ML102880474

OL - FW: 10/01/2010 WBN2 Open Items List to Be Sent to TVA

ML102880474
Person / Time
Site:	Watts Bar
Issue date:	10/01/2010
From:	Office of Nuclear Reactor Regulation
To:	Division of Operating Reactor Licensing
References
Download: ML102880474 (115)

Text

WBN2Public Resource From: Poole, Justin Sent: Friday, October 01, 2010 10:17 AM To: Crouch, William D Cc: Garg, Hukam; WBN2HearingFile Resource

Subject:

FW: 10/01/2010 WBN2 Open Items List To Be Sent To TVA Attachments: 20101001 Open Items List Master.docx

Bill, Here is the latest version of the Open Items List.

Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Marcus, Barry Sent: Friday, October 01, 2010 9:47 AM To: Poole, Justin Cc: Garg, Hukam; Carte, Norbert; Singh, Gursharan; Darbali, Samir; Kemper, William

Subject:

10/01/2010 WBN2 Open Items List To Be Sent To TVA Justin:

Attached is the 10/01/2010 WBN2 Open Items List to be sent to TVA. Please send this file to TVA with a cc: to Hukam.

EICB Reviewers:

As always, wait until we receive TVAs comments before editing the file on the G: drive.

Barry Marcus EICB/DE/NRR 301-415-2823 O-9H17 1

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 122 Mail Envelope Properties (19D990B45D535548840D1118C451C74D6FD3538F71)

Subject:

FW: 10/01/2010 WBN2 Open Items List To Be Sent To TVA Sent Date: 10/1/2010 10:17:12 AM Received Date: 10/1/2010 10:17:15 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:

"Garg, Hukam" <Hukam.Garg@nrc.gov>

Tracking Status: None "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 779 10/1/2010 10:17:15 AM 20101001 Open Items List Master.docx 289509 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

001 11/19/2009 12/15/2009 Presentation Slides Closed Closed November 19, 3/12/2010 NNC 11/19/09: The FSAR contains EICB (Carte) 2010 mostly description of the function The Watts Bar Nuclear Plant FSAR red-line for Unit 2 This item was partially addressed during the Date: 3/15/2010 ML093230343 that the various TVA systems must (Agency wide Documents Access and Management December 15, 2009 meeting. RAI 1 perform. Therefore this question System Accession Number ML080770366) lists RAI response received. was asked to determine how the changes to the Unit 1 FSAR and depicts how Chapter TVA Letter Dated March 12, 2010 (Enclosure 1, systems have been changed.

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

systems that have not been previously reviewed and approved by the NRC?

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

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

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

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

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

004 11/19/2009 Responder: Webb 1/13/10 Public Open Open November 19, January 13, NNC 11/19/09: LIC-110 Rev. 1 EICB (Carte)

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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

Report is not acceptable. TVA NNC 4/15/10: The response (a) Foxboro I/A Segmentation Analysis, to docket a D3 analysis for the addresses many systems and Calculation DCSSEGMENT, Rev. 0 submitted CQ PAMS. This will be should be read by all EICB on TVA letter to the NRC dated August 11, responded to in Item 64. reviewers..

2010 (Reference).

NNC 8/25/10: The (b) Attachment Error! Reference source not segmentation analysis has found. contains Foxboro proprietary been read. Please explain drawings 08F802403-SC-2001 sheets 1 why it is believed that failure through 6. An affidavit for withholding and will not propagate over the non-proprietary versions of the drawings will peer-to-peer network.

be submitted no later than ___________.

Looking for an architectural (c) Credible Mesh Network Failure Modes description of the network interconnections similar to the Attachment 42 contains the mesh network ICS overview, identification of failure analysis. credible failure modes caused by the mesh network and what (d) Refer to the response to item (c) above. component(s) prevent mesh network failures from disabling the entire system. What prevents a segment failure from propagating across the mesh network and affecting other segments.

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

By letter date February 28, 2008 (Agencywide TVA Letter Dated February 5, 2010: TVA provided Date: 3/15/2010 FSAR AMD 100 Documents Access and Management System the Unit 2 setpoint methodology (WCAP-177044- Responsibility: NRC (Garg)

(ADAMS) Accession Number ML080770366) TVA P Revision 0 - dated December). and TVA (Hilmes and Crouch) provided a "red-lined" version of the FSAR for WBN Unit 2. The purpose of this FSAR "red-line" version TVA Letter Dated March 12, 2010 (Enclosure 1, RAI response received. This was to depict how the Unit 2 FSAR will appear at fuel Item No. 5 on Page 5 of 15): TVA responded to item is closed as this is load. This letter identified significant FSAR changes this request for additional Information covered under item 154 later and provided a X-REF number for each. on.

This item is addressed as follows:

Change 7.3-1 refers to the following two Summary This item requires further Reports: 1. FSAR Amendment 100 which was submitted discussion between TVA and on TVA letter to the NRC dated August __, 2010 the staff concerning the TVA Letter, P. L. Pace to NRC, dated February.9, incorporates as-found and as-left setpoint setpoint methodology 1998, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR tolerance discussion into section 7.1.2.1.9, adds employed for WBN2.

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

to section 7.2.1.1.10.

TVA Letter, P. L. Pace to NRC, dated September 30,

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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

Please submit the 50.59 Evaluations for each of these Summary Reports and identify which parts are relevant to the Unit 2 Setpoint Methodology.

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

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

change 7.3-1 consists of updating a reference from P Revision 0 - dated December 2009). amendment 100 review. NRC Review revision 5 to revision 7 and making it applicable to Unit NNC: WCAP-12096 Rev. 8 is the 1 only, while adding a new reference, applicable only TVA Letter Dated March 12, 2010 (Enclosure 1, Date: 2/16/2010 TVA to reference current revision for Unit 1.

to Unit 2. Item No. 6 on Page 7 of 15): TVA responded to TI-28 for as found this request for additional Information. The Westinghouse Setpoint and as left value. NNC 4/15/10: Hukam, please Reagan, J. R., "Westinghouse Setpoint Methodology methodology document Also provide the update this open item as for Protection Systems, Watts Bar Units 1 and 2, Eagle a. TVA to docket Rev. 8 and identify that Rev. 8 is (WCAP-17044-P Revision 0) reference to appropriate.

21 Version," WCAP-12096 Rev. 7, (Westinghouse the current revision for Unit 1. TVA to identify any identifies that the intermediate FSAR Section 7.1 Proprietary Class 2). Unit 1 Only NRC approval of Rev. 8. and source range calculations for the setpoint TVA to docket Rev. 8 and identify were performed by TVA (2- methodology. that Rev. 8 is the current revision WCAP Westinghouse Setpoint Methodology for In accordance with item 2, below, there is no NMD-092-0131). Please for Unit 1. TVA to identify any NRC Protection System, Watts Bar Unit 2, Eagle 21 change to the methodology, therefore revision 8 is provide the intermediate and This is addressed approval of Rev. 8.

Version, WCAP-17044-P. Unit 2 Only. not included in this response. source range calculations in FSAR performed by TVA (2-NMD- Amendment 100. TVA to describe how TVA Please provide both setpoint methodology documents Westinghouse letter WAT-D-10502 (Attachment 092-0131). calculations for Unit 2 are different identified above. 1) describes the two changes to WCAP-12096 than Unit 1. If they are the same, Revision. 8. The first change addresses the The Westinghouse Setpoint TVA to docket such statement containment sump level transmitter replacement. methodology document under oath and Affirmation.

