated September 1, 2010. Open August 19, 2010 - TVA to submit markup of FSAR Amendment 100. Open NRC review FSAR Section 7.5, "Instrumentation System Important to Safety," consists of two major subsections: 7.5.1, "Post Accident Monitoring Instrumentation (PAM)," and 7.5.2, "Plant Computer System."

Regulatory Guide 1.70, "Standard format and content of Safety Analysis Reports for Nuclear Power Plants," 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 2/18/2010

Please provide a description of the interfaces between: (1) the Safety Parameter Display System and (2) the Technical Support Center and Nuclear Data Links with the plant control and safety systems. This Description should contain sufficient detail to support a review of these interfaces using current staff positions. Responder: Clark Date: 5/25/10 FSAR section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated September 1, 2010.. Open August 19, 2010 - TVA to submit markup of FSAR Amendment 100. Open NRC review The slides presented at the December 15, 2010 meeting (ML093520967) indicate that the plant process computer has been replaced.

039 EICB (Garg) January 13, 2010 Please describe the change to the calculation of the estimated average hot leg temperature (see FSAR Section 7.2.1.1.4, page 7.2-14 Version WBNP-96) in sufficient detail to support a review of this system using current staff positions.

Responder: Clark Date: 5/25/10 Refer to revised equations in FSAR amendment 98.

Closed Date: 1/13/2010 Responsibility: TVA NRC staff will review Closed The equation for the calculation of the estimated average hot leg temperature on page 7.2-13 of Revision WBNP-96 of the Unit 2 FSAR is different than the calculation of the average hot leg temperature shown at the top of page 7.2-14 of version WBNP-1 of the UNIT 1 FSAR.

040 EICB (Garg) January 13, 2010 Please describe the change to the calculation of the power fraction (see FSAR Section 7.2.1.1.4, page 7.2-13 Version WBNP-96) in sufficient detail to support a review of this system using current staff positions.

Responder: Clark Date: 5/25/10 Refer to revised equations in FSAR amendment 98.

Closed Date: 1/13/2010 Responsibility: TVA NRC staff will review Closed The equation for the calculation of the power fraction on page 7.2-14 of Revision WBNP-96 of the Unit 2 FSAR is different than the calculation of the power fraction shown at the top of page 7.2-14 of version WBNP-1 of the UNIT 1 FSAR.

041 EICB (Carte) 2/19/2010 Please provide the following Westinghouse documents: (1) WNA-DS-01617-WBT Re

v. 1, "PAMS System Requirements Specification" (2) WNA-DS-01667-WBT Rev. 0, "PAMS System Design Specification" (3) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g" Please provide the following Westinghouse documents or pointers to where the material was reviewed and approved in the CQ TR or SPM: (4) WNA-PT-00058-GEN Rev. 0, "Testing Process for Common Q Safety systems" (5) WNA-TP-00357-GEN Rev. 4, "Element Software Test Procedure" Responder: WEC Items (1) and (2) were docketed by TVA letter dated April 8, 2010.

Items (3), (4) and (5) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g," WNA-PT-00058-GEN Rev. 0, "Testing Process for Common Q Safety systems" and WNA-TP-00357-GEN Rev. 4, "Element Software Test Procedure" are available for audit at the Westinghouse Rockville office (Westinghouse letter WBT-D-1526, Reference 6).

3 will be addressed during September 20 and 21 audit. 4 Westinghouse will develop a WBN2 Specific Test Plan to compensate for WNA-PT-00058-GEN. TBD 5 WNA-TP-00357-GEN superseded by the SPM compliance matrix in the Licensing Technical Report Open The SysRS and SRS incorporate requirements from many other documents by reference.

NNC 8/25/10: (3) An earlier version of this report was docketed for the Common Q topical report; therefore, there should be no problem to docket this version. (4) Per ML091560352, the testing process document does not address the test plan requirements of the SPM. Please provide a test plan that implements the requirements of

the SPM. Open TVA to docket information

indetified in ISG6.

TVA to provide date when information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2

1.1 Software

V&V report (04508005). The non-proprietary version and 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. Software V&V Report.

057 EICB (Singh) 4/19/2010 Please describe the ability to change the software of the RM-1000 at site, including all required equipment and administrative controls (e.g., temporary digital connections). Responder: TVA I&C Staff Date: 5/25/10 Firmware/software changes are done by connecting a laptop to a port on the front of the RM-1000 and placing the Operate/Calibrate switch in the Calibrate position. The first physical barrier to access is the location of the RM-1000 in the main control room which has limited access. The RM-1000 Operate/Calibrate switch is located behind the hinged front panel. The front panel must be opened (held closed by two thumbscrews) to access the switch. This provides a physical barrier to inadvertent switch operation. The system malfunction alarm is visible locally and will annunciate on the control board when the switch is in the Calibrate position.

Administrative control of software/firmware updates is in accordance with TVA Standard Specification SS-E18.15.01, Software Requirements for Real-Time Data Acquisition and Control Computer Systems, and TVA procedures SPP-9.3, Plant Modifications and Engineering Change Control, and SPP-2.6, Computer Softwar e Control. Approved changes to software/firmware are implemented utilizing the TVA work order process.

(1) A laptop is not used to calibrate the monitor. All TVA in-house activities (calibration, alarm setpoint adjustment, etc.) are performed using the touchpad on the monitor. An external computer (laptop etc.) is only used to perform software or firmware updates.

TVA does not perform software or firmware updates using in-house resources therefore no TVA computer 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 Open Requested information provided. NRC to review.

Further Information Requested: Please confirm that the laptop is secure and access to this laptop is commensurate with the access to the equipment for which it will be used. Is the laptop dedicated for calibration of radiation monitors? If the laptop is used for more than one application then please describe the equipment for which the laptop may be used. In addition please explain how software security is assured and that only the software intended for the specific application is used. Is the connection to the radiation monitors made via a special cable/connectors? Please confirm that the RS-232 communication port of the radiation monitors will only be used for calibration purposes.

Also please confirm that the radiation monitor will not be in operation during the calibration mode. In addition please confirm that password protection is provided for logging on to the laptop prior to start of calibration.Open Response path acceptable. TVA

to submit the information for docketing. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Darbali) April 19, 2010 Please describe all digital communications used in the installed configuration.

Date: 5/25/10 Responder: Slifer There are no digital communications between the RM-1000 and any other plant system or component.

Closed Date: 4/19/2010 Responsibility: NRC Requested information provided.

NRC to review. Closed See ML101940236, Encl 1, Item 13 FSAR Section 7.5 Instrumentation Systems Important To Safety - SE Section 7.5.0 059 EICB (Darbali) April 19, 2010 Previously TVA provided the "RM-1000 Digital Radiation Processor Technical Manual," Document No. 04508100-1TM Revision C dated October 2003. The "RM-1000 Version 1.2 Software Verification and Validation Report," Document No. 04508006 Rev. A is dated April 2008. (a) What software version does the technical manual address? (b) When was Version 1.2 implemented?

Date: Responder: Slifer (a) The technical manual is applicable to versions 1.1 and 1.2 of the software.

(b) Version 1.2 was implemented April 1, 2008 Closed Date: 4/19/2010 Responsibility: NRC Requested information provided.

NRC to review. Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 060 EICB (Carte) April 19, 2010 The PAMS System Requirements Specification (SysRS) references RG 1.97 Rev. 3 where the FSAR References Rev. 2. Please explain.

Date: 5/25/10 Responder: Clark Duplicate of Item 47 Closed Date: 4/19/2010 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 061 EICB (Carte) April 19, 2010 Reference 16 of the PAMS System Requirements Specification (SysRS) is the Unit 1 precautions Limitations and Setpoints document. When and how will the transition to the unit 2 document be made.

Date: 5/25/10 Responder: Clark Duplicate of Item 48.

Closed Date: 4/19/2010 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 062 EICB (Carte) April 19, 2010 Please provide 00000-ICE-30156 Rev. 6. The PAMS SysRS incorporates sections of this document by reference.

Date: 5/25/10 Responder: Clark Duplicate of Item 49 Closed Date: 4/19/2010 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 063 EICB (Carte) April 19, 2010 How should the "shall" statements outside of the bracketed requirements be interpreted?

Date: 5/25/10 Responder: Clark Duplicate of Item 50 Closed Date: 4/19/2010 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 064 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the D3 Analysis was April 2, 2010. Responder: Webb Date: 4/8/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the D3 Analysis was April 2, 2010. Open TVA provided roughly a page of description as to why a D3 analysis is not required. The Open TVA to provide requested

information. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments NRC requires additional information to determine the acceptability of this response.

TVA to provide date when

information will be docketed.

065 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the FMEA was August 31, 2010. Responder: WEC Date: 5/25/10

WEC to provide the P version ASAP. Open Awaiting for document to be docketed by TVA. Open Due 9/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 066 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 PAMS Software Design Description (two documents, one for flat panel display and one for AC160)" was March 31, 2010. Responder: WEC Date: 5/25/10 Per Westinghouse letter WBT-D-1961 (Reference 8),

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

WNA-SD-00250-WBT Rev. 0 (AC160) was submitted on TVA letter to the NRC dated August __,

2010 (Reference 7).

WNA-SD-00248-WBT, Rev. 0 (FPDS) was submitted on TVA letter to the NRC dated SEPT 2, 2010 ( Reference 8 ). Open Regulations require that the NRC review be based on docketed material. The SRP directs that reviewer to review the Software Design Specification (softimes called an

SDD). NNC 8/25/10: By letter dated august 20, 2010, one (Reference 7) SDD has been provided. Open TVA to provide remaining information.

NRC to review information provided. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 067 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Commercial Grade Dedication Instructions for AI687, AI688, Upgraded PC node box and flat panels." was September 28, 2010. Responder: WEC Date: 5/25/10 The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix submitted in response to Item 43:

a. AI687, AI688 - Scheduled for September 28, 2010

b. Upgraded PC node box and flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), 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 Open Regulations require that the NRC review be based on docketed material. Open TVA to provide requested information.

TVA to provide date when

information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.0 & 7.5.2 068 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Summary Report on acceptance of AI687, AI688, Upgraded PC node box, flat panels, and power supplies." was September 28, 2010. Responder: WEC Date: 5/25/10 The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix submitted in response to Item 43:

a. AI687, AI688 - Scheduled for September 28, 2010

b. Upgraded PC node box - Per Westinghouse letter WBT-D-2024 (Reference 7), th is item is available for audit at the Westinghouse Rockville office.

c. Flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), th is 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 Open Awaiting for document to be docketed by TVA. Open TVA to provide requested information.

TVA to provide date when information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 069 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 PAMS Specific FAT Report" was October 2010. Responder: WEC Date: 5/25/10 Open Awaiting for document to be docketed by TVA. Open Due 11/30/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 070 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Conc ept and Definition Phase V&V Report" was March 31, 2010. Responder: WEC Date: 5/25/10

Per Westinghouse letter WBT-D-1961, (Reference 8) this document is available for audit at the Westinghouse Rockville office.

WNA-VR- 00283-WBT, Rev 0 was submitted on TVA letter to the NRC dated August __, 2010 (Reference 7). V&V did not address the RTM and did not summarize anomilies. To be addressed at the 9/15 public meeting at NRC. Open Regulations require that the NRC review be based on docketed material. Awaiting for document to be docketed by TVA.

NNC 8/25/10: Requirements Phase SVVR provided by TVA letter dated 8/20/10. Open NRC to review information provided FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 071 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Design Phase V&V Report" was July 30, 2010. Responder: Clark Date: 5/25/10

Verify schedule dates for the next submittal of this matrix against update WEC schedule. Open Awaiting for document to be docketed by TVA. Open Due 9/23/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 072 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Implementation Phase V&V Report" was September 30, 2010. Responder: Clark Date: 5/25/10

Verify schedule dates for the next submittal of this matrix against update WEC schedule.

Open Awaiting for document to be docketed by TVA. Open Due 10/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 073 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Integration Phase V&V Report" was October 29, 2010. Responder: Clark Date: 5/25/10 Verify schedule dates for the next submittal of this matrix against update WEC schedule.

Open Awaiting for document to be docketed by TVA. Open Due 11/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 074 EICB (Carte) 3/12/2010 By letter dated March 12, 2010 TVA stated that the target submittal date for the "Final V&V Report" was November 30, 2010. Responder: Clark Date: 5/25/10 Verify schedule dates for the next submittal of this matrix against update WEC schedule.

Open Awaiting for document to be docketed by TVA. Open Due 12/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 075 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 PAMS Specific FAT Procedure" was September 30, 2010. Responder: Clark Date: 5/25/10

Verify schedule dates for the next submittal of this matrix against update WEC schedule.

Open Awaiting for document to be docketed by TVA. Open Due 10/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 076 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 PAMS Specific Processor Module Software Test" was August 31, 2010. Responder: Clark Date: 5/25/10

Verify schedule dates for the next submittal of this matrix against update WEC schedule. Open Awaiting for document to be docketed by TVA. Open Due 9/15/10 FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 077 EICB (Carte) 3/12/2010

By letter dated March 12, 2010 TVA stated that the target submittal date for seven other documents was "TDB".

Please provide a schedule for the docketing of the remaining documents. Responder: WEC Date: 5/25/10 The availability dates for these documents are included in the revised WBN2 Common Q ISG-6 Compliance Matrix submitted in response to item 43. As stated in the March 12, 2010 letter (Reference 4), the dates in the matrix are the dates the documents will be available to TVA to prepare for submittal or being "Available for Audit". They do not reflect the dates the documents will be submitted to the NRC. Expected submittal date is two weeks after TVA receives the document. Open Open Regulations require that the NRC review be based on docketed material. Awaiting for document to be docketed by TVA. Open TVA to provide requested

information.

TVA to provide date when information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) 4/26/2010 FSAR Section 7.1.2.1.8 adds a reference 6 to the FSAR.

However, Reference 6 is for instrument setpoint and has nothing to do with the diversity discussion on the FSAR Section. We believe the TVA wants to add reference 7 which is the diversity document, WCAP 13869, "Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors." Please confirm this and add commitment to revise FSAR to correct the reference. (Q1) Also, confirm whether this WCAP has been reviewed by NRC, if yes, provide reference and if not, then submit the WCAP to NRC. (Q2) Also provide the justification for this reference to WBN2. (Q3) Responder: Clark Date: 5/25/10 (Q1) The cross reference information is corrected in FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 (Reference 2).

(Q2) WCAP-13869 Rev. 1 was previously reviewed under WBN Unit 1 SER SSER 13 (Reference 9).

Need to identify differences to Revision 2.

(Q3) Westinghouse confirmed the applicability of this WCAP to Watts Bar Unit 2 in letter WBT-D-1321, Final Response to WBT-TVA-0713 Unit 2 WCAP Reviews, dated December 2, 2009 (Reference 10). Open Awaiting TVA response. Open FSAR Amd 100

SSER 13 for unit 1 references rev. 1 of WCAP 13869.