This change was submitted under 50.59 summary (WCAP-17044-P Revision 0) report (ML073460444, Page 77). The second identifies that the undervoltage change is to delete the power range negative flux and underfrequency rate trip. This item was submitted as a Technical calculations were performed Specification change (ML073201052). The by TVA (2-27-068-0031).

Technical Specification change was subsequently Please provide the approved. undervoltage and underfrequency calculations The current revision of Unit 1 WCAP-12096 is performed by TVA (2-27-068-Revision 9. Revision 9 was issued to make the 0031).

changes required by the Steam Generator Replacement Project. Unit 2 is using the original Work with Item 7 for WCAP-steam generators, therefore the changes in 12906 issues.

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

submitted under oath and affirmation. This letter fulfills the oath and affirmation requirements for the previous response.

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

Item No. 7 on Page 7 of 15): TVA responded to This item is reviewed in FSAR and SE Section 7.1.3.1.

The setpoint methodology has been reviewed and this request for additional Information. 100 review. NRC Review approved by the NRC staff in Section 7.1.3.1 of NNC 4/15/10: Hukam, please NUREG-0847 (ML072060490), NUREG-0847 a. TVA will submit WCAP-12096, Rev. 8 if there is Date: 1/13/2010 Same as Item 6 update this open item as Supplement No.4 (ML072060524), and NUREG-0847 a change to the methodology. above appropriate.

Supplement No. 15 (ML072060488). RAI response received. NRC No change in methodology, therefore WCAP- to review response. This is addressed TVA to provide Rev. 8 of the Unit 1 Please describe all changes from the methodology 12906, Revision 8 is not submitted. in FSAR document (which is the current one) that has been reviewed and approved by the staff. TVA will submit WCAP-12096, Amendment 100.. if there is a change in methodology

b. TVA will supply the 50.59 letter for Rev. 8 Rev. 8 if there is a change to and identify how the Unit 2 the methodology. document differs from it.

Westinghouse letter WAT-D-10502 (Attachment

1) describes the two changes to WCAP-12096 TVA will supply the 50.59 letter Revision. 8. The first change addresses the for Rev. 8 containment sump level transmitter replacement.

This change was submitted under 50.59 summary TVA to locate transmittal letter report (ML073460444, Page 77). The second that submitted Rev. 7.

change is to delete the power range negative flux rate trip. This item was submitted and approved TVA to determine the last as a Technical Specification change revision of WCAP-12096 (ML073201052). where there was a change in methodology.

c. TVA to locate transmittal letter that submitted Rev. 7. Work with Item 6 for WCAP-12906 issues.

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

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

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

008 7.3 December 11, 2009 TVA Letter Dated March 12, 2010 (Enclosure 1, Closed Closed ML093431118, EICB (Garg)

Item No. 8 on Page 7 of 15): TVA responded to RAI 8 There are several staff positions that provide guidance this request for additional Information FSAR AMD 100.

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

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

009 7.3.2 5.6, December 11, 2009 TVA Letter Dated March 12, 2010 (Enclosure 1, Closed Closed ML093431118, NNC 4/15/10: Related SE Section EICB (Darbali) 6.3.5 Item No. 9 on Page 8 of 15): TVA responded to RAI 9 7.3.

Change 7.3-2, identified in Watts Bar Nuclear Plant this request for additional Information Date: 3/15/2010 FSAR red-line for Unit 2 (ADAMS Accession Number Responsibility: NRC (Darbali)

ML080770366), refers to the following Summary Report: TVA Letter, P. L. Pace to NRC, dated 50.59 evaluation was September 20, 2002, "Watts Bar Nuclear Plant (WBN) submitted in the RAI response.

Unit 1 - 10 CFR 50.59, Changes, Tests and NRC to review.

Experiments Summary Report" Please provide the 50.59 Evaluation summarized in this Summary Report.

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

Item No. 10 on Page 8 of 15): TVA responded to 7.3.

The original SER on Watts Bar (NUREG-0847) this request for additional Information. Date: 3/15/2010 NRC Review documents that the scope of the review of FSAR Section 7.3, Engineered Safety Features Actuations TVA Letter (ML073550386) dated FEB 26 1992: NRC evaluating TVA System, included: included single-line, function logic docketed WCAP-12374 Rev. 1 (ML080500664). response.

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

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

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

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

011 7.3.2 5.6, December 11, 2009 (ML093431118, RAI 11) TVA Letter Dated March 12, 2010 (Enclosure 1, Closed Closed NNC 4/15/10: Related SE Section EICB (Darbali) 6.3.5 Item No. 11 on Page 13 of 15): TVA responded 7.3.

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

NUREG-0847 Supplement No. 2, Section 7.3.2, for Unit 1.

012 7.4 7.4 December 11, 2009 (ML093431118, RAI 12) TVA Letter Dated March 12, 2010 (Enclosure 1, Closed Closed NNC 4/15/10: Related SE Section EICB (Darbali)

Item No. 12 on Page 13 of 15): TVA responded 7.4.

The original SER on Watts Bar (NUREG-0847) to this request for additional Information Date: 3/15/2010 documents that the scope of the review of FSAR Section 7.4, "Systems Required for Safe Shutdown," A revised response was included in the 7/30 letter TVA provided the following:

included single-line and schematic diagrams: "The that provides the requested information.

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

applicable to Unit 2, and include a description of all changes since these diagrams were reviewed and approved by the NRC staff.

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

EICB (Garg)

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

describe how and when setpoint values (e.g., TS RAI response received. 7. NRC will allowable values) will be provided for Unit 2. Westinghouse is completing review T.S. under NNC 4/15/10: Hukam, please the setpoint calculations which different chapter. update this open item as Please describe the information that will be provided to will be completed by May 11, appropriate.

justify the acceptability of these values. 2011. NRC to review response. Related to SE Section 7.1.3.1.

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

Responder: TVA therefore Garg is responsible.

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

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

Eagle 21 and other platforms 1) stated: "In discussion with the staff, TVA's NNC: I do not recall saying understanding is that the focus of this question is that the NRC is not interested the Eagle 21 system. Please refer to Reference 2 in changes in other platforms.

[TVA Letter Dated March 12, 2010], Question 10, Please provide a description of and TVA letter to NRC dated August 25, 2008, changes to other platforms

'Watts Bar Nuclear Plant (WBN) - Unit 2 - (e.g., SSPS).

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

dated August 25, 2008]) for the discussion of changes to the Eagle 21 system." Response understood.

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

015 C B December 22, 2009 (ML093560019, item 2) Date: 4/27/10 Closed Closed (G Responder: TVA

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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

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

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

3). Acceptable. Close 017 7.3.1 7.3.1, December 22, 2009 (ML093560019, item 4) Date: 4/27/10 Open Open 5.5.5, EICB 5.6 Identify precedents in LARs, if any, for the solid state By letter dated April 27, 2010 TVA responded to Date: 4/27/10 NRC Review (Darbali) protection system. Also, identify any hardware this request for information (Enclosure, Item No.

deviation from the precedent. 4). Awaiting NRC evaluation of response.

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

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

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

Verify that the containment purge isolation radiation By latter dated April 27, 2010 TVA responded to Date: 4/27/10 NRC Review monitor is the same as used in Watts Bar Unit 1, or this request for information (Enclosure 1, Item No.

identify any hardware changes. 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.

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

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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

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

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

1. Analog loop comparison meeting.

2. Analog card comparison

3. Analog system description 022 7.3.2 5.6, December 22, 2009 (ML093560019, item 9) Date: 4/27/10 Open Open EICB (Darbali) 6.3.5 Verify the auxiliary feedwater control refurbishment By letter dated April 27, 2010 TVA responded to Date: 4/27/10 NRC Review results in a like-for-like replacement, and identify any this request for information (Enclosure, Item No.

changes from the identified precedents. 9). TVA should confirm if Woodward Governor is the The control function of the Auxiliary Feedwater only change.

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

discrete analog modules as Unit 1 control loops.

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

The differences between the Units that have a control function for the AFW system is the differential pressure control upstream of the motor driven AFW pumps 2A-A and 2B-B. Unit 1 still has the analog Bailey/GEMac controllers and signal conditioners. Whereas Unit 2 has converted the controllers and signal conditioners to Foxboro SPEC 200 discrete analog components. Both

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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 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-3-132C (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-3-132 (on panel 2-L-11B) is in the auxiliary position.

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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 those qualified for Nuclear Class 1E Service per IEEE-323-1974 and IEEE-344-1975.

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

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

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

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

discussed.

NNC 8/18/10: The TVA By letter dated February 5, 2010 (see enclosure agreement in the Comments 1), TVA provided a list of documents and column conflicts with the TVA associated availability for PAMS. responses to other open items where TVA states that By letter dated April 27, 2010 TVA responded to information is available for this request for information (Enclosure, Item No. audit.

11).

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

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

025 EIC B December 22, 2009 (ML093560019, item 12) Date: 4/27/10 Open Open FSAR Section 7.5.1 Post Accident (Sin h) Monitoring Instrumentation - SE For the containment radiation high radiation monitor, By letter dated April 27, 2010 TVA responded to Date: 07/28/2010 NRC Review Section 7.5.2

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verify that the information provided by TVA is this request for information (Enclosure, Item No.

consistent with the information provided with the 12). NRC review in progress.

previously-approved license amendment request for the Duane Arnold plant or provide Phase 3 (See OI 300 for additional information. questions.)

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

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

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

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

equipment in accordance with ISG 4. 14): "There is no digital communications or interactions between Foxboro Intelligent Automation (IA) and any Safety-related system."

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

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

this request for information (Enclosure, Item No.

15).

The requested 50.59 is included in Attachment 1.

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

Responder: TVA For the rod control system, verify that the Date: 4/27/10 refurbishment results in a like-for-like replacement. By letter dated April 27, 2010 (ML101230248) Responsibility: NRC (Carte)

TVA responded to this request for information (Enclosure, Item No. 16 & Attachment 5): TVA stated on a card by card basis that the refurbished cards have the same form fit and function.

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

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

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Revised response acceptable.

There are no other I&C upgrades which contain an imbedded digital processor.

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

EICB (Carte)

Responder: TVA Note: The issue of interlock with For the rod position indication system (CERPI), Date: 4/27/10 rod withdrawal system is addressed provide information in accordance with ISG 4. Need to By letter dated April 27, 2010 TVA responded to Responsibility: NRC (Carte) in open item 301. (Singh Sept22, consider cyber-security issues. this request for information (Enclosure, Item No. 2010) 18). Response acceptable.

032 December 22, 2009 (ML093560019, item 19) Date: 4/27/10 Closed Closed EICB (Carte)

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

19). EICB will no longer consider cyber issues.

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

Responder: TVA is not connected to any other For the loose parts monitoring system, provide Date: 4/27/10 system.

information regarding interactions with safety related By letter dated April 27, 2010 TVA responded to Responsibility: NRC (Carte) equipment. this request for information (Enclosure, Item No.

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

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

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

1 Licensing (see below). For each of the following 21).

significant changes:

Remove all references to Elbow Tap Methodology

1) Is the change unique to Unit 2, or will it be the same from Unit 2 Licensing Bases.

as whats currently installed in Unit 1?

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

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

034. Chapter 7.1 - Introduction Open Open EICB 1 Reactor Coolant System Flow Rate Measurement Design Basis Analysis Parameters Loose Parts Monitoring (Garg/Singh)

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034. Chapter 7.2 - Reactor Trip System Open Open EICB (Garg) 2 Deletion of Neutron Flux Negative Rate Trip Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump Reactor Coolant System Flow Rate Measurement Foxboro I/A 034. 7.3 7.3 Chapter 7.3 - ESFAS Open Open 3 EICB Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam (Darbali) Dump 034. 7.5.1. 7.5.2 Chapter 7.5 - Instrumentation Systems Important to Open Open EICB 4 1 Safety Plant Process Computer Replacement Containment Sump Level Transmitter Replacement (Carte/Marcus)

Safety Injection Systems Cold Leg Accumulator Level Measurement System Common Q/PAMs 034. 7.5.1. 7.5.2 Chapter 7.6 - All Other Systems Required for Safety Open Open EICB 5 1 7.6.7 Plant Process Computer Replacement 7.6.1 Loose Parts Monitoring System (Marcus/Singh) 034. Chapter 7.7 Control Systems Open Open EICB (Singh/Darbali) 6 Alternate Means for Monitoring Control or Shutdown Rod Position Eliminate Pressurizer Backup Heaters on High Level Signal AMSAC Replacement Foxboro I/A WINCISE /Power Distribution Monitoring System (Beacon) 035 2/18/2010 Responder: Clark Open Open LIC-110 Section 6.2.2 states:

EICB (Singh)

Design features and administrative Please provide a system description of the Digital TVA Letter dated March 12, 2010 Enclosure 1, Description provide is not of TVA to docket the programs that are unique to Unit 2 Metal Impact Monitoring System that contains item 4 responded to this request for information. sufficient detail to allow a information should be reviewed in accordance sufficient detail to support a review of this system regulatory determination. TVA including with the current staff positions.

using current staff positions. Attachment Error! Reference source not to send the proprietary proprietary Unit 2 FSAR Section 7.6.7, Loose found. contains the non-proprietary system information for NRC review. At information for Part Monitoring (LPMS) system description which was developed from proprietary the 9-2 meeting G. Singh LPMS. Description, describes a system Westinghouse Watts Bar Unit 2 DIMMS-DX stated the system description design that is unique to Unit 2.

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Operations and Maintenance Manual, 1TS3176 provided was acceptable and Rev.0 (Reference ). Westinghouse approved this the proprietary information was non-proprietary version for public release via letter not required at this time.

WBT-D-2281 dated August 17, 2010 (Reference )

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

Responder: Clark 7.5.2 Please provide a system description of the Post Date: 2/18/2010 Accident Monitoring System that contains sufficient In previous letters TVA has provided the Common Responsibility: TVA NNC: Unit 2 FSAR Section 7.5.1, detail to support a review of this system using current Q documents that address this item: Post Accident Monitoring staff positions. 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 7.5.1. 7.5.2 2/18/2010 Responder: Clark Date: 5/25/10 Closed Closed FSAR Section 7.5, Instrumentation EICB (Marcus) 1 09/16/10 System Important to Safety, Is the plant computer a safety-related display system? As identified in TVA letter dated March 12, 2010, August 19, 2010 - TVA to consists of two major subsections:

Enclosure 1, item 2, the plant computer system is submit markup of FSAR 7.5.1, Post Accident Monitoring non-safety related. Amendment 100. Instrumentation (PAM), and 7.5.2, Plant Computer System.