Rev. 2 is used for Unit 2. Identify all the differences between Rev.1 and Rev.2 and justify their acceptability. 079 EICB (Garg) 4/26/2010 FSAR Section 7.1.2.1.9, Trip Setpoints, adds reference to 3, 4, and 5. However, reference 3 was deleted by FSAR amendment 81. Reference 4 has been changed to ISA-DS-67.04-1982. Just ify applicability of this standard for WBN 2.(Q1) Why the latest ISA standard endorsed by NRC has not been used? (Q2) Also reference 5 is a topical report for Eagle 21, system. Please confirm that this topical report also discusses the setpoint for Eagle 21 system and whether it meets the recent guidance for the setpoint issued by the staff. (Q3) Also, W setpoint methodology do not provide discussion on the AS Found Tolerance and As left value determination and how these values are used for the instrument operability, therefore, add the discussion of these topics in the FSAR. (Q4) and add reference to other documents if it is discussed in some other document. (Q5) Provide this document to the staff for review and approval. (Q6) Responder: Clark Date: 5/25/10 (Q1) WBN Unit 2 is licensed based on WBN Unit 1. The WBN Unit 1 licensing basis is ISA-DS-67.04-1982. Therefore this methodology is used for the same SSDs for WBN Unit 2. This maintains consistency in the licensing bases for both units.

(Q2) Please refer to the response to Q1.

(Q3) FSAR Reference 4 is the Eagle 21 Topical Report. FSAR Reference 5, WCAP-17044, Westinghouse Setpoint Methodology for Protection Systems Watts Bar Unit 2 submitted under TVA letter to the NRC dated February 12, 2010 (Reference 11) discusses the setpoint methodology used for Eagle 21 loops.

(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).

Closed Closed This item is closed as it will be reviewed under item 154. FSAR Amd 100 080 EICB (Singh) 4/26/2010 FSAR Table 7.1-1, Note 12 has been added to the table but it's justification has not been provided to the staff for review and approval. Responder: WEC A revised note was included in the 7/30 letter along with justification for the note. Open Open NRC review.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 081 EICB (Carte) 5/6/2010 The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in Section 7, lists codes and standards applicable to the Common Q PAMS. This list contains references to old revisions of several regulatory documents, for example: (1) RG 1.29 - September 1978 vs. March 2007 (2) RG 1.53 - June 1973 vs. November 2003 (a) IEEE 379-1994 vs. -2000 (3) RG 1.75 - September 1975 vs. February 2005 (a) IEEE 384-1992 vs. -1992 (4) RG 1.100 - June 1988 vs. September 2009 (a) IEEE 344-1987 vs. -2004 (5) RG 1.152 - January 1996 vs. January 2006 (a) IEEE 7-4.33.2-1993 vs. -2003 (6) RG 1.168 - September 1997 vs. February 2004 (a) IEEE 1012-1986 vs. -1998 (b) IEEE 1028-1988 vs. -1997 (7) IEEE 279-1991 vs. 603-1991

(8) IEEE 323-1983 vs. -1974 (R G 1.89 Rev. 1 June 1984 endorses 323-1974) However, 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."

Please identify all differences between the versions referenced and the current staff positions. Please provide a justification for the acceptability PAMS with respect to these differences. Responder: Merten/WEC The codes and standards documents listed in Section 7 of the Common Q PAMS Licensing Technical Report are the documents that the Common Q platform was licensed to when the NRC approved the original topical report and issued the approved SER. The WBN Unit 2 Common Q PAMS is designed in accordance with the approved Common Q topical report and approved SER and the codes and standards on which the SER was based. Since the current versions referenced are not applicable to WBN Unit 2, there is no basis for a comparison review.

Bechtel to develop a matrix and work with Westinghouse to provide justification. Open ML101600092 Item No.1: There are three sets of regulatory criteria that relate to a Common Q application (e.g. WBN2

PAMS): (a) Common Q platform components - Common Q TR (b) Application Development Processes - Common Q SPM (c) Application Specific - current regulatory criteria The Common Q Topical Report and associated appendices primarily addressed (a) and (b). The Common Q SER states:

'-Appendix 1, "Post Accident Monitoring Systems," provides the functional requirements and conceptual design approach for upgrading an existing PAMS based on Common Q components (page 58, Section 4.4.1.1, "Description")-On the basis of the above review, the staff concludes that Appendix 1 does not contain sufficient 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. Open TVA to provide requested information.

TVA to provide date when information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 082 EICB (Carte) 5/6/2010 The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in Section 2.3, lists hardware/software changes to the Common Q PAMS previously reviewed by the NRC. However the Common Q ISG-6 Compliance Matrix does not contain activities that address qualification of all changes specifically: Responder: WEC Date: 6/18/10 These components can be found in the Summary Qualification Report Of Hardware Testing For Common Q Applications, 00000-ICE-37764, Rev 3 and TWICE Qualification Status Report, WNAQR-00011-SSP Per Westinghouse letter WBT-D-2024, (Reference __) dated June 9, 2010, these documents are available for audit at the Westinghouse Ro ckville Office.

TVA provided information by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item No. 7.

Revision 1 of the Licensing Technical Report provides additional detail on the platform specific to WBN2 and references to the evaluation documentation. Open Regulations require that the NRC review be based on docketed material. Awaiting for document to be docketed by

TVA. NNC 8/9/10: per telephone conversation on 8/5/10, it is not clear how Westinghouse Commercial Grade Dedication Plans and Reports for Digital I&C. Westinhouse agree to present to the NRC in a public meeting on August 17, 2010, and explanation of how their system addreses regulatory 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. Open Updated compliance matrix provided. Awaiting WEC submittal of documents to TVA. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 083 EICB (Carte) May 6, 2010 Please identify all FPGAs in the new or changed PAMS hardware.

Date: 6/18/10 Responder: WEC The FPGAs used in the Common Q PAMS AC160 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.

Closed Date: 5/6/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 084 EICB (Carte) May 6, 2010 Please provide: TVA Design Criteria WB-DC-30-7 Rev. 22, Post Accident Monitoring Instrumentation.

Date: 6/18/10 Responder: Clark Attachment 5 contains Design Criteria WB-DC-30-7 Rev. 22, Post Accident Monitoring Instrumentation.

Closed Date: 5/6/2010 Responsibility: TVA Document received Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 085 EICB (Carte) 5/6/2010 Please provide a detailed description of the PAMS MTP data link to the plant computer. This description should identify all equipment (model & version) and describe the functions that each piece of equipment performs. This description should be of sufficient detail for the NRC to Responder: WEC Is the WEC ISG4 evaluation inadequate?

Operation of the MTP as a barrier device. MTP Fails as a barrier device. Describe what prevents a MTP failure from propagating to the AC160? Open A response will be provided by 10/31/10 NNC 8/11/10: Design information should be avaialble Open Need WEC to provide make and model information after FAT.

FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments independently evaluate the statements made in WNA-LI-00058-WBT Rev. 0, Section 5.3.

Node loss on the bus? Bus loss?

Revise the ISG4 section of the Licensing Technical Report (Rev. 2) to provide a more detailed description of the MTP as a barrier device. now. By letter dated July 30, 2010 (ML102160349) TVA stated that the MTP was connected to a Red Hat Linux Server (see Enclosure 1, Item No. 14 part b.). It is presumed that this server is not safety-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. NNC 8/25/10: Disagree with path forward input by

TVA above. An explanation is about the design is needed. 086 EICB (Carte) 5/6/2010 The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in Section 6, lists references applicable to the Common Q PAMS. This list contains references to old revisions of several regulatory documents, for example:

(1) DI&C-ISG04 - Rev. 0 (ML072540138) vs. Rev. 1 (ML083310185) However, 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." Please identify all differences between the versions referenced and the current staff positions. Please provide

a justification for the acceptability PAMS with respect to these differences. Responder: WEC Date: 5/24/10 The regulatory documents listed in the Common Q PAMS Licensing Technical Report are the documents that the Common Q platform was licensed to when the NRC approved the original topical report and issued the approved SER. The WBN Unit 2 Common Q PAMS is designed in accordance with the approved Common Q topical report and approved SER and the regulatory documents on which the SER was based. Since the current versions referenced are not applicable to WBN Unit 2, there is no basis for a comparison review.

Rev 0 of the Licensing Technical Report references Rev. 1 of ISG4 Open The response does not address the request. This request was regarding guidance that did not exist at the time that the CQ topical report was reviewed. The WBN2 PAMS applicaton must address current regulatory criteria. Open TVA to provide requested

information.

TVA to provide date when information will be docketed. FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2 087 EICB (Darbali) May 6, 2010 Regarding the Sorrento RM-1000 Digital Radiation Processor: Please identify the model and version to be installed. Please include explicit identification of software version. Date: 5/24/10 Responder: Slifer The rate meter is model RM-1000. The software is version 1.2 Closed Date: 5/6/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2.

088 EICB (Darbali) May 6, 2010 Regarding the Sorrento RM-1000 Digital Radiation Processor: Please provide prior software V&V reports. The latest report only addresses Version 1.2.

Date: 5/24/10 Responder: Slifer See response to item 56 Closed Date: 5/6/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section 7.5.2.

089 EICB (Carte) 5/6/2010 What FSAR functions are implemented using Foxboro Intelligent Automation (IA)? Responder: Clark The list of FSAR functions is listed in TVA letter dated March 12, 2010, Enclosure 1, item 12

FSAR Section 7.7.11 will add a discussion of the DCS.

Open Open NRC review NNC: Docketed response states that the applicable FSAR Sections are:

5.6 - 7.2.2.3.2 - Garg 7.2.2.3.3 - Garg 7.2.2.3.4 - Garg 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments See item 4 for questions on failure modes and mesh network. 7.6.8 - 7.7.1.6 -

7.7.1.7 -

7.7.1.8 - 9.3.4.2.1.C -

10.4.7.2 -

090 EICB (Carte) 5/6/2010 What FSAR Systems are implemented using Foxboro Intelligent Automation (IA)? Responder: Clark Date: 5/25/10 The list of FSAR functions is listed in TVA letter 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. Open Open NRC review 091 EICB (Darbali) May 20, 2010 TVA to submit excerpts of EDCRs 52421, 52987, 52321, 52351 and 52601 Date: 5/25/10 Responder: Clark

1. Attachment 6 contains the EDCR 52421 excerpt

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.

Closed Two EDCRs have been submitted. TVA has agreed to submit the remaining EDCRs. Closed Item is Closed and replaced by items 103, 104 and 118.

092 DORL (Bailey) 5/20/2010

TVA to review Licensee Open Item list and determine which items are proprietary. Responder: Hilmes

Next review due 6/18/10 Open Open

Continuous review as items are added 093 EICB (Garg) May 20, 2010 TVA to submit a letter committing to include setpoint methodology discussion in the FSAR no later than amendment 100.

Date: 5/25/10 Responder: Knuettel Letter Sent 5/25/10 Closed Closed 094 EICB (Garg) 5/20/2010 TVA to locate and provide information on the TMI action item to add an anticipated reactor trip on turbine trip to the design bases in the FSAR Responder: Clark Date: 5/25/10 This item is described in FSAR amendment 98, Section 7.2.1.1.2 item 6 page 7.2.9, and Table 7.2-1 item 14, page 7.2-39.

Closed NRC staff will review. Closed 095 B (D arMay 20, 2010 Date: Responder:

Closed Closed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments TVA to review SER supplements 5 and 14 item 7.8.1 and supplement 4 item 7.8.4 and confirm if they are identical to Unit 1. If not provide differences.

Q1: Monitoring of the reactor coolant system relief valve position is the same as Unit 1.

Q2: The reactor trip on turbine trip is the same as Unit 1. Response is satisfactory. Item closed. NRC Review 096 EICB (Darbali) 5/20/2010 TVA to provide information on implementation of IEN 79-22 and how it is addressed in the FSAR Responder:

IEN 79-22 is not specifically listed or discussed in the WBN Unit 1 UFSAR or Unit 2 FSAR. IEN 79-22 is one of the precursors to 10CFR50.49 environmental qualification. The initial SQN and WBN Unit 1 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. Open Response provided. NRC staff to review response.

See Follow up question 283. Open This items will be closed upon the resolution of item 283. 097 EICB (Darbali) May 20, 2010 TVA to review SER Supplement 7 item 7.4.25 deviation on Aux Control Room display of RCS cold leg temperature for applicability to Unit 2.

Date: Responder:

The deviation to not have RCS cold leg temperature 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.

Closed Response is satisfactory. Item closed. Closed 098 EICB (Darbali) May 25, 2010 Unit 1 SER Supplement 7, RCS Cold Leg Temperature instrumentation. How does Unit 2 address this change?

Date: Responder:

Refer to the response to Item 13 11 above.

Closed Response is satisfactory. Item closed. Closed 099 DORL (Bailey) April 12, 2010 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 Date: Responder: WEC Closed Closed Closed to Item 129 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Carte) 5/20/2010 The following Common Q proprietary documents listed in the response and the affidavits for the proprietary documents will be provided by April 9, 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 Responder: WEC The documents, and affidavits for withholding for the listed documents were submitted to the NRC on TVA letter to the NRC dated April 8, 2010.

Closed TVA has not yet docketed all items requested. Closed 101 DORL (Bailey) 4/12/2010 The non-proprietary versions of the following RM-1000, Containment High Range Post Accident Radiation Monitor documents will be provided by June 30, 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 Responder: Slifer The documents, and affidavits for withholding for the listed documents were submitted to the NRC on TVA letter to the NRC dated July 15, 2010. Open Open NRC review TVA is working with the vendor to meet the 6/30 date, however there is the potential this will slip to 7/14.

102 EICB (Carte) May 24, 2010 Provide a schedule for resolution of items 80, 82 and 83 Date: 5/24/10 Responder: WEC Item 80 - no later than July 23, 2010 Item 82 - no later than July 23, 2010 Item 83 - no later than July 23, 2010 Closed Date: Responsibility:

Closed 103 EICB (Darbal i) 5/27/2010 TVA to submit excerpts of EDCR 52321 Responder: Clark Date: 5/27/10 Open EDCR is scheduled for issue 10/13/10 Open Due 10/31/10 Submittal date is based on current EDCR scheduled issue date.

104 EICB (Darbal i) 5/27/2010 TVA to submit excerpts of EDCR 52351 Responder: Clark Date: 5/27/10 Open EDCR is scheduled for issue 11/30/10 Open Due 12/15/10 Submittal date is based on current EDCR scheduled issue date.

105 EICB (Garg) April 29, 2010 Provide As-Found/As-Left methodology procedure Date: Responder: Langley Submitted copy of TI-28 May 14/2010.

Closed Date: 5/27/10 Responsibility: NRC Replaced with new open item 176. Closed 106 EIC B (Cart e)May 6, 2010 Confirm that the Unit 1 and Unit 2 CERPI systems utilize Date: 5/25/10 Responder: Davies Closed Date: Closed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments the same processor (AC110 or AC160). Westinghouse Unit 2 Drawing 6D31420, Watts Bar 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. Responsibility:

107 EICB (Darbali) May 6, 2010 Describe any control functions associated with the RM-1000 radiation monitors.

Date: 5/28/10 Responder: Clark The RM-1000 radiation monitors do not provide any control functions.

Closed Requested information provided.

NRC to review. Closed See ML101940236, Encl 1, Item 29.

108 EICB (Garg) May 6, 2010 We are requested to docket the fact that the appropriate sections of chapter 7 of the FSAR will be updated to include references to:

a. TI-28 to address as-found/as-left issues b. RISC 2006-17 Date: 5/25/10 Responder: Webb/Hilmes This item is addressed as follows:

109. 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. Closed This item is to be worked with item 51. Closed This item is closed as it will be reviewed under item 154. FSAR Amd 100 109.b EICB (Carte) 5/6/2010 The reviewer was unable to identify the sections of the FSAR that correspond to the standard review plan sections7.9. Responder: NA TVA Provided response Open J. Wiebe accepted this action. Open NRC Action 109.a EICB (Darbali) 5/6/2010 The reviewer was unable to identify the sections of the FSAR that correspond to the standard review plan sections 7.8. Responder: NA TVA Provided response Open J. Wiebe accepted this action. Open NRC Action 110 EICB (Garg) May 6, 2010 The reviewer was unable to locate the Eagle 21 WCAPs 12374 and 12375 for review within the NRC records. We agreed to provide the ADAMS numbers for the submittal.

Date: Responder: Clark These items were docketed under ML073550386 Closed Closed 111 EICB (Carte) May 6, 2010 The reviewer was unable to locate information (SER) on the plant computer or annunciator systems and asked us to provide the location within the FSAR where these systems are described.

Date: 5/28/10 Responder: Clark The annunciator system is not described in the WBN Unit 1 UFSAR. As such it is not included in the WBN 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.

Closed Date: Responsibility: Closed 112 (GJune 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments What are the differences between the Unit 1 and Unit 2 Eagle 21 Systems?

Responder: Clark This information is included in TVA letter dated March 12, 2010, Enclosure 1, Item 10.

113 EICB (Garg) 6/1/2010 Are the new model Eagle 21 power supplies installed in Unit 1? Responder: Clark Yes. Attachment 9 provides a work order excerpt and unit difference form. Revised attachment provided on 7/30 letter.

Closed Attachment 9 does not show the vendor and model no. of the Power Supply. Closed 114 EICB (Garg) 6/1/2010 Provide the resolution of the Eagle 21 Rack 5 lockup on update issue. Responder: WEC The following non-proprietary response was developed from proprietary Westinghouse letter WBT-D-2027 (Reference 11), which provided the resolution of this issue. Westinghouse approved this non-proprietary response via e-mail from A. Drake to M. Clark on June 15, 2010.

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 Open The writeup shows that there was differences between Unit 1 and 2 but was not identified to NRC in earlier response. Are there any more surprises like this? Open NRC to review Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Carte) 2/25/2010 Provide a list of digital 1E systems that have a digital communications path to non safety related systems and if

it has: a. Been reviewed before for unit 1 b. Or installed in unit 1 under 50.59, or

c. Is unique to unit 2 Responder: Clark Response states that Eagle21 and the CQ PMAS MTP have communications links to non-safety-related systems..

This item was identified during TVA review of Figure 2.2-1 of the PAMS Licensing Technical Report WNA-LI-00058-WBT, Rev.0 and the figure was revised to remove the connection. It was addressed with Westinghouse at that time. However other Common Q PAMS documents had been issued before the issue was identified to Westinghouse. The Licensing Technical has been corrected and the other documents will be corrected at the next revision

Design change after documents were produced that deleted the connection from the OM to plant computer.

There are no communications from the Operator's Module to the plant computer or any other system. The Common Q PAMS SysRS WNA-DS-01617-WBT Rev. 1, Figure 2.1-1 will be revised to remove this connection by April 1, 2011 and submitted to the NRC by April 15, 2011. Open The CQ PAMS SysRS (WNA-DS-01617-WBT Rev. 1 Figure 2..1-1) shows that the OM has a TCP interface to non-safety. Please provide a list of ALL digital communications paths to non-safety-related systems.

NNC 8/12/10: The staff pinted out this inconsistency to TVA. The staff could consider PAMS Licensing Technical Report to be a correction if TVA specifically identified the inconsistency to the staff, or identified where the error in the SysRSs, SRS, & SDS had already been identified. This apppreas to be a feature in the CQ TR appendix that was carried forward to WBN2 PAMS inappropriately Open TVA to update response 116 EICB (Garg) 6/3/2010 The Eagle 21 boards originally had a conformal coating.

However, the new boards do not. Provide the basis for deletion of the conformal coating. Responder: WEC The response to this RAI was submitted in TVA letter to the NRC dated June 21, 2010. Open Open How is the tin whisker issue is addressed. I think conformal coating was credited to protect against tin whisker issue. Letter sent to Westinghouse requesting the basis information and documentation for submittal to the NRC. 117 EICB (Garg) 6/3/2010 Does TVA use a single sided or double sided methodology for as-found and as-left instrument setpoint values.

(RIS2006-7) Responder: Webb/Powers TVA uses double-sided as-found and as-left tolerances for trip setpoints as described in FSAR amendment 100. Open Open TVA needs to address that trip setpoint and allowable value uncertainties are not reduced by the reduction factor for the single sided reduction factor. 118 EICB (Darbali) 6/8/2010 TVA to submit excerpts from EDCR 55385 Responder: Clark Open TVA has agreed to submit the EDCR by 11/15/10. Open Due 11/15/10 Submittal date is based on current EDCR scheduled issue date. Note: The RVLIS EDCR has been split into two EDCRs. The first EDCR is 52601 (Open Item 91) The second EDCR is 55385. 119 EIC B (Dar bali)June 10, 2010 Submit the non-proprietary version of Sorrento/GA Date: Responder:

Closed Closed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments software V&V report version 1.1 04508005 and withholding affidavit Provided 7/15/2010 Date: 07/29/10 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 EICB (Carte) 5/6/2010 In reviewing the Maintenance Test Panel (MTP) link to the plant computer, the reviewer noted that the MTP software is not purely one directional in that it does allow low level handshaking to support the communications protocol. M. Merten/S. Hilmes

a. The reviewer stated that this was a potential concern and requested additional information on how the MTP ws protected from feedback from the plant computer.

b. The reviewer stated that in the Oconee review, it was found that the non-safety related data diode was easier to credit than a software barrier. It was suggested we look at changing our position to credit the data diode provided it provided a physical barrier to feedback. Need OWL Information SAH

c. During this discussion, the reviewer asked if we had information from Westinghouse that demonstrated the ability of Common Q PAMs to withstand a data storm. A verbal response was that this was required by contract as part of the Factory Acceptance Test and would not be available until the FAT was completed. Need to docket the verbal response and provide a date the information will be available. Believe we stated this in the Tech Report. SAH Responder: Hilmes/Merten/Costley TVA respinded by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item No. 14: Detailed discussion is provided including technical information on the data diode.

See Item 85. TVA not crediting the data diode.

Closed NNC 8/9/10: By letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item No. 14 -

a. TVA stated no new information was found in Westinghouse documentation and that this information would be addressed in the V&V reports, and that the final hardware drawing will be provided. Neither of these two documents will contain the information requested. Please provide a detailed description of the MTP hardware connections and the software that perform the communications. b. The information provided indicates that the MTP is connected directly to a non-safety-related Red Hat Linux Server which is then connected to the data diode divices. Please describe the secure 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? Closed 121 EICB (Garg) 5/6/2010 If not previously provided, provide the requested information in items a, b and c for changes to all platforms between Unit 1 and 2. (Specific request for information on 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 ut ilize a different platform in Unit 1. c. Identify the functions (ensure all control functions are addressed) that have been transferred to the Foxboro Responder: Webb/Webber The information in the letter provides references to previous submittals and a cross reference for the

Foxboro I/A system. Open Open NRC Review Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Spec 200 system that utilize a different platform in Unit 1.

122 EICB (Carte) June 14, 2010 Provide a date for completing the next revision of the Common Q PAMS System Requirements Specification.

Date: Responder: WEC This is a duplicate of NRC RAI Matrix Item 50 and is considered closed.

Closed Closed 123 EICB (Darbali) 6/14/2010 Safety Evaluation(SE) Section 7.7.3 Volume Control Tank Level Control System

1. Confirm whether or not any Instrumentation & Control (I&C) systems or equipment have been changed in the Volume Control Tank Level Control System.

2. In the original Safety Evaluation(SE), NUREG-0847 (ML072060490), Section 7.7.3, the staff addressed a concern that was raised by Westinghouse regarding an adverse control and protection system interaction. (-a single random failure in the VCT level control system could cause the letdown flow to be diverted to the liquid holdup tank). Based on your responses to the staff's questions related to this concern, the staff considered the issue resolved. Confirm that your responses are applicable to Unit 2. Responder:

1. The devices in the Volume Control Tank Level Control System have been replaced. The Volume Control Tank Level Indication and Control functions have been relocated to the Foxboro IA system. The transmitters and indicators have been replaced with 4-20mA technology and the transmitters have been changed to Rosemount.

2. Upscale failure of LT-62-129A: Flow is diverted to the holdup tank but makeup continues to maintain level and alarms alert the operator.

Upscale failure of LT-62-130A: Unlike Unit 1, the makeup control system uses inputs from both LT-62-130A and LT-62-129A. This results in a more robust design that eliminates a single point of failure for LT-62-130A. If transmitter LT-62-130A fails >20mA, the system disregards the input and uses the LT-62-129A 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.

Closed Follow up question is to request a logic diagram 284. Closed 124 EICB (Darbali) 6/14/2010 SE Section 7.7.5 IE Information Notice 79-22

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 2's control and logic functions or describe any changes and why they are acceptable. Responder:

Duplicate of item 96 Closed Closed 125 EICB (Darbali) 6/14/2010 SE Section 7.7.8 AMSAC

1. Confirm whether or not any I&C systems or equipment have been changed in the AMSAC? Describe the changes, if any.

2. NUREG-0847, Supplement 14 (ML072060486), documents the staffs review of FSAR Amendment 81 that found that the AMSAC automatic initiation signal [to start the turbine-driven and motor-driven AFW pumps] was not Responder:

1. The AMSAC system was not previously installed in Unit 2. EDCR 52408 installs the system. Attachment 3 contains excerpts from the EDCR that describe the Unit 2 system and how it differs from

the Unit 1 system.

2. EDCR 52408 incorporates the AMSAC system into the Unit 2 drawings. Open Staff is reviewing response. Open NRC review Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Darbali) June 14, 2010 SE Section 7.8 NUREG-0737 Items

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

Date: Responder:

No I&C components or systems are affected by this change. Closed Closed 127 EICB (Garg) 6/16/2010 Provide the status of the Eagle 21 Rack 2 RTD accuracy issue. Responder: WEC/Clark The following non-proprietary response was 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. Open Open NRC to review. 128 EICB (Garg) 6/18/2010

Submit the report on the final resolution of the Eagle 21 Rack 2 RTD input issue Responder: WEC

Open Open Staff will issue SE with this as an open item.

Due 12/3/10 TVA Unit 1 has to address first and Unit 2 will follow Unit 1.

129 DORL (Bailey) 6/12/2010 TVA will provide non-proprietary versions of the following Common Q attached proprietary documents and the Responder: WEC The documents, and affidavits for withholding for the listed documents were submitted to the NRC on TVA OpenOpen Due 7/16/10 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments affidavits for the proprietary documents by June 30, 2010. 1. System Design Specification WNA-DS-01667-WBT, Rev. 1

2. System Requirements Specification WNA-DS-01617-WBT, Rev. 1 3. Software Requirements Specification WNA-SD-00239-WBT, Rev. 1 letter to the NRC dated July 14, 2010.

Andy to Verify the documents have been submitted and then close this item.

130 DORL (Bailey) 6/28/2010 TVA committed to revise in Amendment 100: table 4.3-1 to add ID and OD nomenclature to thimble guide tube dimensions . Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 added the ID and OD nomenclature. OpenOpen FSAR Amd 100 131 DORL (Bailey) 6/28/2010 TVA committed to revise in Amendment 100: FSAR 3.10 references to eliminate (LATER) for document numbers. Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 updated the reference document number

information. OpenOpen FSAR Amd 100 132 DORL (Bailey) 6/28/2010 TVA committed to revise in Amendment 100: FSAR 3.10 to correct differences between the list on page 3.10-4 and the numbering refrenced by the text below the list. Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 corrected the numbering in the text. OpenOpen FSAR Amd 100 133 DORL (Bailey) 6/28/2010 TVA committed to revise in Amendment 100: FSAR 3.10 to remove references to IEEE 344-1987. Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 removed the reference to IEEE 344-1987. OpenOpen FSAR Amd 100 134 DORL (Bailey) 6/28/2010

TVA committed to revise in Amendment 100: FSAR Table 1.3-3 to reflect modifications to WBN2 . Responder: Clark

FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 updated the table to reflect the WBN2 modifications. OpenOpen FSAR Amd 100 135 EICB (Darbali) 6/30/2010 TVA committed to add in Amendment 100 a reference to 7.3.1.1.1 in 6.2.5.2.b. Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated Sept 1, 2010 added the reference.

Closed Amendment 100 received. Closed 136 EICB (Darbali) 6/30/2010 TVA committed to replace in Amendment 100 the terms "service water" and "emergency raw cooling water" where they are used incorrectly with "Essential Raw Cooling Water" in sections 7.4, 6.2.1, Table 3.7-25, Table 9.3-3, Table 15.4-14, 1.9.2.7, 7.3.2.2.5 and 11.2.4. Responder: Clark FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated Sept 1, 2010 updated the "service water" and "emergency raw cooling water" nomenclature as required to read essential raw cooling water.

Closed Amendment 100 received. Closed 137 EICB (Carte) 6/17/2010 Several WBN2 PAMS documents contain a table titled, "Document Traceability & Compliance."

(a) Please explain the purpose of this table.

(b) Please describe how this table is different than a reference list.

(c) What does it mean for a document to be listed in this table? Responder: WEC (a) The table is to show the document hierarchy (i.e., what documents are predecessors to the document in relationship to the design life cycle).

(b) This table is showing a hierarchical relationship between documents. These documents are also in the reference list along with other documents that 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.

Open Carte accepted this response 9/1Open TVA to provide date when

information will be docketed.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 138 EICB (Carte) 6/17/2010 By letter dated February 3, 2010, Westinghouse informed TVA that certain PAMS documentation has been completed.

(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." Responder: WEC To be addressed during 9/20-9/21 audit. Open Open TVA to provide date when information will be docketed. 139 EICB (Carte) 6/17/2010 The WBN2 PAMS System Requirements Specification (WBN2 PAMS SysRS) contains a table (see page iii) titled, "Document Traceability & Compliance," which states that the WBN2 PAMS SysRS was created to support no documents. Please explain. Responder: WEC (a) The table is to show the document hierarchy (i.e., what documents are predecessors to the document in relationship to the design life cycle).

(b) This table is showing a hierarchical relationship between documents. These documents are also in the reference list along with other documents that 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. Open Open TVA to provide date when

information will be docketed. WBN2 PAMS System Requirements Specification 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.