FSAR section 7.5 describes both safety and non- Plant computer system is non-safety related devices and systems. FSAR safety related. Regulatory Guide 1.70, Standard section 7.1.1.2 is revised in FSAR Amendment format and content of Safety 100 submitted to the NRC on TVA letter to the Analysis Reports for Nuclear Power NRC dated September 1, 2010. 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 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

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process computer is not safety-related. Therefore the docketed material is inconsistent and needs to be clarified.

038 7.5.1. 7.5.2 2/18/2010 Responder: Clark Date: 5/25/10 Open Open The slides presented at the EICB (Marcus) 1 December 15, 2010 meeting Please provide a description of the interfaces between: FSAR sections 7.1.1.2 and 7.5.2 are revised to August 19, 2010 - TVA to NRC review (ML093520967) indicate that the (1) the Safety Parameter Display System and (2) the address this comment in FSAR Amendment 100 submit markup of FSAR plant process computer has been Technical Support Center and Nuclear Data Links with submitted to the NRC on TVA letter to the NRC Amendment 100. replaced.

the plant control and safety systems. This Description dated September 1, 2010.

should contain sufficient detail to support a review of these interfaces using current staff positions.

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

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

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

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

Requirements Specification" Item (3) will be addressed by NRC audit of reference. ISG6. 270.

(2) WNA-DS-01667-WBT Rev. 0, "PAMS System Westinghouse in New Stanton, Connecticut on Design Specification" September 20 and 21. NNC 8/25/10: (3) An earlier TVA to provide (3) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version of this report was date when version 4.5g" Item (4) will be addressed by Westinghouse docketed for the Common Q information will be Please provide the following Westinghouse documents developing a WBN2 Specific Test Plan to topical report; therefore, there docketed.

or pointers to where the material was reviewed and compensate for the fact that the NRC disapproved should be no problem to approved in the CQ TR or SPM: WNA-PT-00058-GEN during the original Common docket this version. (4) Per (4) WNA-PT-00058-GEN Rev. 0, "Testing Process for Q review. No date is available from ML091560352, the testing Common Q Safety systems" Westinghouse when this document will be sent to process document does not (5) WNA-TP-00357-GEN Rev. 4, "Element Software TVA. TVA will provide the document to the NRC address the test plan Test Procedure" within two weeks of receipt. requirements of the SPM.

Please provide a test plan that Item (5) WNA-TP-00357-GEN is superseded by implements the requirements the SPM compliance matrix in the Licensing of the SPM.

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Technical Report next revision scheduled from Westinghouse September 30, 2010. This document will be provided to the NRC within two weeks of receipt.

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

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

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

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

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

Monitoring Instrumentation - SE The PAMS ISG6 compliance matrix supplied as The PAMS ISG6 compliance matrix supplied as Revised compliance matrix is TVA to docketed Section 7.5.2 Enclosure 1 to TVA letter dated February 5, 2010 is a Enclosure 1 to TVA letter dated February 5, 2010 unacceptable. requested first draft of the information needed. The shortcomings is a first draft of the information needed. material. NNC 8/25/10: A CQ PAMS ISG6 of the first three lines in the matrix are: NNC 8/12/10: It is not quite compliance matrix was docketed By letter dated April 8, 2010 TVA provided the enough to provide all of the TVA to provide on: (1) February, 5 12010, (2)

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

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

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commercial grade dedication reports; this apparent deviation should be justified or explained.

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

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

FSAR is implemented in various manners. TVA By letter Dated June 18, 2010 (see Enclosure 1 Responsibility: TVA should identify: Item 6) TVA provided information requested.

(1) Those variables that are implemented identical to what was reviewed and approved for Unit 1.

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

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

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

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

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

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

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

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

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

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

Requirements Specification references revision 3.

In order to resolve this discrepancy an NNC 8/9/10: There are two engineering evaluation of the Common Q PAMS aspects of this issue. The first was performed. aspect has been addressed by the response. The second Attachment 2 contains an engineering evaluation aspect is: How could

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of the Common Q PAMS design against the Westinghouse Design, and requirements of Reg. Guide 1.97 Rev. 2. The TVA approve a design to the evaluation concluded that the Common Q PAMS wrong requirement?

meets all requirements of Reg Guide 1.97 Rev. 2.

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

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

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

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

The Unit 2 Common Q PAMS PLS section was developed based on the actual Common Q PAMS system design as reflected in the System Requirements Specification. As such, the Common Q PAMS PLS section is an output of the Common Q PAMS System Requirements Specification. Therefore, no transition from the Unit 1 to the Unit 2 PLS is required.

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

049 4/8/2010 Responder: WEC Date: 5/25/10 Open NRC Review FSAR Section 7.5.1 Post Accident EICB (Carte)

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

This document was submitted on September 2, TVA to provide 2010. date when information will be docketed.

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

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

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

The System Requirements Specification will be Is there a requirement on the

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revised by September 30, 2010 and submitted shall referenced above??

within two of receipt from Westinghouse.

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

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

guidance provided in TSTF - 493, rev.4 as a basis for meeting the RIS 2006 -17 guidance. 2. TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal dated February 2, 2010.

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

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

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

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

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

054 4/19/2010 Responder: Slifer Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Singh)

Monitoring Instrumentation - SE Please describe all the different environments in which The only safety-related application for the RM- NRC Review Section 7.5.2 the RM-1000 will be required to operate. Please group 1000 is the Containment High Range radiation these environments into two categories (a) Harsh monitors. The Containment High Range radiation environment, per 10 CFR 50.49, and (b) Mild monitors will be installed in the Main Control Environment. Room, a mild environment. The detectors will be installed remotely in the containment.

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

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

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event (DBE) (e.g., temperature rise due to steam release) are no more severe than those which would occur during an abnormal plant operational condition, (2) the temperature will not exceed 130°F due to the indirect effects of a DBE (e.g.,

increased heat loads from electrical equipment),

(3) the event radiation dose is less than or equal to 1 x 104 rads, and (4) the total event plus the 40 year TID (total integrated dose) is less than or equal to 5 x 104 rads. (Reference 3).

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

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

Specifically address EMI and RFI 1974, as well as the System Requirements including EPRI TR 102323 (Sept. 94) in the design basis.

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

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

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

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

(Reference 3) 056 April 19, 2010 Date: 5/25/10 Closed Closed Sorrento Radiation Monitoring EICB Responder: Slifer (Singh) The "RM-1000 Version 1.2 Software Verification and Date: 4/19/2010 Validation Report," Document No. 04508006 Rev. A, is The initial draft Software Verification and Responsibility: NRC

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an incremental report. That is to say it addresses the Validation (V&V) report document, version 1.0, verification an validation for changes that resulted in was never issued. TVA provided the requested Version 1.2; therefore, the NRC has not received a Software V&V Report.

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

The latest proprietary version is 1.2, (an incremental report that addresses the differences from the version 1.1 report) was submitted by TVA Letter dated March 12, 2010 (Reference 4).

Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 101, due June 30, 2010.

057 4/19/2010 Responder: TVA I&C Staff Date: Open Open FSAR Section 7.5.1 Post Accident EICB (Singh) 5/25/10 Monitoring Instrumentation - SE Please describe the ability to change the software of Requested information Response path Section 7.5.2 the RM-1000 at site, including all required equipment Firmware/software changes are done by provided. NRC to review. acceptable. TVA and administrative controls (e.g., temporary digital connecting a laptop to a port on the front of the Further Information to submit the connections). RM-1000 and placing the Operate/Calibrate Requested: Please confirm information for switch in the Calibrate position. The first physical that the laptop is secure and docketing.

barrier to access is the location of the RM-1000 in access to this laptop is the main control room which has limited access. commensurate with the access The RM-1000 Operate/Calibrate switch is located to the equipment for which it behind the hinged front panel. The front panel will be used. Is the laptop must be opened (held closed by two dedicated for calibration of thumbscrews) to access the switch. This provides radiation monitors? If the a physical barrier to inadvertent switch operation. laptop is used for more than The system malfunction alarm is visible locally one application then please and will annunciate on the control board when the describe the equipment for switch is in the Calibrate position. which the laptop may be used.