140 EICB (Carte) 6/17/2010

The first requirement in the WBN2 PAMS SysRS (i.e., R2.2-1) states: "The PAMS shall be capable of operation during normal and abnormal environments and plant operating modes." The rational for this requirement is that it is necessary to meet Regulatory Guide (RG) 1.97.

Responder: WEC

Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be provided. Open Open TVA to provide date when information will be docketed. WBN2 PAMS System Requirements Specification

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,"

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments What document specifies which RG 1.97 variables are implemented in the Common Q based WBN2 PAMS?

dated December 2009.

141 EICB (Carte) June 17, 2010 deleted Date: Responder:

Closed Closed WBN2 PAMS System Requirements Specification 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 EICB (Carte) 6/17/2010 The applicable regulatory guidance for reviewing the WBN2 PAMS SysRS would be IEEE 830 as endorsed by Regulatory Guide 1.172 and BTP 7-14 Section B.3.3.1, Requirements Activities - Software Requirements Specifications." IEEE 830-1994 Section 4.3.8, "Traceable," states: "A [requirements specification] is traceable of the origin of each of its requirements is clear-" How did TVA ensure the traceability of each requirement in the WBN2 PAMS SysRS. Responder: WEC Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be provided. Open Open TVA to provide date when information will be docketed. WBN2 PAMS System Requirements Specification 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.

143 EICB (Carte) 6/17/2010 The WBN2 PAMS Software Requirements Specification (WBN2 PAMS SRS - ML101050202) contains a table (see page iii) titled, "Document Traceability & Compliance," which states that the WBN2 PAMS SRS was created to support the three documents identified (one of which is the WBN2 PAMS SysRS). Section 1.1, "Overview," of the WBN2 PAMS SRS states: "This document describes 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 tabl e (see page iii) titled, "Document Traceability & Compliance," which states that the WBN2 PAMS SysRS was created to support the WBN2 PAMS SysRS. Secti on 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. Responder: WEC Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be provided. Open Open TVA to provide date when information will be docketed. WBN2 PAMS System Requirements Specification 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.

144 (

C a6/17/2010 Responder: WEC Open Open WBN2 PAMS Software Requirements Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments The WBN2 PAMS Software Requirements Specification (WBN2 PAMS SRS) contains a table (see page iii) titled, "Document Traceability & Compliance," which states that the WBN2 PAMS SRS was created to support the three documents identified (two of these documents have been provided on the docket).

(a) Please describe the third document (i.e., NABU-DP-00014-GEN Revision 2, "Design Process for Common Q Safety Systems").

(b) Please describe the flow of information between these three documents.

(c) Does the PAMS SRS implement the requirements in these three documents?

(d) Please describe if and how these three documents are used in the development of the PAMS Software Design Description.

(e) Do the WBN2 V&V activities include verification that the requirements of these three documents have been incorporated into the WBN2 PAMS SRS.

(a) The purpose of NABU-DP-00014-GEN document is to define the process for system level design, software design and implementation, and hardware design and implementation for Common Q safety system development. This document supplements the Common Q SPM, WCAP-16096-NP-A. The scope of NABU-DP-00014-GEN includes the design and implementation processes for the application development. For a fuller description of the design process described in NABU-DP-00014-GEN please refer to the Design Process for AP1000 Common Q Safety Systems, WCAP-15927 on the AP1000 docket. This document describes the process used for the WB2 PAMS.

(b) - (d) pending

(e) WBN2 PAMS Software Requirements Specification (WNA-SD-00239-WBT, Rev. 1) refers to Document Traceability & Compliance table on page iii. This table has three entries; Design Process for Common Q Safety Systems (NABU-DP-00014-GEN, Rev. 2), RRAS Watts Bar 2 NSSS Completion 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 initiat ed 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.

NRC Review and WEC to complete response.

b-d to be addressed at public meeting and audit. Will require information to be docketed.

Responses to items a and e provided. Need response to b-d.

Specification By letter dated April 8, 2010 (ML10101050203), TVA docketed WNA-SD-00239-WBT, Revision 1, ""RRAS Watts Bar 2 NSSS Completion Program I&C Projects, Software Requirements Specification for the Post Accident Monitoring System," dated February 2010 (ML101050202).

145 EICB (Carte) 6/17/2010

The WBN2 PAMS System Design Specification (WBN2 PAMS SDS) contains a tabl e (see page iii) titled, "Document Traceability & Compliance," which states that the WBN2 PAMS SDS was created to support the WBN2 PAMS SysRS.

(a) Does the WBN2 PAMS SDS implement all of the hardware requirements in the WBN2 PAMS SysRS?

Responder: WEC

Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be provided. Open Open TVA to provide date when information will be docketed. WBN2 PAMS System Design Specification

TVA docketed WNA-DS-01667-WBT Rev. 1, "RRAS Watts Bar 2 NSSS Completion Program I&C Projects Post Accident Monitoring System- System Design Specification," dated December 2009.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments (b) Please briefly describe all of the documents that implement the hardware requirements of the WBN2 PAMS SysRS. 146 EICB (Carte) 6/17/2010 deleted Responder:

ClosedClosed PAMS System Requirements Specifications 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 EICB (Carte) 6/17/2010 deleted Responder:

ClosedClosed PAMS System Requirements Specifications 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 EICB (Carte) 6/17/2010 deleted Responder:

ClosedClosed PAMS System Requirements Specifications 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 EICB (Garg) 6/25/2010 FSAR Section 7.1.1.2(2), Overtemperature delta T and Overpressure delta T equations have been simplified and many values are removed from the FSAR. Provide the justification for this change. Responder: Tindell In FSAR amendment 96 the equations were revised to agree with the Unit 1 UFSAR which is the basis document for the Unit 2 FSAR. This resulted in the equations being simplified and the removal of the values for the constants. The equations were 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. Open In FSAR amendment 96, the values of the constants have been moved to TS or plant procedures. Need to document the basis for this change. Open TVA to provide date when

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

Open Open TVA to provide date when information will be FSAR Section 7.2, Reactor Trip System Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments changes. docketed.

151 EICB (Garg) 6/25/2010 Provide the EDCR 52378 and 54504 which discusses the basis for many changes to this FSAR section. Responder: Clark EDCR 54504 has been voided and replaced with EDCR 52378 which is contained in (Attachment ___ ) and EDCR 52671 is contained in (Attachment ___

). Open Open TVA to provide date when information will be docketed. FSAR Section 7.2, Reactor Trip System 152 EICB (Garg) 6/25/2010

Deleted portion of FSAR section 7.2.3.3.4 and moved to FSAR section 7.2.1.1.5. However, the FSAR section 7.2.1.1.5 does not include the discussion of ambient temperature and also on the calibration of the sealed reference leg system. No justification was provided for deleting this discussion. Please explain the bases for deletion of this information. Responder: Merten/Clark

The text was revised to match the Unit 1 UFSAR. The Unit 1 text was modified in Amendment 1 by FSAR Change Package 1553 S00 which is contained in Attachment 30. The basis for the change in the change package is:

16 The update to Section 7.2.1.1.5 is taken from text in Section 7.2.2.3.4 with clarifications and editorial changes. The relocated discussion of the pressurizer water level instrumentation Is more appropriately included in this section than Section 7.2.2.3.4, which deals with control and protection system interaction. The changes to 7.2.1.1.5 are based on a general description of the Westinghouse pressurizer level 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 Se ction 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. Open Open TVA to confirm if this description is the same as for Unit 1. If it is same as Unit 1 then why this was shown as change in redline version of FSAR Amendment 96.

TVA to provide date when information will be docketed. FSAR Section 7.2, Reactor Trip System 153 EICB (Garg) 6/25/2010

FSAR section 7.2.1.1.7 added the reference to FSAR section 10.4.4.3 for exception to P-12. However, FSAR section 10.4.4.3 states bypass condition is not displayed and it is not automatically removed when conditions for bypass are no longer met. Provide the basis for this. Responder: Craig/Webb

Add alternate method of RCS cooldown using additional steam dump valves after entering Mode 4, by disabling the P-12 Interlock. Operators use additional condenser dump valves to aid in maintaining a cooldown rate closer to the administrative limit established by operating procedure.

Refer to Unit 1 UFSAR Amendment 3 Change Package 1676 S00 (Attachment 6) for the safety evaluation and basis for this change. Open Open TVA will send 50.59.

TVA to provide date when information will be docketed. FSAR Section 7.2, Reactor Trip System Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments The 50.59 for the change is included in the Change Package. 154 EICB (Garg) 6/25/2010 FSAR section 7.2.1.1.10, setpoints: NRC staff has issued RIS 2006-17 to provide guidance to the industry regarding the instrument setpoint methodology which complies with 10 CFR 50.36 requirements. Provide the information on how the WBN2 setpoint methodology meets the guidance of RIS 2006-17 and include this discussion in this section.

Also, by letter dated May 13, 2010, TVA provided Rev. 7 of EEB-TI-28 to the staff. The staff noted that section 4.3.3.6 of EEB-TI-28 discusses the correction for setpoints with a single side of interest. It should be noted that the staff has not approved this aspect of setpoint methodology for Unit 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. Responder: Craig/Webb (Q1) Refer to the response to letter item 13, RAI Matrix Item 51.

(Q2) EEB-TI-28's single sided methodology conforms with WBN's design basis commitment to ensure that 95% of the analyzed population is covered by the calculated tolerance limits as defined in NRC Reg Guide 1.105, Revision 2, 1986 that was in affect during WBN Unit 1 licensing. Open Open FSAR Amd 100.

Since all the setpoint and allowable value for Unit 2 is calculated and added to TS, TVA needs to address the latest criteria and that include 95/95 criteria. FSAR Section 7.2, Reactor Trip System 155 EICB (Garg) June 25, 2010 Summary of FSAR change document section 7.2 states that sections 7.2.1.1.9 and 7.2.2.2(4) are changed to show that these activities will o ccur in future. However, no changes were made to the FSAR sections. Please explain. Date: Responder: Stockton The change package summary were the changes recommended by Engineering. TVA Licensing is responsible for the actual submittal and elected not to incorporate these recommendations. The activities are complete and the text in Amendment 99 of the FSAR is correct.

Closed Closed TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 156 EICB (Garg) 6/25/2010

FSAR section 7.2.2.1.1 states that dashed lines in Figure 15.1-1--designed to prevent exceeding 121% of power--.The value of 121% is changed from 118%.

The justification for this change states that this was done to bring the text of this section in agreement with section 4.3.2.2.5, 4.4.2.2.6 and table 4.1-1. However, Table 4.1-1 and section 4.3.2.2.5 still show this value as 118%. Justify the change. Responder: WEC

Per Westinghouse letter WBT-D-2340, TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 2 FSAR Markups Units I and 2 118%

vs 121 % and Correction to RAI Response SNPB 4.3.2-7, (Reference 17) the 118% value should be 121%. Depending on the use in the FSAR either 118% or 121% are the correct values. As a result of 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 incorp orated in a future FSAR amendment. Open Open TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System Response on hold pending Westinghouse review.

157 EICB (Garg) 6/25/2010 FSAR section 7.2.2.1.1, fifth paragraph was deleted except for the last sentence. The last sentence states that, "The P-8 interlock acts essentially as a high nuclear power reactor trip when operating in this condition." This sentence is confusing because the condition is not defined. Please clarify this discrepancy. Responder: Tindell The condition is defined in the preceeding discussion as operating with a reactor coolant pump out of service and core power less than 25%. Open Open TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 158 EICB (Garg) 6/25/2010

FSAR section 7.2.2.1.1, paragraph six was changed to state that the design meets the requirements of Criterion 23 of the 1971 GDC instead of the Criterion 21 of the GDC. The Criterion 21 is about protection system reliability and testability, while Criterion 23 is about Responder: Tindell

FSAR Amedment 99 reflects the change to Criterion

23. Open Open TVA to provide date when information will be docketed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) 6/25/2010 FSAR section 7.2.2.1.2 discusses reactor coolant flow measurement by elbow taps. However, it further states that for Unit 2, precision calorimetric flow measurement methodology will be used. If elbow taps are not used for Unit 2, then why does this section discuss this methodology? It is the staff's understanding that TVA plans to use elbow taps methodology in the future for Unit

2. Please revise this section to describe the current plant design/methodology. Responder: Craig Elbow taps are used to measure reactor coolant flow for both Unit 1 and 2. However the method used to verify reactor coolant flow, as required by the Technical Specifications, is not the same. Unit 1 uses a simplified methodology based on elbow tap P measurements correlated with precision calorimetric data over several cycles of operation as described in Reference 17, WCAP-16067, Rev 0, 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. Open Open TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 160 EICB (Garg) 6/25/2010 FSAR section 7.2.2.2(7) deleted text which has references 12 and 14. These references are not included in the revised text. Provide the basis for the deletion of these references. Also, the revised text states that typically this requirement is satisfied by utilizing 2/4 logic for the trip function or by providing a diverse trip. Provide any exception to this and their basis for acceptability. Responder: Tindell The text was revised to match the Unit 1 UFSAR.

The Unit 1 text was modified in Amendment 1 by FSAR Change Package 1553 S00 which is contained in Attachment 30. The basis for the change in the change package is:

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. Open Open TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 161 EICB (Garg) 6/25/2010 FSAR section 7.2.2.3 states that changes to the control function description in this section are expected to be required after vendor design of the Unit 2 Foxboro IA design is complete. Provide the schedule for the completion of the design and when this information will be available to the staff for review and approval. Responder: Clark FSAR Amendment 99 reflects the changes associated with the Foxboro I/A system design. Open Open TVA to provide date when

information will be docketed FSAR Section 7.2, Reactor Trip System 162 EICB (Garg) 6/25/2010 FSAR section 7.2.2.2(14) states that bypass of a protection channel during testing is indicated by an alarm in the control room. Explain how this meets RG 1.47. Responder: Tindell The Bypassed and Inoperable Status Indication System (BISI) compliance with Reg. Guide 1.47 is described in detail in FSAR Section 7.5.2.2. Open Open TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 163 (GJune 25, 2010 Date: ClosedClosed 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments deleted Responder: System 164 EICB (Garg) 6/25/2010 FSAR section 7.2.2.2(20) has been revised to include the plant computer as a means to provide information read out for all signals which can cause a reactor trip. Justify the use of the plant computer for this function. Include the discussion on the effect of plant computer failure on the system functions. Responder: Perkins The primary purpose of the plant computer is to present plant process and equipment status information to the control room operators to assist them in the normal operations of the unit, and inform them of any abnormal conditions. The plant 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, "Compu ter 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 (S AT) will be conducted. The SAT will include several te sts: computer accuracy, Open Open TVA to provide date when

information will be docketed FSAR Section 7.2, Reactor Trip System Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) 6/25/2010 FSAR section 7.2.2.3.2, last paragraph of this section has been deleted. The basis for this deletion is that discussion regarding the compliance wi th IEEE-279, 1971 and GDC 24 is covered in section 7.2.2.2. However, there is no reference to this section in 7.2.2.3.2 to direct the reader to 7.2.2.2. Please revise 7.2.2.2 accordingly. Responder: Clark The reference to Section 7.2.2.2 for the general discussion for control and protection interactions is provided in Section 7.2.2.3. The reference in Section 7.2.2.3 is applicable to all Sub-Section paragraphs, including 7.2.2.3.2. An additional reference in this section is not necessary and would be redundant to the Section 7.2.2.3 reference. OpenOpen TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 166 EICB (Garg) 6/25/2010 Changes to FSAR section 7.2.2.2(20) are justified based on the statement that the integrated computer system is implemented through EDCR 52322. Provide a copy of EDCR 52322 for staff review. Responder: Clark EDCR 52322, Design, Procure And Construct An Intergrated Computer System (Ics) For Watts Bar Nuclear Plant Unit 2. Provide All Appropriate Documentation To Support Design Input. Generate Or Revise All Official Drawings To Represent Final Constuction Configuration is contained in Attachment __ OpenOpen TVA to provide date when

information will be docketed FSAR Section 7.2, Reactor Trip System 167 EICB (Garg) 6/25/2010

FSAR section 7.2.2.4, provide an analysis or reference to chapter 15 analysis which demonstrate that failure of rod Responder: Clark

Continuous rod withdrawal events are analyized in FSAR sections 15.2.1 and 15.2.2. While the rod OpenOpen TVA to provide date when FSAR Section 7.2, Reactor Trip System Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments stop during a rod withdr awal event will not affect the safety limit. stops a mentioned, they are not credited in the analysis.

information will be docketed 168 EICB (Garg) 6/25/2010 FSAR table 7.2-4, item 9 deleted loss of offsite power to station auxiliaries (station blac kout) based on the fact that station blackout is not listed in AAPC events. Explain what are AAPC events and how it justifies deleting this accident from the list. Responder: Clark This this change is in accordance with the Unit 1 UFSAR. The change was made by FSAR Change Package 1553 S00 (Attachment __). The justification for the change is:

"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 primar y 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." OpenOpen TVA to provide date when information will be docketed FSAR Section 7.2, Reactor Trip System 169 EICB (Garg) 6/18/2010 Describe the design changes which were made to Unit 1 by 10CFR50.59 process and which significantly affect the instrumentation and controls systems discussed in FSAR Chapter 7. Responder: Clark This is a duplicate of items 2, 10, 11 and 44 ClosedClosed 170 EICB (Garg) 6/17/2010 TVA needs to document that Arnold Magnetics power 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.) Responder: Clark This is a duplicate of item 113.

ClosedClosed 171 EICB (Garg) 6/17/2010 An external unidirectional communications interface was installed between the Eagle 21 test subsystem and the plant process computer. TVA should confirm that testing has demonstrated that two way communication is impossible with the described configuration. (Open Item # 3 of Eagle 21 audit) Responder: Craig This item requires further discussion. It has been deleted from the current letter. OpenOpen TVA to provide date when information will be docketed 172 EICB (Garg) 6/17/2010 During a FAT diagnostic test, the Loop Calculation Processor (LCP) failed while performing a parameter update. TVA should identify the cause and fix for the problem encountered. (Open Item # 1 of Eagle 21 audit) Responder: Craig This is a duplicate of the rack 5 update issue item 114. ClosedClosed 173 (G6/17/2010 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments EEB-TI-28 discusses the correction for setpoints with a single side of interest. The staff finds this correction factor is not justified. TVA should justify this correction factor and demonstrate that, with this correction, factor 95/95 criteria identified in RG 1.105 is met.

TVA to provide date when

information will be docketed 174 EICB (Garg) 6/28/2010 Placeholder: The staff has identifed questions regarding 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. Responder: H ilmes/Craig Duplicate of 171 ClosedClosed 175 EICB (Garg) June 28, 2010 Placeholder: The staff has identified questions regarding diversity. The staff will keep this item open until TVA provides the related WCAP to the staff for its review and approval.

Responder:

WCAP-13869 rev.2. is submitted in response to item Closed In FSAR amendment 98, reference 6 added a new WCAP-13869 rev.2. Has this WCAP been reviewed by the staff. If not then provide the copy of WCAP for staff review. Closed This item is covered under item

78. TVA to provide date when information will be docketed.

176 EICB (Garg) 6/28/2010

Placeholder: The staff has identified questions regarding instrument setpoints. The staff will keep the instrument setpoint methodology issue open until TVA provides additional information regarding RIS 2006-17 and single sided correction factor for uncertainty determination. Responder: Craig/Webb

Open Open TVA to provide date when information will be docketed 177 EICB (Garg) 7/15/2010

FSAR Amendment 99 Section 7.5.1.2 states: "Type A Variables Those variables that provide primary information to the MCR operators to allow them to take preplanned 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. Responder: Clark

The type A variables are the same in Unit 1 and Unit 2. See calculation WBNOSG4047 Rev. 4 (Attachment ) Open August 19, 2010 - TVA to submit calculation. Open TVA to docket calculation. 178 EICB (Marcu s) 7/15/2010 Please provide WBN-OSG4-047, "PAM Type A Variable Determination." Responder: Clark See response to item 177 above. Open August 19, 2010 - TVA to submit calculation. Open TVA to docket calculation. 179 EICB (Carte) 7/15/2010 An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed in Regulatory Guide 1.172, which breaks with typical NRC use of the word

"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 Responder: WEC Steve Clark to look at ho w to combine traceability items.

Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. Open Open TVA to provide date when

information will be docketed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments (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 EICB (Halverson) 7/15/2010 The SRP, BTP 7-14, Section B.3.3.1 states that Regulatory Guide 1.172 endorses, with a few noted exceptions, IEEE Std 830-1993. "IEEE Recommended Practices for Software Requirements Specifications."

Clarify whether the WBU2 Post Accident Monitoring System's 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. Responder: WEC Steve Clark to look at ho w to combine traceability items. Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. OpenOpen TVA to provide date when information will be docketed 181 EICB (Halverson) 7/15/2010

An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed in Regulatory Guide 1.172, which breaks with typical NRC use of the 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" Explain the source(s) of the requirements present in the Post Accident Monitoring System's 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? Responder: WEC

Steve Clark to look at ho w to combine traceability items.

Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. OpenOpen TVA to provide date when information will be docketed 182 EICB (Halverson) 7/15/2010 Characteristics that the SR P states that an Software Requirements Specifications should have include unambiguity, verifiability, and style, part of the latter is that "Each requirement should be uniquely and completely defined in a single location in the SRS."

Clarify whether the unnumbered paragraphs in the Post Accident Monitoring System's Software Requirements Specification, such as in the section headings, or are all Responder: WEC Somewhat redundant with question on Shalls outside of the "requirements" sections.

Shalls included in non-numbered sections and general discussions. OpenOpen TVA to provide date when information will be docketed Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Halverson) 7/15/2010 An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed in Regulatory Guide 1.172, which breaks with typical NRC use of the 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"

On page 1-2 of the Post Accident Monitoring System's 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? Responder: WEC Steve Clark to look at ho w to combine traceability items.

Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. Open Open TVA to provide date when

information will be docketed 184 EICB (Halverson) 7/15/2010

The NRC considers that a System Requirements Specification 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.

Are there any sources of requirements in parallel with the Post Accident Monitoring System's 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? Responder: WEC

Steve Clark to look at ho w to combine traceability items.

Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. OpenOpen TVA to provide date when information will be docketed 185 B (Halvers7/15/2010 An emphasis is placed on the traceability of requirements Responder: WEC Steve Clark to look at ho w to combine traceability OpenOpen TVA to provide Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments in Software Requirements Specifications in the SRP, in the unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed in Regulatory Guide 1.172, which breaks with typical NRC use of the 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 System's 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?

items. Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. date when information will be docketed.

186 7.7.8 7.7.1.1 2 EICB (Darbali) 7/15/2010

Along with Amendment 96, TVA submitted a list of Bechtel changes for each section. Change number 45 addresses a change to section 7.7.1.12, AMSAC, however, the Justification column states "This change is not included. EDCR 52408 installs the AMSAC in Unit 2. It does not have a trouble alarms. The existing words better reflect the operation of the system."

Even thought this change was not included in Amendment 96, will it be included in a future amendment?

Also, please submit a summary of EDCR 52408. Responder: Perkins/Clark

This change will be included in FSAR Amendment 101.

EDCR 52408 Summary: A Purchase Order was issued to Nutherm International to provide a Unit 2 cabinet with the same functions as the current Unit 1 AMSAC. EDCR 52408 will install the cabinet and route/install cabling to provide the necessary inputs/outputs for/from the AMSAC cabinet. The EDCR will only route and install cables from the cabinet to the field side of a terminal block in the Main Control Room panel 2-M-3. These cables will pr ovide 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 Open Response is satisfactory. Issue date of Amendment 101 is not yet determined.

Open Response is acceptable awaiting FSAR amendment submittal. Open Once FSAR Amendmet 101 is received, the item will be closed.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Carte) 7/20/2010 By letter dated June 18, 2010, TVA docketed responses to NRC requests for information.

1) Enclosure 1, Item No. 33 of the TVA letter dated June 18, 2010, did not identify any connection from the PAMS Operator Modules (OMs) to the plant computer and printers; however, Figure 2.1-1 of the PAMS System Requirements Specification (WNA-DS-01617-WBT Rev. 1

- ML101680578) shows a TCP connection from the OMs to the plant computer and printer. Please explain.

2) Please clarify whether any digital safety-related systems or components have a digital communications path to non-safety-related systems or with safety related systems in another division. If so, NRC staff will need these paths identified on the docket. Responder: Clark

1) The original design was to allow printing from both the Operator Module (OM) and Maintenance and Test Panel (MTP) via the plant computer. This required both to be connected to the plant computer. Westinghouse did not perceive this as an issue, because the standard Common Q PAMS design includes both the flat panel displays and individual control panel indicators. The Westinghouse Common Q team did not realize that WBN does not use the individual control panel indicators. As a result, the original design documents provided by Westinghouse included the connection from the OM to the plant computer.

The TVA team did not realize that the Westinghouse 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. Open NNC 8/25/10: Why did TVA not catch this on the review of the PAMS SysRS or SRS? Does TVA check that the CQ PAMS system meets the requirements

in its purchase specifications? Open Are these connections already docketed?

188 EICB (Carte) 7/20/2010 By letter dated June 30, 2010, TVA docketed, "Tennessee Valley Authority (TVA) Watts Bar Unit 2 (WBN2) - Post-Accident Monitoring System (PAMS) Licensing Technical Report," (Document Number WNA-LI-00058-WBT- P, Revision 0, June 2010) (Westinghouse Proprietary Class 2).

1) Figure 2.2-1 of the PAMS Licensing Topical Report does not show any connection between the Operators Modules and the plant computer or printer; however, Figure 2.1-1 of the PAMS System Requirements Specification (WNA-DS-01617-WBT Rev. 1 - ML101680578) shows a TCP connection from the OMs to the plant computer and printer. Please explain.

2) Section 5.3, "Response to individual criteria in DI&C-ISG-04," of the PAMS Licensing Topical Report does not address the TCP connection between the OM and non-safety components depicted in Figure 2.1-1 of the PAMS Responder: Clark

1) The original design was to allow printing from both the Operator Module (OM) and Maintenance and Test Panel (MTP) via the plant computer. This required both to be connected to the plant computer.

Westinghouse did not perceive this as an issue, because the standard Common Q PAMS design includes both the flat panel displays and individual control panel indicators. The Westinghouse Common Q team did not realize that WBN does not use the individual control panel indicators. As a result, the original design documents provided by Westinghouse included the connection from the OM to the plant computer.

The TVA team did not realize that the Westinghouse 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 Open NNC 08/25/10: See Open Item No. 187. Open TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments System Requirements Specification (WNA-DS-01617-WBT Rev. 1 - ML101680578). Please explain. 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.

189 7.6.7 EICB (Singh) 7/20/2010 FSAR Section 7.6.7States: "Conformance with Regulatory Guide 1.133, Revision 1 is discussed in Table 7.1-7." FSAR Chapter 7 does not contain any such numbered table. Please explain. Responder: Clark This is a typographical error. The correct reference is Table 7.1-1. The refe rence will be corrected in FSAR Amendment 100.

Closed NNC 8/25/10: Acceptable response. Closed By FSAR Amendment 100, page 7.6-4.

190 7.9 EICB (Singh) 7/20/2010 NUREG-0800 Chapter 7, Section 7.9, "Data Communication Systems" contains review criteria for data communication systems. The WBN2 FSAR did not include any description of data communications systems. 1) Please identify all data communications systems.

2) Please describe each data communications system identified above. 3) Please provide a regulatory evaluation of each data communications system against the applicable regulatory criteria. Responder: Clark

1) TSR 3.3.6.3 specifies 18 months as the calibration frequency.

2) Per the Technical Requirements Manual (TRM) Bases 3.3.6 (Attachment __) the surveillance requirements and frequency are provided in Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors." 3) TRM section 3.3.6 and it's bases are contained in Attachment __. Open Open TVA to revise response. 191 7.9 EICB (Carte) 7/20/2010 NUREG-0800 Chapter 7, Section 7.9, "Data Communication Systems" contains review criteria for data communication systems. The WBN2 FSAR did not include any description of data communications systems. 1) Please identify all data communications systems. 2) Please describe each data communications system identified above. Responder: Jimmie Perkins WBN Unit 2 is in compliance with the regulatory requirements for data communications systems as described in Attachment 33 (Data Communications Systems Description and Regulatory Compliance Analysis).

See item 4 Open NNC 8/25/10: Information received, and read. Open 192 7.5 EICB (Marcus) 7/20/2010 The NRC Staff is using SRP (NUREG-0800) Chapter 7 Section 7.5, "Instrumentation Systems Important to Safety," to review the WBU2 FSAR Section 7.5, "Instrumentation Systems Important to Safety." The following requests are for information that the SRP directs

the reviewers to evaluate.

The role of the EICB Technical reviewer is to determine if there is reasonable assurance that the equipment will perform the required functions. The WBU2 FSAR, Section 7.5.2, "Plant Computer System," does not contain any description of the equipment that performs the functions described in the section. Enclosure 1 Item 3 of letter dated March 12, 2010, TVA stated that the "platform" of the "Process Computer" was, "Hewlett Packard RX2660 and Dell Poweredge R200 servers with RTP Corp 8707 I/O." In addition TVA provided (a) two pages of marketing Responder: Clark

11. At WBN Unit 1 and 2, there is a single computer system named the "Integrated Computer System" or ICS. That system is sometimes described as the "Plant Computer System", the "Process Computer", the Technical Support Center Data System (TSCDS)

or the Emergency Response Facility Data System (ERFDS). At one time, the TSCDS and ERFDS were separate computers on unit 1 but their functions were all incorporated into the ICS when it was installed.