In addition please explain how Administrative control of software/firmware software security is assured updates is in accordance with TVA Standard and that only the software Specification SS-E18.15.01, Software intended for the specific Requirements for Real-Time Data Acquisition and application is used. Is the Control Computer Systems, and TVA procedures connection to the radiation SPP-9.3, Plant Modifications and Engineering monitors made via a special Change Control, and SPP-2.6, Computer cable/connectors? Please Software Control. Approved changes to confirm that the RS-232 software/firmware are implemented utilizing the communication port of the TVA work order process. radiation monitors will only be used for calibration purposes.

(1) A laptop is not used to calibrate the monitor. Also please confirm that the All TVA in-house activities (calibration, alarm radiation monitor will not be in

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

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 the RM-1000 is made via a standard RS-232 cable.

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

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

(8) See the response to Item 1.

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

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

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

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

The "RM-1000 Version 1.2 Software Verification and Requested information Validation Report," Document No. 04508006 Rev. A is (b) Version 1.2 was implemented April 1, 2008 provided. NRC to review.

dated April 2008. (a) What software version does the technical manual address? (b) When was Version 1.2 implemented?

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

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

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

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

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

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

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

Responder: Clark Monitoring Instrumentation - SE How should the "shall" statements outside of the Date: 4/19/2010 Section 7.5.2 bracketed requirements be interpreted? Duplicate of Item 50 Responsibility: NRC 064 3/12/2010 Responder: Webb Date: Open Open FSAR Section 7.5.1 Post Accident EICB (Carte) 4/8/2010 Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the TVA provided roughly a page TVA to provide Section 7.5.2 target submittal date for the D3 Analysis was April 2, The WBN2 Common Q PAMS provides redundant of description as to why a D3 requested 2010. signal processing and indication of two RG-1.97 analysis is not required. The information.

Type A variables: Core-Exit Temperature (CET) NRC requires additional and Subcooled Margin. In the event of a common- information to determine the TVA to provide cause failure of the Common Q PAMS, acceptability of this response. date when instrumentation diverse from Common Q is information will be available for these two variables. Wide Range docketed.

(WR) Hot Leg Temperature indication is specified as a diverse variable for CET in the Post-Accident Monitoring Design Criteria, WB-DC-30-7 (Attachment ). WR Hot Leg Temperature indication from all four hot legs is available on control board indicators and plant computer displays.

Temperature and pressure saturation margin calculations are also performed in the plant computer independently of Common Q utilizing different hardware and software. Isolated outputs from the Eagle 21 protection system are provided to the plant computer for four WR Hot Leg Temperature channels and four WR RCS Pressure channels. The temperature channels and two of the pressure channels are the same as those used in the Common Q saturation margin calculations.

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The plant computer temperature saturation margin is calculated as the difference in the maximum temperature input and the saturation temperature of the minimum pressure input. The temperature saturation margin is displayed as point ID U0987.

The plant computer pressure saturation margin is calculated as the difference in the minimum pressure input and the saturation pressure of the maximum temperature input. The pressure saturation margin is displayed as point ID U0984.

Reactor Vessel Level Indication (RVLIS) is defined as a Type B1 variable. Redundant indication for this variable is provided by the core exit thermocouples/Thot and reactor coolant system (RCS) pressure. So long as the RCS pressure is greater than the saturation pressure for the temperature indicated by the core exit thermocouples/Thot, there is reasonable assurance that a steam void has not formed in the core and the vessel is full. This is indicated by the subcooled margin monitor/plant computer previously discussed.

065 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the Attachment 37 contains the proprietary version of Awaiting for document to be Due 9/15/10 Section 7.5.2 target submittal date for the FMEA was August 31, the Common Q PAMS FMEA and the affidavit for docketed by TVA.

2010. withholding. A non-proprietary version will be provided at a later date.

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

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

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

• WNA-SD-00250-WBT Rev. 0 (AC160) was the Software Design NRC to review submitted on TVA letter to the NRC dated August Specification (sometimes information 20, 2010 (Reference 7). called an SDD). provided.

• WNA-SD-00248-WBT, Rev. 0 (FPDS) was submitted on TVA letter to the NRC dated SEPT NNC 8/25/10: By letter dated 2, 2010 ( Reference 8 ). august 20, 2010, one (Reference 7) SDD has been provided.

067 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the The following status is from the revised WB2 Regulations require that the TVA to provide Section 7.5.0 & 7.5.2 target submittal date for the "Commercial Grade Common Q PAMS ISG-6 Compliance Matrix NRC review be based on requested Dedication Instructions for AI687, AI688, Upgraded PC submitted in response to Item 43: docketed material. information.

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node box and flat panels." was September 28, 2010.

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

b. Upgraded PC node box and flat panel displays docketed.

- 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 068 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

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

flat panels, and power supplies." was September 28, 2010. a. AI687, AI688 - Scheduled for September 28, TVA to provide 2010 date when information will be

b. Upgraded PC node box - Per Westinghouse docketed.

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

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

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

To be addressed during 9/20-9/21 audit 069 3/12/2010 Responder: WEC Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB Monitoring Instrumentation - SE (Carte) By letter dated March 12, 2010 TVA stated that the Awaiting for document to be Due 11/30/10 Section 7.5.2 target submittal date for the "Watts Bar 2 PAMS docketed by TVA.

Specific FAT Report" was October 2010.

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

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

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

Requirements Traceability Matrix and did not summarize anomalies. At the September 15th public meeting, Westinghouse agreed to include the Concept and Definitions Phase Requirements Traceability Matrix (RTM) in the next IV&V report along with partial Design Phase updates to the RTM.

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

Report" was July 30, 2010.

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

V&V Report" was September 30, 2010.

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

Report" was October 29, 2010.

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

November 30, 2010.

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

Specific FAT Procedure" was September 30, 2010.

076 3/12/2010 Responder: Clark Date: 5/25/10 Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

Monitoring Instrumentation - SE By letter dated March 12, 2010 TVA stated that the Verify schedule dates for the next submittal of this Awaiting for document to be Due 9/15/10 Section 7.5.2 target submittal date for the "Watts Bar 2 PAMS matrix against update WEC schedule. docketed by TVA.

Specific Processor Module Software Test" was August 31, 2010.

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

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

the remaining documents. 43. As stated in the March 12, 2010 letter NRC review be based on (Reference 4), the dates in the matrix are the docketed material. Awaiting TVA to provide dates the documents will be available to TVA to for document to be docketed date when

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prepare for submittal or being Available for by TVA. information will be Audit. They do not reflect the dates the docketed.

documents will be submitted to the NRC.

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

Note: There is a typo in the matrix in line item 33.

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

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

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

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

discussion on the FSAR Section. We believe the TVA (Reference 2). 1 of WCAP wants to add reference 7 which is the diversity 13869. Rev. 2 is document, WCAP 13869, "Reactor Protection System (Q2) WCAP-13869 revision 1 was previously used for Unit 2.