2. The Watts Nuclear Plant ICS is a non-safety related system, is designed as a single, large-scale nuclear plant computer system which integrates balance of plant (BOP) monitoring with extensive nuclear steam supply syst em (NSSS) application software into a comprehensive computer based tool Open August 19, 2010 - NRC to review TVA response. Open NRC to review response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments literature by DELL on the Poweredge R200 Server, (b) the "HP Integrity rx2660 Server Unser Service Guide," and (c) the Integrated Computer System Network Configuration Connection Diagram (2-45W2697-1-1 dated 8/27/09). This provided information is not sufficient for evaluating whether the equipment will, wi th reasonable assurance, perform the functions described in the FSAR.

1) Is the "Plant Computer System" another name for the "Process Computer"?

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

3) Please describe the relationship between the Plant Computer System and the Integrated Computer System. for plant operations. The system is comprised of the following major components:

Remote multiplexers in the Computer Room, Auxiliary Instrument Room and 480V Board rooms.

Redundant Central Processing Units (CPUs)

Data Storage Devices

Man-Machine Interfaces (MMI) - Satellite Display Stations (SDS) terminals in the Main Control Room (MCR), Technical Support Center (TSC) and Computer Room.

Networking equipment including switches, firewalls and terminal servers

Printers

Data Links to other plant computer devices (serial and network)- These systems or devices include but 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 unit's 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 unit's ICS:

Provides plant emergency support with the Safety Parameter Display System (SPDS) functions based upon the Westinghouse Owner's 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 7/20/2010

The WBU2 FSAR, Section 7.5.2, "Plant Computer System," contains three subsections, 7.5.2.1, "Safety Parameter Display System" 7.5.2.2, "Bypassed and Inoperable Status Indication System (BISI)" 7.5.2.3, "Technical Support Center and Nuclear Data Links" Are there three separate sets of hardware that implement these functions, or are these three functions that are implemented on a single set of hardware? Responder: Clark

There is a single set of hardware that incorporates the functionality of Safety Parameter Display System (SPDS), Bypass and Inoperable Status Indication System (BISI) and the Technical Support Center (TSC).

Also refer to the response to item 71.

The function of the Nuclear Data Links or Emergency Response Data System (ERDS) is actually provided by the TVA Central Emergency Control Center (CECC) which acts as the Emergency Offsite Facility (EOF) for all of TVA's 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. OpenOpen TVA to respond or provide proposed date of response. 194 7.5.2.1 EICB (Marcus) 7/20/2010 The WBU2 FSAR Section 7.5.2.1, "Safety Parameter Display System," contains a description of the Safety Parameter Display System.

SRP Section 7.5, Subsection II, "Acceptance Criteria" states:

Requirements applicable to the review of SPDS-10 CFR 50.55a(a)(1), "Quality Standards."

Please provide a description of how SPDS meets this regulatory requirement. Responder: Costley/Norman The principal purpose and function of the SPDS is to aid control room personnel during abnormal and emergency conditions in determining the safety status of the plant and in assessing if abnormal conditions require corrective action by the operators to avoid a degraded core. It also operates during normal operations, continuously displaying information from which the plant safety status can be readily and reliably accessed.

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 TVA's 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 OpenOpen TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 7/20/2010 Bypassed and Inoperable Status Indication (BISI)

The WBU2 FSAR Section 7.5.2.2, "Bypassed and Inoperable Status Indication System (BISI)," contains a description of the Bypassed Inoperable Status Indication System (BISI).

SRP Section 7.5, Subsection II, "Acceptance Criteria" states:

Requirements applicable to bypassed and inoperable status indication -10 CFR 50.55a(a)(1), "Quality Standards."

Please provide a description of how BISI meets this regulatory requirement. Responder: Costley/Norman The BISI system is a computer based system that provides automatic indication and annunciation of the abnormal status of each ESFAS actuated component of each redundant portion of a system that performs a safety-related function.

To ensure quality, the design, testing, and inspection of the BISI system 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 TVA's nuclear power plants consistent with the Nuclear Quality Assurance Plan.

This ensures that the design and operation of the Open Open TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 7/20/2010

Bypassed and Inoperable Status Indication (BISI)

The NRC staff is performing its review in accordance with LIC-110, Rev. 1, "Watts Bar Unit 2 License Application Review." LIC-110 directs the staff to review systems unique to Unit 2 in accordance with current staff guidance.

Regulatory Guide (RG) 1.47 Revision 1, "Bypassed and Inoperable Status indication for Nuclear Power Plant Safety Systems," is the current regulatory guidance for BISI. Please provide a regulatory evaluation of BISI against the current RG. Responder: Costley/Norman

Section C of the Regulatory Guide lists the following six regulatory positions for guidance to satisfy the NRC requirements with respect to the bypassed and inoperable status indication(BISI) for nuclear power plant safety systems:

1. Administrative procedures should be supplemented by an indication system that automatically indicates, for each affected safety system or subsystem, the bypass or deliberately 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: Open Open TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments

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 system's 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 inoper ability 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 staff's attention.

3. Annunciating functions for system failure and automatic actions based on the self-test or self-diagnostic capabilities of di gital comput er-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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 alar ms 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/inop erability 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 7/20/2010 SRP Section 7.5, Subsection III, "Review Procedures" states: Recommended review emphasis for BISI F. Scope of BISI indications - As a minimum, BISI should be provided for the following systems:

- Reactor trip system (RTS) and engineered safety features actuation system (ESFAS) - See SRP Appendix 7.1-B subsection 4.13, "Indication of Bypasses," and SRP Appendix 7.1-C subsection 5.8.3, "Indication of Bypasses." - Interlocks for isolation of low-pressure systems from the reactor coolant system - See SRP BTP 7-1.

- ECCS accumulator isolation valves - See SRP BTP 7-2. - Controls for changeover of residual heat removal from injection to recirculation mode - See SRP BTP 7-6.

G. Conformance with Regulatory Guide 1.47, "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems."

H. Independence - See SRP Appendix 7.1-B subsection 4.7, "Control and Protection System Interaction," and SRP Appendix 7.1-C subsections 5.6, "Independence," and 6.3, "Interaction Between the Sense and Command Features and Other Systems." The indication system should be designed and installed in a manner that precludes the possibility of adverse effect s 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. Responder: Costley/Norman F. The scope of the WBN BISI indications are based on engineering calculat ion WBPEVAR8807025 Rev. 7 (Attachment __). This calculation has not been updated for Unit 2. The calculation does include Common and Unit 2 equipment required to support Unit 1 operation. G. Compliance to Regulatory Guide 1.47 is described in design criteria document WB-DC-30-29 Rev. 8, Integrated Computer System (Attachment __) which is a design input to calculation WBPEVAR8807025 Rev. 7 (Attachment __). H. Design criteria document WB-DC-30-29 Rev. 8, Integrated Computer System (Attachment __),

section 3.4.1, BISI Design and Operation states: "The BISI shall not be designed to safety related system criteria and therefore is not to be used to perform functions essential to the health and safety of the public. Class 1E isolation is required, however, to maintain the independence of safety related equipment and systems." I. - Response in letter from Mike Norman Open Open TVA to respond or provide proposed date of response. 199 EICB (Marcus) 7/20/2010 The WBU2 FSAR Section 7.5.2.3, "Technical Support Center and Nuclear Data Links," contains a description of the Technical Support Center and Nuclear Data Links.

SRP Section 7.5, Subsection II, "Acceptance Criteria"

states: Requirements applicable to the review of-ERF Responder: Costley/Norman The Technical Support Center is intended to be an accident mitigation support center and provides Satellite Display Stations (SDS) capable of displaying information on plant systems for Unit 1, Unit 2 or the Simulator. Stations in the TSC receive data from the plant Integrated Computer System (ICS) over the ICS network. Separate PCs receive Open Open TVA to respond or provide proposed date of response. Related SE Section 7.5.5.3 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments information systems, and ERDS information systems -10 CFR 50.55a(a)(1), "Quality Standards."

Please provide a description of how the nuclear data links meets this regulatory requirement. data from the simulator computer over the WBN site network to support drills and training exercises. Those PCs can also access the Plant Engineering Data System (PEDS) as a backup to ICS. The TSC 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 EICB (Carte) 7/21/2010

Amendment 99 of the Watts Bar Unit 2 FSAR Section 7.5, "Instrumentation Systems Important to Safety," does not include any description of instrumentation for normal operation; therefore, Section 7.5 of the FSAR does not support statements made in the SER Section 7.5; compare SER (ML072060490) Section 7.5.1 and FSAR Amendment 99 Section 7.5. Please identify where, in the docketed material, information exists to support the statements in the SER Section 7.5.1. Responder: Clark The statement in SER Section 7.5.1 is supported by the following:

I&C Systems for Normal Operation FSAR Section Eagle 21 7.2 Neutron Monitoring 7.2 Foxboro Spec 200 7.3 (List of other sections in attachment 34) 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 Open Open NRC Review Related to SE Section 7.5 201 EICB (Carte) 7/21/2010 Amendment 99, FSAR Section 7.7.1.1.1, "Reactor Control Input Signals (Unit 2 Only)," contains a description of functions performed uniquely for Unit 2. Please describe the equipment that performs this function (in sufficient detail to support a regulatory evaluation), and evaluate this equipment against the appropriate regulatory criteria. Responder: Webb These functions are within the scope of the Foxboro I/A system. Section 7.7.

11 will be added to the FSAR in amendment 101 to provide a discussion of the DCS. Open Open TVA to docket amendment 101. Related to SE Section 7.7.1.1.1 202 EICB (Carte) 7/22/2010

The letter (ML0003740165) which transmitted the Safety Evaluation for the Common Q topical report to Westinghouse stated: "Should our criteria or regulations change so that our conclusions as to the acceptability of the report are invalidated, CE Nuclear Power and/or the applicant referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for continued applicability of the topical Responder: WEC

Revision 1 of the Licensing Technical Report will provide more detailed information on the changes to the platform.

Rev. 2 of the Licensing Technical Report wil include the applicability of guidance. Open Open TVA to respond or provide proposed date of response. Relates to SE Section 7.5.2, PAMS Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Marcus) 7/26/2010 By letter datedApril 27, 2010 (ML101230248), TVA stated (Enclosure Item No.19): "The WBN Unit 2 Itegrated Computer System(ICS) modification merges the ERFDS and plant computer into a single computer network."

FSAR Section 7.5.2, "Plant Computer System," has three subsections:

7.5.2.1, "Safety Parameter Dispaly System" 7.5.2.2, "Bypassed and Inoperable Status Indication System (BISI)"

7.5.2.3, "Technical Cupport Center and Nuclar Data Links" This arrangement implies that the each of these function are part of the plant computer, and not a separate sets of equipment. Please describe the equipment for each function and identify any equipment common to more than one function. Responder: Clark The plant computer system is one set of hardware.

The "Safety Parameter Display System", "Bypassed and Inoperable Status Indi cation System (BISI)", "Technical Support Center and Nuclear Data Links" are all functions of the Plant Computer System. Historically the Westinghouse P2500 Plant Process Computer and Emergency Response Facilities Data System (ERFDS) were individual systems but were merged together with the implementation of DCN 39911-A, implemented for WBN Unit 1 in December 1998, to become the Plant Integrated Computer System (ICS). A similar system is being installed for WBN Unit 2 based on the same software with more modern hardware.

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. Open Open TVA to respond or provide proposed date of response. 204 EICB (Marcus) 7/26/2010 By letter dated March 12, 2010 (ML101680577) TVA provided drawing No. 2-45W2697-1-1, "Integrated Computer System Network Configuration Connection Diagram," that depics three "Data Diode"s. Please provide a detailed description of the equipment, software, and configurations of each "Data Diode". Responder: Costley/Norman

1. Three data diodes. 2. Two provide an interface between train A and B of Common Q. a. These are identical systems consisting of the following:

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 Open Open TVA to respond or provide proposed date of response. Relates to SE Section 7.5.2, PAMS Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) 7/26/2010

Regarding the Foxboro Spec 200 system installed at Unit 2: a- Is it similar to Unit 1? If not, identify the differences and evaluation of the acceptability of these differences.

b- deleted

c- For each system which is discussed in the FSAR and utilizes the Spec 200 sy stem, please provide the instrument logic diagram, loop/block diagram with reference to where the system is discussed in the FSAR. Responder: Clark As discussed at the August 3 and 4 meeting in Knoxville between TVA and the NRC, the Foxboro Spec 200 is not a system. The Foxboro Spec 200 analog hardware is used to replace the existing obsolete hardware with the same functions. There are no interconnections between the analog loops unless such interconnections existed prior to the replacement. This is strictly an analog to analog upgrade due to equipment obsolescence. The Foxboro hardware is installed in existing cabinets which require modifications to accept the Foxboro 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. OpenOpen TVA to respond or provide proposed date of response. Question B related to prior NRC approval of this system or 50.59 information. This question will be addressed in the August plant visit.

206 EIC B (Marcus)7/27/2010

The NRC Requested a description of the plant computer Responder: Clark

(1) The "Plant Computer" is not just a computer but Open Open TVA to respond or Relates to SE Section: 7.5.5, Plant Computer Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments and TVA provided: (1) Dell marketing literature for Dell Poweredge R200 Server, which can be found on the internet (http://www.dell.com/downloads/global/products/pedge/en/pe_R200_spec_sheet_new.pdf), and (2) HP Integrity rx2660 Server User Service guide (edition 6), which has not yet been found on the internet, but many other editions have been found. This information is not adequate for answering the question. (Note: TVA also provided a network configuration connection diagram, which is necessary but not sufficient.)

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. is a system and is designated the Integrated Computer System or ICS. The ICS is composed of multiple computer CPUs, LCD displays, RTP Multiplexer Assemblies, network fiber optic panels, fiber optic converters, Ethernet switches and network taps previously described in items 71, 81 and 82 above. For a detailed discussion of the ICS functions refer to design criteria document WB-DC-30-29 Rev. 8, Integrated Computer System submitted under TVA letter dated August __, 2010.

(2) As previously discussed in item 82, there is no unique set of hardware for any specific function. provide proposed date of response.

207 EICB (Carte) July 27, 2010 deleted Date: Responder:

ClosedClosed 208 EICB (Marcus) 7/27/2010

By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the variable was: (1) implemented identically to Unit 1 and reviewed by the NRC, (2) implemented identically to Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) 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. Responder: Clark The notes provided with the table include the change to the variable under 10 CFR 50.59. For ease of review, the other note references have been deleted for these variables and only the note dealing with the Unit 1 change has been retained in the Notes column of the table excerpt. The applicable notes are highlighted in the notes list. Open Open TVA to respond or provide proposed date of response. Relates to SE Section: 7.5.2, PAMS 209 EICB (Marcus) 7/27/2010 By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the variable was: (1) implemented identically to Unit 1 and reviewed by the NRC, (2) implemented identically to Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) implemented in a manner that is unique to Unit 2. There were nine variables that were identified as both Unique to Unit 2 and identical to what was reviewed and approved on Unit 1. Please explain. Responder: Clark The first eight variables in question are primary chemistry parameter. The parameters are the same for both units, but in Unit 1, the sample is obtained via the post accident sampling system, while in Unit 2 the sample is obtained using a grab sample via the normal sample system.

The last variable was somewhat difficult to characterize. The method of detection and the hardware manufacturer is the same in both units. 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. Open Open TVA to respond or provide proposed date of response. Relates to SE Section: 7.5.2, PAMS 210 EICB (Marcus) 7/27/2010 By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the variable was: (1) implemented Responder: Clark The design basis for Unit 2 is to match Unit 1 as closely as possible. This includes incorporating changes made to Unit 1 after licensing under 10 CFR 50.59. The changes in question fall into this OpenOpen TVA to respond or provide proposed date of response. Relates to SE Section: 7.5.2, PAMS Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments identically to Unit 1 and reviewed by the NRC, (2) implemented identically to Unit 1 but modified under 10 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. category and are described in the Notes for each variable in the original submittal.

211 EICB (Carte) 7/27/2010

FSA Table 7.1-1 shows: "The extent to which the recommendations of the applicable NRC regulatory guides and IEEE standards are followed for the Class 1E instrumentation and control systems is shown below. The symbol (F) indicates full compliance. Those which are not fully implemented are discussed in the referenced sections of the FSAR and in the footnotes as indicated."

Please describe how systems that are important to safety, but not 1E, comply with 10 CFR 50.55a(a)1: "Structures, systems, and components must be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed." Responder: Clark The WBN 2 FSAR Section 7.5 defines the following systems as "important to safety"

1. Post Accident Monitoring including:

a. Common Q Post Accident Monitoring System (Safety-Related) i. Reactor Vessel Level ii. Core Exit Thermocouples iii. Subcooling Margin Monitor b. Eagle 21 indications (Safety-Related)

c. Foxboro Spec 200 indications (Safety-Related) d. Neutron Monitoring (Source and Intermediate Range) (Safety-Related)

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, N3-85-4003, 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 Open Open TVA to respond or provide proposed date of response. Relates to SE Sections: 7.5.5, Plant Computer 7.6.10, Loose Part Monitoring 7.7.1, Control System Description 7.7.2, Safety System Status Monitoring System

7.7.4, Pzr & SG Overfill 7.9, Data Communications Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Carte) 7/27/2010 By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. 3) that the PAMS system design specification and software requirements specification contain information to address the "Design Report on Computer Integrity, Test and Calibration..." The staff has reviewed these documents, and it is not claer how this is the case.

(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. Responder: WEC Application specific requirements for testing. This cannot be addressed in a topical report. Evaluation of how the hardware meets the regulatory requirements.

WEC to provide the information and determine where the information will be located. Open Open TVA to respond or provide proposed date of response. Relates to SE Section 7.5.2 213 EICB (Carte) 7/27/2010 By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. 3) that the PAMS system design specification and software requirements 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? Responder: WEC Open Carte to review and revise this question. Open TVA to respond or provide proposed date of response. Relates to SE Section 7.5.2 214 EICB (Carte) 7/27/2010 By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. 10) that the approved Common Q Topical Report contains information Responder: WEC According to "The Software Program Manual for Common Q Systems," WCAP-16096-NP-1A, the Software Safety Plan only applies to Protection class Open WEC References Common Q PAMS preliminary hazards analysis is referenced in the Open TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments to address the "Safety Analysis." The Common Q SPM however states that a Preliminary Hazards Analysiss Report and the V&V reports document the software hazards analysis. Please Provide these documents. software and PAMS is classified as Important-to-safety. Exhibit 4-1 of the SPM shows that PAMS is classified as Important-to-Safety SRS. WEC to delete.

215 DORL (Bailey) 7/29/2010 By letter dated June 18, 2010, TVA provided a talbe showing the documents that had been completed and were available for staff review. In a conference call on July 27, 2010, TVA agreed to submit the requested documents on the docket. Please provide the schedule for submitting the documents. Responder: WEC Close this item OpenOpen TVA to respond or provide proposed date of response. 216 EICB (Marcus) 7/29/2010 By letter dated March 12, 2010 (ML101680577), TVA stated that it would provide five documents to describe the Process computer: (1) EDCR 52322 Rev. A excerpts, (2)

HP RX2660 Users Guide AB419-9002C-ed6, (3) Dell Poweredge R200 Server sheet November 2007, (4) RTP Corp 8707 I/O Brochure RTP 8707-02, 2004, and (5)

Integrated Computer System Drawing. Responder: Clark

1) EDCR 52322 is contained in Attachment 7. 5) The design change referred to is the addition of a data diode. This has not been incorporated into the drawing. Please see the response to letter item 88 (RAI Matrix Item 224). OpenOpen TVA to respond or provide proposed date of response. 217 EICB (Garg) 7/6/2010 Provide copies excerpts of the EDCRs and DCNs that provide the block and logic diagrams for the Foxboro Spec 200 implementation. Responder: Clark Attachment 7 contains excerpts of the following change documents:

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 OpenOpen NRC Review 218 EICB (Garg) 7/6/2010 Provide copies excerpts of the EDCRs and DCNs that provide the block and logic diagrams for the Foxboro Spec 200 implementation. Responder: Clark The excerpt of work order WO 08-813412-000 provided with the June 18 letter did not contain the information showing that the new type (Arnold) 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. Open Attachment 8 contains the required correct work order excerpt. Open NRC Review 219 EICB (Garg) 8/4/2010 Transmit copy of February 8, 2008 FSAR Red-Line for Unit 2 letter with attachments [CD]. Responder: TVA Licensing A copy was hand carried by Mr. W. Crouch and delivered to Stewart Bailey at the August 17 meeting at NRC headquarters. Open Check what sent by Terry missing attachments. Open 220 EICB (Garg) 8/4/2010 For Safety Related SSPS, submit letter justifying delta between U1 [utilizing ARs] & U2 [utilizing ARs and MDRs]. [Requires TS change ???] Responder: Ayala

The Westinghouse ARLA latch attachment is obsolete. In order to provide a latching relay for Unit 2 Solid State Protection System (SSPS), a MDR 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 Open Are there any open issues? Docket plant specific responses to the individual. Open TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments MDR ESFAS Slave relays on an 18-month interval based on the assessment done in WCAP-13878-P-A, Revision 2, "Reliabilit y 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 We stinghouse 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 EICB (Garg) 8/4/2010 Submit EDCR Technical Evaluation for the source and intermediate range updated electronics for Unit 2 Responder: Trelease The EDCR _____ Source and Intermediate Range, Scope and Intent, Unit Difference and Technical Evaluations are contained in Attachment __. OpenOpen TVA to respond or provide proposed date of response. 222 EICB (Garg) 8/4/2010 Submit updated list for Foxboro Spec 200 [replacement of Bailey and Robert-Shaw electronics Responder: Clark The updated listing of Foxboro Spec 200 loop functions is contained in Attachment 34. OpenOpen 223 EICB (Garg) 8/4/2010 Submit EDCR Technical Evaluationn for Foxboro I/A replacing obsolete non-safety related Foxboro H-Line analog electronics with a digital CDS. [selected single point failures being addressed in design] Responder: Clark Duplicate of item 233.

ClosedClosed 224 EICB (Marcus) 8/4/2010 Mike Norman [TVA Computer Eng. Group] will check status of DCN/50.59 for Integrated Computer System upgrade that will install the data diode between the WBN PEDS and the Unit 1 and Unit 2 ICS. Responder: Norman (TVA CEG)

The Data diode to isolate the WBN Unit 1 and Unit 2 ICS computers from the WBN PEDS computers will be installed in PIC 56278 as part of DCN 54971.

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. OpenOpen TVA to respond or provide proposed date of response. 225 EICB (Garg) 8/4/2010 Provide EDCR Technical Evaluation Justify/explain updated hardware [functionally equivalent to Unit 1] for the RCP and Turbine Generator vibration monitoring equipment. Responder: Scansen The requested information is contained in the Scope and Intent, Unit Difference and Technical Evaluations for EDCRs 52420 (Attachment __) and 53559 (Attachment __) OpenOpen TVA to respond or provide proposed date of response. 226 EICB (Carte/Singh) 8/4/2010 Submit the Foxboro I/A segmentation analysis and ICS Design Criteria documents on an expedited separate letter. Provide a date when the Segmentation analysis will be revised based on discussions at the meeting. Responder: TVA Licensing These documents were submitted under TVA letter dated August 11, 2010.

Closed NNC 8/25/10: Segmentation analysis has been received and read. Please describe why a failure or error will not propagate over the -peer-to-peer network, and cause more than one segment to fail. Closed See also Open Item Nos. 41 & 270.

227 EICB (Garg) 8/4/2010 Provide copies of 50.59s for the following Unit 1 changes

a. CERPI (initial installation and 2009 upgrade)

b. Vibration monitoring (RCP, TG and FW pumps to Responder: Clark

A. CERPI, initial installation DCN 51072 and 2009 upgrade DCN 52957 (Attachment __) B. Upgrade of RCP, TG and FW pumps vibration monitoring to Bentley-Nevada 3300, DCN 39242, OpenOpen TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Bentley-Nevada 3300) c. Containment Sump Level Transmitter replacement d. Turbine Servo Control Valve Card replacement

e. Pressurizer Heater deletion of Backup Heaters on for PZR High Level f. AMSAC

g. Significant ESFAS changes DCN 39506, DCN 39548, and DCN 50750 (Attachment __) C. Containment Sump Level Transmitter replacement, DCN 39608, (Attachment __) D. Turbine Servo Control Valve Card replacement, DCN 38993, (Attachment 1)

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 Comp uter System (ICS), DCN 50301 (Attachment __)

228 EICB (Carte/Sin g h) 8/4/2010 Submit rod control system description N3-85-4003 Responder: Clark The Rod Control Systemt Desciption N3-85-4003 is contained in Attachment 21. Open Open TVA to respond or provide proposed date of response. 229 EICB (Carte) 8/4/2010 Submit Annunciator system description/design criteria Responder: Clark Condition Status/Alarm Design Criteria Document WB-DC-30-21 is contained in Attachment 22. Open NNC 8/25/10: Document not yet received. Open TVA to respond or provide proposed date of response. 230 EICB (Carte) 8/4/2010 Submit Foxboro I/A Procurement Specification excerpts that provide system description information Responder: Webb

The requested Foxboro I/A Procurement Specificaition is contained in Attachment 23. Discuss with Steve Hilmes 1 page description Open NNC 8/25/10: Document not yet received. Open TVA to respond or provide proposed date of response. 231 EICB (Garg) 8/4/2010 Update FSAR Amendment 100 Section 7.1.1.2 markup based on discussion with Hukam Garg. Responder: Clark

FSAR section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 includes the requested clarifications. OpenOpen FSAR Amd 100 232 EICB (Garg) 8/4/2010 Submit EDCR Technical Evaluation for LPMS EDCR Responder: Clark The EDCR 52418 Lose Part Monitoring Scope and Intent, Unit Difference and Technical Evaluations are contained in Attachment 24. OpenOpen TVA to respond or provide proposed date of response. 233 EICB (Carte) 8/4/2010 Submit EDCR Technical Evaluation for Foxboro I/A EDCR Responder: Clark

Foxboro I/A EDCRs 52378 and 52671 Scope and Intent, Unit Difference and Technical Evaluations are contained in Attachment 25. Open NNC 8/25/10: Documents received. Open NRC to review documents. 234 EICB (Carte) 8/4/2010 Bechtel to perform D3 analysis for Common Q PAMS which will be incorporated in to Westinghouse Licensing Technical Report. Responder:

Duplicate of Item 64 ClosedClosed 235 EICB (Garg) 8/4/2010 TVA to ensure Stewart Bailey is on cc: for all Chapter 7 RAI response letters. Responder: TVA Licensing Stewart Bailey has been added to the standard response letter template used for Chapter 7 responses.

ClosedClosed 236 (G8/4/2010 Responder: Clark OpenOpen Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Submit EDCR Technical Evaluation for Foxboro Spec 200 EDCRs Foxboro Spec 200 EDCRs 52343, 52427 and 52641, Scope and Intent, Unit Difference and Technical Evaluations are contained in Attachment 26.

TVA to respond or provide proposed date of response.

237 EICB (Carte) 8/4/2010 Submit EDCR Technical Evaluation for Annunciator EDCR Responder: Clark The Annunciator EDCR 52315 Scope and Intent, Unit Difference and Technical Evaluations are contained in Attachment 27. Open NNC 8/25/10: Documents not yet received. Open TVA to respond or provide proposed date of response. 238 EICB (Carte) 8/4/2010 Discuss with TVA adding a description of the Foxboro I/A system to chapter 7 of the FSAR. Responder: Webb/Hilmes Duplicate of item 201 ClosedClosed 239 EICB (Carte) 8/4/2010 Plan a meeting with TVA the NRC and Westinghouse to review Common Q PAMS documentation. Responder: Hilmes meeting held 8/17/10 Closed Closed 240 EICB (Garg) 8/4/2010 Submit EDCR Technical Evaluation for Vibration Monitoring EDCR(s) Responder: Clark The Scope and Intent, Unit Difference and Technical Evaluations for EDCRs 53559 and 52420 are contained in Attachment 28. OpenOpen TVA to respond or provide proposed date of response. 241 EICB (Singh) 8/4/2010 Review CERPI WCAPs for system description information to be submitted to the NRC. Responder: Davies CERPI was designed after Westinghouse stopped using WCAPs. The documents that provides the most detailed information are the CERPI System Requirements Specification WN-DS-00001-WBT Rev. 2. This document is containted in Attachment

__. OpenOpen TVA to respond or provide proposed date of response. 242 EICB (Garg) 8/4/2010 TVA to make firm decision on date of transfer (before or after initial startup) of Unit 2 loops in service for Unit 1 to new Foxboro Spec 200 hardware Responder: Hilmes

The Unit 2 loops in service for Unit that are scheduled to be transferred to the Foxboro Spec 200 hardware will be transferred prior to Unit 2 fuel load. OpenOpen TVA to respond or provide proposed date of response. 243 EICB (Carte) 8/3/2010 Section 8.2.1 of the Common Q SPM (ML050350234) states that the System Requirements Specification (SysRS) includes the system design basis. Section 1.2, "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. Responder: WEC WEC to address at the 9/15 meeting Open Open TVA to respond or provide proposed date of response. 244 EICB (Carte) 8/3/2010 Section 8.2.2 of the Common Q SPM (ML050350234) states that the Software Requirements Specification (SRS) shall be develped using IEEE 830 and RE 1.172. Clause 4.8, "Embedding project requirements in the SRS," of the

IEEE 830 states that an SRS should address the software product, not the process of producing the software. In addition Section 4.3.2.1 of the SPM states "Any alternatives to the SPM processes or additional project specific information for the ...SCMP...shall be specified in the PQP. Contrary to these two statements in the SPM, the WBN2 Responder: WEC WEC agreed to remove process related items from all docs. Close to previous item and revise previous item to include all documents. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence." LIC-101 Rev. 3 states: "The safety analysis that supports the change 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 Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments PAMS SRS (ML101050202) contains many process 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. safety." 245 EICB (Carte) 8/3/2010 Section 5.8 of the Common Q SPM (ML050350234) identifies the required test documentation for systems developed using the Common Q SPM. Please provide sufficient information for the NRC staff to independently asssess whether the test plan for WBN2 PAMS, is as described in the SPM (e.g., Section 5.8.1). Responder: WEC Relates to the commitment to provide the test plan and the SPM compliance matrix Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 A ppendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence." LIC-101 Rev. 3 states: "The safety analysis that supports the change 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 EICB (Carte) 8/3/2010 Section 4.3.2.1, "Initiation Phase" of the Common Q SPM (ML050350234) requires that a Project Quality Plan (PQP) be developed. Many other section of the SPM identify that this PQP should contain information reuired by ISG6. Please provide the PQP. If "PQP" is not the name of the documentation produced, please describe the documentation producted and provide the information that the SPM states should be in the PQP. Responder: WEC There is a PQP and SPM compliance matrix will be referenced in the Licensing Technical Report.