Diversity in Westinghouse Pressurized Water reviewed under WBN Unit 1 SER SSER 13 Identify all the Reactors." Please confirm this and add commitment (Reference 8). Unit 2 references revision 2. A differences to revise FSAR to correct the reference. (Q1) Also, review to identify the differences and justify their between Rev.1 confirm whether this WCAP has been reviewed by acceptability will be performed by September 30, and Rev.2 and NRC, if yes, provide reference and if not, then submit 2010 and submitted to the NRC no later than justify their the WCAP to NRC. (Q2) Also provide the justification November 15, 2010. acceptability.

for this reference to WBN2. (Q3)

(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).

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

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

used? (Q2) Also reference 5 is a topical report for Eagle 21, system. Please confirm that this topical (Q2) Please refer to the response to Q1.

report also discusses the setpoint for Eagle 21 system and whether it meets the recent guidance for the (Q3) FSAR Reference 4 is the Eagle 21 Topical setpoint issued by the staff. (Q3) Also, W setpoint Report. FSAR Reference 5, WCAP-17044, methodology do not provide discussion on the AS Westinghouse Setpoint Methodology for Found Tolerance and As left value determination and Protection Systems Watts Bar Unit 2 submitted

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how these values are used for the instrument under TVA letter to the NRC dated February 12, operability, therefore, add the discussion of these 2010 (Reference 11) discusses the setpoint topics in the FSAR. (Q4) and add reference to other methodology used for Eagle 21 loops.

documents if it is discussed in some other document.

(Q5) Provide this document to the staff for review and (Q4) (Q4) FSAR Amendment 100 which was approval. (Q6) submitted on TVA letter to the NRC dated September 1, 2010 (Reference 2) incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

(Q5) Please refer to the response to Q4.

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

080 4/26/2010 Responder: WEC Open Closed EICB (Singh) FSAR Table 7.1-1, Note 12 has been added to the A revised note was included in the 7/30 letter NRC review table but it's justification has not been provided to the along with justification for the note. complete.

staff for review and approval.

081 5/6/2010 Responder: Merten/WEC Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

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

PAMS. This list contains references to old revisions of Common Q platform was licensed to when the a Common Q application (e.g.

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

(3) RG 1.75 - September 1975 vs. February 2005 approved SER and the codes and standards on Processes - Common Q SPM (a) IEEE 384-1992 vs. -1992 which the SER was based. Since the current (c) Application Specific -

(4) RG 1.100 - June 1988 vs. September 2009 versions referenced are not applicable to WBN current regulatory criteria (a) IEEE 344-1987 vs. -2004 Unit 2, there is no basis for a comparison review. The Common Q Topical (5) RG 1.152 - January 1996 vs. January 2006 Report and associated (a) IEEE 7-4.33.2-1993 vs. -2003 Bechtel to develop a matrix and work with appendices primarily (6) RG 1.168 - September 1997 vs. February 2004 Westinghouse to provide justification. addressed (a) and (b). The (a) IEEE 1012-1986 vs. -1998 Common Q SER states:

(b) IEEE 1028-1988 vs. -1997 (7) IEEE 279-1991 vs. 603-1991 Appendix 1, Post Accident (8) IEEE 323-1983 vs. -1974 (RG 1.89 Rev. 1 June Monitoring Systems, provides 1984 endorses 323-1974) the functional requirements However, LIC-110, "Watts Bar Unit 2 License and conceptual design Application Review," states: "Design features and approach for upgrading an administrative programs that are unique to Unit 2 existing PAMS based on should then be reviewed in accordance with the Common Q components (page current staff positions." Please identify all differences 58, Section 4.4.1.1, between the versions referenced and the current staff Description)On the basis of

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positions. Please provide a justification for the the above review, the staff acceptability PAMS with respect to these differences. 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.

082 5/6/2010 Responder: WEC Date: Open Open FSAR Section 7.5.1 Post Accident EICB (Carte) 6/18/10 Monitoring Instrumentation - SE The PAMS Licensing Technical Report (WNA-LI- Regulations require that the Updated Section 7.5.2 00058-WBT Rev. 0, Dated April 2010), in Section 2.3, These components can be found in the Summary NRC review be based on compliance matrix lists hardware/software changes to the Common Q Qualification Report Of Hardware Testing For docketed material. Awaiting provided.

PAMS previously reviewed by the NRC. However the Common Q Applications, 00000-ICE-37764, Rev for document to be docketed Awaiting WEC Common Q ISG-6 Compliance Matrix does not contain 3 and by TVA. submittal of activities that address qualification of all changes TWICE Qualification Status Report, WNAQR- documents to specifically: 00011-SSP Per Westinghouse letter WBT-D- NNC 8/9/10: per telephone TVA.

2024, (Reference __) dated June 9, 2010, these conversation on 8/5/10, it is documents are available for audit at the not clear how Westinghouse Westinghouse Rockville Office. Commercial Grade Dedication Plans and Reports for Digital

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TVA provided information by letter dated July 30, I&C. Westinghouse agree to 2010 (ML102160349) - See Enclosure 1 Item No. present to the NRC in a public

7. meeting on August 17, 2010, and explanation of how their Revision 1 of the Licensing Technical Report system addresses regulatory provides additional detail on the platform specific criteria for both commercial to WBN2 and references to the evaluation grade dedication and documentation. equipment qualification.

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

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

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

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

Additionally, Westinghouse states in, Westinghouse Letter WBT-D-2170, (Reference

10) that their review of Flat Panel displays and PC Node Boxes concluded that they do not contain any FPGAs.

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

Responder: Clark Monitoring Instrumentation - SE Please provide: TVA Design Criteria WB-DC-30-7 Rev. Date: 5/6/2010 Section 7.5.2 22, Post Accident Monitoring Instrumentation. Attachment 5 contains Design Criteria WB-DC Responsibility: TVA 7 Rev. 22, Post Accident Monitoring Instrumentation. Document received 085 5/6/2010 Responder: WEC Open Open FSAR Section 7.5.1 Post Accident EICB (Carte)

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

performs. This description should be of sufficient a MTP failure from propagating to the AC160? information should be available detail for the NRC to independently evaluate the now. By letter dated July 30, NNC 8/25/10:

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statements made in WNA-LI-00058-WBT Rev. 0, Node loss on the bus? Bus loss? 2010 (ML102160349) TVA Disagree with Section 5.3. stated that the MTP was path forward input Revise the ISG4 section of the Licensing connected to a Red Hat Linux by TVA above.

Technical Report (Rev. 2) to provide a more Server (see Enclosure 1, Item An explanation is detailed description of the MTP as a barrier No. 14 part b.). It is presumed about the design device. that this server is not safety- is needed.

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

Please describe how the MTP serves as the isolation device.

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

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

This list contains references to old revisions of several licensed to when the NRC approved the original guidance that did not exist at regulatory documents, for example: topical report and issued the approved SER. The the time that the CQ topical TVA to provide (1) DI&C-ISG04 - Rev. 0 (ML072540138) vs. Rev. 1 WBN Unit 2 Common Q PAMS is designed in report was reviewed. The date when (ML083310185) accordance with the approved Common Q topical WBN2 PAMS application must information will be However, LIC-110, "Watts Bar Unit 2 License report and approved SER and the regulatory address current regulatory docketed.

Application Review," states: "Design features and documents on which the SER was based. Since criteria.

administrative programs that are unique to Unit 2 the current versions referenced are not applicable should then be reviewed in accordance with the to WBN Unit 2, there is no basis for a comparison current staff positions." Please identify all differences review.