WEC to identify the elements of the SPM in the compliance matrix Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

LIC-101 Rev. 3 states: "The safety analysis that supports the change 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." 247 EICB (Carte) 8/8/2010 As part of the Common Q topical report development effort, Westinghouse developed the Software Program Manual for Common Q Systems (ML050350234) to address software planning documentation. The NRC reviewed the SPM and concluded: "the SPM specifies plans that will provide a quality software life cycle process, and that these plans commit to documentation of life cycle activities that will permit the staff or others to evaluate the quality of the design features upon which the safety determination will be based. The staff will review the Implementation of the life cycle process and the software

life cycle process design outputs for specific applications on a plant-specific basis." Please identify the implementation documentation produced as a result of following the SPM, and state what information will be docketed. Responder: WEC

The documents will be identified in Rev. 1 of the Licensing Technical Report in the compliance matrix. WEC to make the documents available ASAP in Rockville. May require later submittal. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

LIC-101 Rev. 3 states: "The safety analysis that supports the change 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." 248 EICB (Carte) 8/8/2010 As part of the Common Q topical report development effort, Westinghouse developed the Software Program Manual for Common Q Systems (ML050350234) to address software planning documentation. The NRC Responder: WEC The documents will be identified in Rev. 1 of the Licensing Technical Report in the compliance matrix. WEC to make the documents available ASAP in Rockville. May require later submittal. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments reviewed the SPM and concluded: "the SPM specifies plans that will provide a quality software life cycle process, and that these plans commit to documentation of life cycle activities that will permit the staff or others to evaluate the quality of the design features upon which the safety determination will be based. The staff will review the Implementation of the life cycle process and the software life cycle process design outputs for specific applications on a plant-specific basis." Please identify the design outputs produced as a result of following the SPM, and state when what inform ation will be docketed. analysis that supports the change 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." 249 EICB (Carte) 8/8/2010 The SVVP in the SPM describes the V&V implementation tasks that are to be carried out. The acceptance criterion for software V&V implementation is that the tasks in the

SVVP have been carried out in their entirety. Documentation should exist that shows that the V&V tasks have been successfully accomplished for each life cycle activity group. Please provide information that shows that the V&V tasks havebeen successfully acomplished for each life cycle actifity group. Responder: WEC

Close to previous items to provide the V&V Reports. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

LIC-101 Rev. 3 states: "The safety analysis that supports the change 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." 250 EICB (Carte) 8/8/2010 The SPM describes the softwa re and documents that will be created and placed under configuration control. The SCMP (e.g., SPM Section 6, "Software Configuration Management Plan") describes the implementation tasks that are to be carried out. The acceptance criterion for software CM implementation is that the tasks in the SCMP have been carried out in their entirety. Documentation should exist that shows that the configuration management tasks for that activity group have been successfully accomplished. Please provide information that shows that the CM tasks have been successfully accomplished for each life cycle activity group. Responder: WEC Westinghouse develops Software Release Reports/Records and a Configuration Management Release Report. Describe the documents and when they will be produced. Sumarize guidance on how to produce these records, focus on project specific requirements in SPM etc. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4,"Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence." LIC-101 Rev. 3 states: "The safety analysis that supports the change 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." 251 EICB (Carte) 8/8/2010 The SPM describes the software testing and documents that will be created. The SPM also describes the testing tasks that are to be carried out. The acceptance criterion for software test implementation is that the tasks in the SPM have been carried out in their entirety. Please provide information that shows that testing been successfully accomplished. Responder: WEC Addressed by SPM Compliance matrix in Rev. 1 of the Licensing Technical Report.

Norbert is looking for guidance on how to ask for less. Open Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

LIC-101 Rev. 3 states: "The safety analysis that supports the change 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." 252 EICB (Carte) 8/8/2010 The SPM contain requirements for software requirements traceability analysis and associated documentation (see Section 5.4.5.3, "Requirements Traceability Analysis"). Responder: WEC Explain response to AP1000 audit report. RTM docketed NRC awaiting V&V evaluation of RTM. Open Read ML091560352 Open TVA to respond or provide proposed date of response. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Please provide information that demonstrates that requirements traceability analysis has been successfully accomplished. LIC-101 Rev. 3 states: "The safety analysis that supports the change 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 EICB (Carte) 8/8/2010 TVA provided information by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item No. 8 - that some AC160 module contain FPGAs. For those modules that have not been previously approved, please provide information to address regulatory criteria for FPGAs. Responder: Clark Identify only FPGAs in new or revised modules. If none, provide a revised response. Steve Clark to revise response. Open Open TVA to respond or provide proposed date of response. Related to Open Item no. 83.

LIC-110 Rev. 1 Section 6.2.2 states:

"Design features and administrative programs that are unique to Unit 2 should then be reviewed in 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 EICB (Halverson) 8/10/2010 Please make the following available in Westinghouse's

Rockville office.

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. Responder: WEC WEC Reviewing to ensure all documents are

available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 255 EICB (Halverson) 8/10/2010 Please make the following available in Westinghouse's Rockville office. The Reusable Software Elements Documents. These 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 Responder: WEC WEC Reviewing to ensure all documents are available in Rockville office. OpenOpen TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Halverson) 8/10/2010 Please make the following available in Westinghouse's

Rockville office.

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, Responder: WEC WEC Reviewing to ensure all documents are

available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 257 EICB (Halverson) 8/10/2010 Please make the following available in Westinghouse's Rockville office.

The following are documents that contain requirements used in the SRS which we incorporated by reference within that document.

"AC160 CPU Loading Restrict ions," 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, Responder: WEC WEC Reviewing to ensure all documents are available in Rockville office. OpenOpen TVA to respond or provide proposed date of response.

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Westinghouse Electric Company LLC, "Generic Common Q Software Installation Procedure,"

WNA-IP-00152-GEN, Rev. 7, Westinghouse Electric Company LLC.

258 EICB (Halverson) 8/10/2010

Please make the following available in Westinghouse's Rockville office.

The "IV&V Phase Summary Report", (WNA-VR-00283-WBT Rev . 0 ) indicated that the IV&V team had created some information that may fac ilitate 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 Responder: WEC

WEC Reviewing to ensure all documents are available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 259 EICB (Halverson) 8/10/2010

Please make the following available in Westinghouse's Rockville office.

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. Responder: WEC

WEC Reviewing to ensure all documents are available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 260 EICB (Halverson) 8/10/2010 Please make the following available in Westinghouse's Rockville office.

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" Responder: WEC WEC Reviewing to ensure all documents are available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 261 EICB (Halverson) 8/10/2010 Please provide the Requirements Traceability Matrix for generic PAMS and/or any other RTMs applicable to WBN2 PAMS. Some requirements in the Software Requirements Specification are simply not present in the Watts Bar 2 PAMS specific RTM (WNA-VR-00279-WBT). Responder: WEC WEC to make available in Rockville ASAP. May require later submittal per 9/15 meeting. OpenOpen TVA to respond or provide proposed date of response. LIC-110 Rev. 1 Section 6.2.2 states: "Design features and administrative programs that are unique to Unit 2 should then be reviewed in accordance with current staff positions"

Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence." 262 EICB (Halverson) 8/10/2010 In order to facilityate visits to the Rockville office, please make the following documents available at the Rockville office.

Watts Bar 2 PAMS licensing technical report 00000-ICE-37722 Rev. 0 (ML003733136) Common Q Software Programming manual (ML050350234) Common Q topical report. (ML031830959) Responder: WEC WEC Reviewing to ensure all documents are

available in Rockville office. OpenOpen TVA to respond or provide proposed date of response. 263 EICB (Carte) 8/11/2010 Based on an examination of document available at the

Westinghouse Rockville offices (i.e., NA 7.4, WEC 7.2, WEC 7.3, CDI-3803, & CDI-3722) a CDI appears to identify the verification activities for each critical 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. Responder: WEC

Addressed in 9/20 - 9/21 audit. Open Open TVA to respond or provide proposed date of response. 264 EICB (Carte) 8/11/2010

Please provide a copy of the commercial grade survey(s) applicable to each new (not previously approved) Common Q component. Responder: WEC

After the 9/20 - 9/21 audit. Open Open TVA to respond or provide proposed date of response. 265 EICB (Carte) 8/11/2010

Please provide: WNA-CD-00018-GEN Rev. 3 00000-ICE-35444 Rev. 1 Responder: WEC

After the 9/20 - 9/21 audit. Open Open TVA to respond or provide proposed date of response. 266 EICB (Carte) 8/11/2010 Please provide a high level description of the Foxboro IA equipment used at WBN2. This description should be more detailed than a brochure on the product line (or available on the web), and less detailed than a technical manual on each field replaceable unit. It is expected that such literature already exists. Responder: Webb/Webber SER Level writeup. Steve Hilmes Open Open TVA to respond or provide proposed date of response. 267 EICB (Carte) 8/11/2010 By letter dated June 18, 2010 (ML101940236) TVA stated that the software safety plan (SSP) was not applicable to PAMS applications (see Watts Bar 2 - Common Q PAMS 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. Responder: WEC References will be removed as appropriate. Open Open TVA to respond or provide proposed date of response. 268 EIC B (Cart e)8/19/2010

By letter dated March 12, 2010 (ML101680577), TVA Responder: WEC

Open Open 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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments stated that the application specific hardware and software architecture descriptions are addressed in the WBN2 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. Andy to see what can be done. provide proposed date of response.

269 DORL (Bailey) 8/20/2010 DORL to send the Eagle-21 Audit Report to TVA.

Responder: NRC Open Open 270 EICB (Carte) 8/23/2010 By letter dated June 18, 2009 (ML091560352) the NRC informed Westinghouse that WNA-PT-00058-GEN (see pdf page 7 of 25) did not adequately address the test plan 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. Responder: Clark

Close to items 41 and 226 Steve Clark to confirm item references and close. Open Open See also Open Item Nos. 41 & 226.

271 EICB (Carte) 8/23/2010 By letter dated August 20, 2010 TVA dockated a 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. Responder: WEC 9/15 meeting and 9/20 audit Open Open 272 7.5 EICB (Marcus) 8/26/2010 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. Responder: Clark OpenOpen 273 7.5 EICB (Marcus) 8/26/2010 In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations)," (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. Responder: Clark State samples are taken via the normal sample system. OpenOpen 274.a 7.5 EICB (Marcu s) 8/26/2010 In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations)," Responder: Clark OpenOpen Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments (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.b EICB (Singh) 8/26/2010 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. Responder: Clark OpenOpen 275 EICB (Singh) 8/27/2010 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. Responder: Clark Closed Closed 276 EICB (Garg) 8/27/2010 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 thes e events will not be outside chapter 15 analyses or beyond the capability of operators or safety systems. Responder: Tindell OpenOpen 277 7.6.3 EICB (Garg) 8/27/2010 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. Responder: Clark OpenOpen 278 7.6.6 EICB (Garg) 8/27/2010 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. Responder: Clark OpenOpen 279 7.6.6 EICB (Garg) 8/27/2010

For FSAR Section 7.6.6, provide the justification for the addition of protective covers which operator has to remove before he can have access to control switch to operate two additional valves FCV62-98 and FCV62-99. Responder: Clark OpenOpen 280 7.6.6 (G8/27/2010 Responder: Clark OpenOpen Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 EICB (Garg) 8/27/2010

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. Responder: Clark OpenOpen 282 7.6.9 EICB (Garg) 8/27/2010 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. Responder: Clark OpenOpen 283 7.7.5 XX EICB (Darbali) 8/27/2010 Follow-up to item 96

On Open Item 96, regarding the implementation of IEN 79-22, part of TVA's 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. Responder: Clark Open Open This item is a followup question to item 96.

284 7.7.3 7.4.1 EICB (Darbali) 8/27/2010 Follow-up to item 123

Please provide a readable electrical logic diagram of the Volume Control Tank Level Control System. Responder: Troutman Open Open This item is a followup question to item 123 285 7.3 7.3 EICB (Darbali) 8/27/2010 Follow-up to item 22 Do the control loops meet t he requirements of IEEE-279? If not are they isolated from the circuit which meets the requirements of 279. Responder: Clark Open Open This item is a followup question to item 22 286 7.7.3 9.3.4.2

.4 EICB (Darbali) 8/27/2010

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".

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 No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments Please explain if this deletion was an editorial change to correct a typo.

287 7.7.8 7.7.1.1 2 EICB (Darbali) 8/27/2010

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. Open Open 288 7.3 EICB (Garg) 9/2/2010 Can we add a section to chapter 7 giving a brief overview of the Foxboro Spec 200 in Section 7.3?

Responder: McNeil OpenOpen 289 EICB (Singh) 9/2/2010 Provide an ISG4 diversity analysis for the containment high range accident monitors RM-1000.

Responder: Mather OpenOpen 290 7.7 EICB (Carte) 9/7/2010 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. Responder: Clark Open Open 291 7.7 EICB (Carte) 9/7/2010 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. Responder: Clark Open Open 292 7.2 EICB (Garg) 9/7/2010 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.

OpenOpen 293 7.2.2.3.5 EICB (Marcus) 9/8/2010 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.

OpenOpen 294 7.3 7.3.1.1.1 EICB (Darbali) 9/9/2010 In Amendment 95 of FSAR section 7.3.1.1.1 'Function Initiation', item (13) was arranged into paragraph form from Open Open Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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 MSIV's."

Please explain this omission or state your commitment to correct this in a future amendment.

295 7.3 7.3.1.1.2 EICB (Darbali) 9/9/2010 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.

Open Open 296 7.3 7.3.1.2.1 EICB (Darbali) 9/9/2010 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.

Open Open 297 7.3 7.3.1.2.2 EICB (Darbali) 9/9/2010 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.

Open Open 298 7.3 XX EICB (Darbali) 9/9/2010 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 applicant's justification for some safety-Open Open Agenda for Weekly Telecon with TVA (I&C Chapter 7 only) radD42B8.docx Open Items to be Resolved for SER Approval No. SE Section FSAR Section NRC POC Issue TVA Response(s)

Prop Y/NStatus/ Current Actions Resolution Path RAI No. & Date RAI Response Date Comments 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.

299 X OpenOpen 300 X OpenOpen 301 X OpenOpen Pa ge 1of 1 9/14/2010file://c:\EMailCa p ture\Watts

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