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

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

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

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

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

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

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089 5/6/2010 Responder: Clark Open Open NNC: Docketed response states EICB (Carte) that the applicable FSAR Sections What FSAR functions are implemented using Foxboro The list of FSAR functions is listed in TVA letter NRC review are:

Intelligent Automation (IA)? dated March 12, 2010, Enclosure 1, item 12 5.6 -

7.2.2.3.2 - Garg FSAR Section 7.7.11 will add a discussion of the 7.2.2.3.3 - Garg DCS. 7.2.2.3.4 - Garg 7.2.2.3.5 - Garg See item 4 for questions on failure modes and 7.2.3 - Garg 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 5/6/2010 Responder: Clark Date: 5/25/10 Open Open EICB (Carte)

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

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

091 7.4 7.4 May 20, 2010 Date: 5/25/10 Closed Closed EICB (Darbali)

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

2. Attachment 7 contains the EDCR 52987 excerpt

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

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

5. Attachment 8 contains the EDCR 52601 (RVLIS) excerpt. The RVLIS EDCR has been split into two EDCRs. The second EDCR is

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55385. Submittal of EDCR 55385 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 118 due November 15, 2010.

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

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

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

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

095 7.8.1, XX May 20, 2010 Date: Closed Closed EICB (Darbali)

7.8.4 Responder

TVA to review SER supplements 5 and 14 item 7.8.1 Response is satisfactory. Item NRC Review and supplement 4 item 7.8.4 and confirm if they are Q1: Monitoring of the reactor coolant system relief closed.

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

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

096 7.7.5 XX 5/20/2010 Responder: Open Open EICB (Darbali)

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

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 safety-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:

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1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

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

097 7.4.2 7.4 May 20, 2010 Date: Closed Closed EICB (Darbali)

Responder:

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

leg temperature for applicability to Unit 2. 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 Licensing bases and this deviation is applicable to Unit 2.

098 7.4.2 7.4 May 25, 2010 Date: Closed Closed EICB (Darbali)

Responder:

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

address this change?

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

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

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

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 C B

(C 5/20/2010 Responder: WEC Closed Closed t

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

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

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

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

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

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

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

1000, Containment High Range Post Accident the listed documents were submitted to the NRC Radiation Monitor documents will be provided by June on TVA letter to the NRC dated July 15, 2010.

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 102 May 24, 2010 Date: 5/24/10 Closed Closed EICB (Carte)

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

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

Item 82 - no later than July 23, 2010 Item 83 - no later than July 23, 2010 103 7.4 7.4 EICB 5/27/2010 Responder: Clark Date: 5/27/10 Open Open Submittal date is based on current (Darbal EDCR scheduled issue date.

i) TVA to submit excerpts of EDCR 52321 EDCR is scheduled for issue Due 10/31/10 10/13/10 104 7.4 7.4 EICB 5/27/2010 Responder: Clark Date: 5/27/10 Open Open Submittal date is based on current (Darbal EDCR scheduled issue date.

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

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

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

(Cart Responder: Davies

)

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

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utilize the same processor (AC110 or AC160). Westinghouse Unit 2 Drawing 6D31420, Watts Responsibility:

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.

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

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

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

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

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

b. RISC 2006-17 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.

109. 5/6/2010 Responder: NA Open Open b EICB (Carte) The reviewer was unable to identify the sections of the TVA Provided response J. Wiebe accepted this action. NRC Action FSAR that correspond to the standard review plan sections7.9.

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

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

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

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

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

on the plant computer or annunciator systems and The annunciator system is not described in the Responsibility:

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

112 June 1, 2010 Date: Closed Closed EICB (Garg)

Responder: Clark What are the differences between the Unit 1 and Unit 2 Eagle 21 Systems? This information is included in TVA letter dated March 12, 2010, Enclosure 1, Item 10.

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

114 7.2 7.2 6/1/2010 Responder: WEC Open Open EICB (Garg)

Provide the resolution of the Eagle 21 Rack 5 lockup The following non-proprietary response was The write-up on update issue. developed from proprietary Westinghouse letter shows that there WBT-D-2027 (Reference 11), which provided the was differences resolution of this issue. Westinghouse approved between Unit 1 this non-proprietary response via e-mail from A. and 2 but was not Drake to M. Clark on June 15, 2010. identified to NRC in earlier As documented in WBT-D-1917, Eagle-21 Rack response. Are 5 LCP Diagnostic Failures, (Reference 14), there any more during the factory acceptance testing for the Unit surprises like 2 Eagle-21 System, Westinghouse noted an this?

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

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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 installed on the Unit 2 Rack 5 LCP, and the appropriate factory acceptance testing has been successfully conducted using this updated board. Additionally, the LCP boards in the balance of the Unit 2 racks have been updated with the 80287 XL coprocessor.

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

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

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

b. Or installed in unit 1 under 50.59, or The original design allowed printing from both the Please provide a list of ALL

c. Is unique to unit 2 Operator Module (OM) and Maintenance and Test digital communications paths Panel (MTP) via the plant computer. This to non-safety-related systems.

required both to be connected to the plant computer. Westinghouse did not perceive this as NNC 8/12/10: The staff pointed an issue, because the standard Common Q out this inconsistency to TVA.

PAMS design includes both the flat panel displays The staff could consider PAMS and individual control panel indicators. The Licensing Technical Report to Westinghouse Common Q team did not realize be a correction if TVA that WBN does not use the individual control specifically identified the panel indicators. As a result, the original design inconsistency to the staff, or documents provided by Westinghouse included identified where the error in the

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the connection from the OM to the plant SysRS, SRS, & SDS had computer. already been identified. This appears to be a feature in the The TVA team did not realize that the CQ TR appendix that was Westinghouse design relied on the OM and MTP carried forward to WBN2 to be qualified isolation devices that protected the PAMS inappropriately AC160 functions and individual control panel indicators from interference from the plant computer. It was not until a meeting was held with TVA, Westinghouse and Bechtel 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/Bechtel understood that the OM was being credited as the qualified isolation device. It became apparent at the meeting to both TVA/Bechtel and Westinghouse that the original design was not acceptable. The team then agreed to delete the OM connection to the plant computer.

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

the basis for deletion of the conformal coating. addressed. I think As previously stated the technical reason for the conformal coating coating was to ensure performance at high was credited to humidity, with the major concern being the effects protect against tin of humidity on low level analog circuitry. whisker issue.

Westinghouse letter (WBT-D-2036, TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 2, Basis for Removal of Conformal Coating Requirement on Eagle 21 Boards (Reference 7) does not credit the conformal coating as addressing the tin whisker issue.

As addressed in Resolution of Generic Safety Issues: Issue 200: Tin Whiskers (NUREG-0933, Main Report with Supplements 1-33),

CONCLUSION The low number of reported events associated with this issue, the lack of any increasing trend, the lack of any apparent decrease in reliability of systems or components due to tin whiskers, the existence of applicable regulatory requirements and programs (i.e., 10 CFR Part 21, the maintenance rule requirements, and the Reactor Oversight Program), and the issuance of

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Information Notice 2005-251878 to alert licensees collectively indicated that tin whiskers did not meet the requirements of NRC Management Directive 6.4. "Generic Issues Program," for further pursuit. Based on the considerations discussed above, RES recommended that the issue be returned to the originator to be evaluated for other possible options. As a result, the issue was DROPPED from further pursuit.1879 Based on the preceding NRC position no further discussion of the tin whisker issue is required.

117 7.1 7.1 6/3/2010 Responder: Webb/Powers Open Open EICB (Garg)

Does TVA use a single sided or double sided Reactor Protection System (RPS) (comprised of TVA needs to methodology for as-found and as-left instrument Reactor Trip (RPS) and Engineered Safety address that trip setpoint values. (RIS2006-7) Features Actuation System (ESFAS)) setpoint setpoint and values are monitored by periodic performance of allowable value surveillance tests in accordance with Technical uncertainties are Specification requirements. TVA uses double- not reduced by sided as-found and as-left tolerances for Reactor the reduction Trip and ESFAS trip setpoint surveillance tests as factor for the described in FSAR amendment 100. single sided reduction factor.

TVA response not acceptable. TVA need to clarify if single sided methodology has been used in calculating trip setpoint and allowable value and if it is used then provide justifications.

118 7.4 7.4 6/8/2010 Responder: Clark Open Open Submittal date is based on current EICB EDCR scheduled issue date.

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

119 June 10, 2010 Date: Closed Closed EICB (Singh)

Responder:

Submit the non-proprietary version of Sorrento/GA software V&V report version 1.1 04508005 and Provided 7/15/2010 Date: 07/29/10 withholding affidavit Responsibility: NRC TVA provided the non-proprietary version of V&V report version 1.1 04508005

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and the withholding affidavit via TVA letter dated July 15, 2010.

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

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

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

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

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

c. During this discussion, the reviewer asked if we had communications.

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

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

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

information on Foxboro IA). D. Webb/H. Webber

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

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

c. Identify the functions (ensure all control functions are addressed) that have been transferred to the Foxboro Spec 200 system that utilize a different platform in Unit 1.

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

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

123 7.7.3 7.4.1, 6/14/2010 Responder: Closed Closed EICB (Darbali) 9.3.4.2

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

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

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

an adverse control and protection system interaction.

(a single random failure in the VCT level control Upscale failure of LT-62-130A: Unlike Unit 1, the system could cause the letdown flow to be diverted to makeup control system uses inputs from both LT-the liquid holdup tank). Based on your responses to 62-130A and LT-62-129A. This results in a more the staffs questions related to this concern, the staff robust design that eliminates a single point of considered the issue resolved. Confirm that your failure for LT-62-130A. If transmitter LT-62-130A responses are applicable to Unit 2. 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.

124 7.7.5 XX 6/14/2010 Responder: Closed Closed EICB (Darbali)

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

1. In the original SE, Section 7.7.5, the staff determined that Information Notice 79-22 was resolved based on your statement that the control and logic

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functions of the Watts Bar plant were identical to the Sequoyah plant, thus making the Sequoyah evaluation applicable to Watts Bar. Confirm that your statements regarding the control and logic functions are applicable to Unit 2s control and logic functions or describe any changes and why they are acceptable.

125 7.7.8 7.7.1.1 6/14/2010 Responder: Closed Closed EICB (Darbali) 2 SE Section 7.7.8 AMSAC 1. The AMSAC system was not previously installed in Unit 2. EDCR 52408 installs the

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

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

that found that the AMSAC automatic initiation signal

[to start the turbine-driven and motor-driven AFW pumps] was not 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 7.8 7.8 June 14, 2010 Date: Closed Closed EICB (Darbali)

Responder:

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

1. In the SER Cross Reference To FSAR table (06 this change.

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?

127 7.2 7.2 6/16/2010 Responder: WEC/Clark Close Open EICB (Garg)

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

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

During the Watts Bar Unit 2 Eagle 21 Factory Acceptance Test (FAT) of Rack 2 it was discovered that the narrow range Resistance

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Temperature Detector (RTD) temperature inputs were consistently reading about 0.2 °F higher than expected. Investigation revealed that these inputs are configured in the Loop Calculation Processor software as a shared RTD. This is incorrect. Rack 2 RTD's are not shared. Racks 6, 10 and 13 RTD's are. Configuration as a shared RTD input alters the equation used for the temperature calculation. Watts Bar Unit 1 uses identical software to Unit 2.

Further investigation by Westinghouse showed this configuration error causes the Narrow Range Temperatures for only Division I to read 0.2 to 0.27 °F higher over the Narrow Range span of 510-650 °F. The 0.2 °F shift affects Thot and Tcold equally and thus will not affect the indication of Delta T. Tavg will indicate high by 0.2 °F which will decrease the Over temperature and Overpower set points; which is in the conservative direction.

128 7.2 7.2 6/18/2010 Responder: WEC Open Open TVA Unit 1 has to address first and EICB (Garg)

Unit 2 will follow Unit 1.

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

Due 12/3/10 129 6/12/2010 Responder: WEC Open Open DORL (Bailey)

TVA will provide non-proprietary versions of the The documents, and affidavits for withholding for Due 7/16/10 following Common Q attached proprietary documents the listed documents were submitted to the NRC and the affidavits for the proprietary documents by on TVA letter to the NRC dated July 14, 2010.

June 30, 2010.

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

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

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

131 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR FSAR Amendment 100 submitted to the NRC on FSAR AMD 100 3.10 references to eliminate (LATER) for document TVA letter to the NRC dated September 1, 2010 numbers. updated the reference document number information.

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132 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR FSAR Amendment 100 submitted to the NRC on FSAR AMD 100 3.10 to correct differences between the list on page TVA letter to the NRC dated September 1, 2010 3.10-4 and the numbering referenced by the text below corrected the numbering in the text.

the list.

133 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR FSAR Amendment 100 submitted to the NRC on FSAR AMD 100 3.10 to remove references to IEEE 344-1987. TVA letter to the NRC dated September 1, 2010 removed the reference to IEEE 344-1987.

134 6/28/2010 Responder: Clark Open Open DORL (Bailey) TVA committed to revise in Amendment 100: FSAR FSAR Amendment 100 submitted to the NRC on FSAR AMD 100 Table 1.3-3 to reflect modifications to WBN2 . TVA letter to the NRC dated September 1 2010 updated the table to reflect the WBN2 modifications.

135 7.3.1 7.3.1 6/30/2010 Responder: Clark Closed Closed EICB TVA committed to add in Amendment 100 a reference FSAR Amendment 100 submitted to the NRC on Amendment 100 received.

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

136 7.3.2, 7.4, 6/30/2010 Responder: Clark Closed Closed EICB (Darbali) 7.4 5.6, 6.3.5 TVA committed to replace in Amendment 100 the FSAR Amendment 100 submitted to the NRC on Amendment 100 received.

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

11.2.4.

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

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

(b) This table is showing a hierarchical (b) Please describe how this table is different than a relationship between documents. These reference list. documents are also in the reference list along with other documents that have no hierarchical (c) What does it mean for a document to be listed in relationship with the document.

this table?

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

138 6/17/2010 This item is used to track all Commercial Open Open EICB Grade Dedication issues.

(Carte) By letter dated February 3, 2010, Westinghouse TVA to provide informed TVA that certain PAMS documentation has This item will be updated with the results of date when

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been completed. the September 20 and 21 Commercial Grade information will be Dedication and SDS RTM audit. docketed.

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

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

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

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

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

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

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

Requirements Specification The WBN2 PAMS System Requirements Specification The table is to show the document hierarchy (i.e., TVA to provide (WBN2 PAMS SysRS) contains a table (see page iii) what documents are predecessors to the date when TVA docketed WNA-DS-01617-titled, Document Traceability & Compliance, which document in relationship to the design life cycle). information will be WBT Rev. 1, RRAS Watts Bar 2 states that the WBN2 PAMS SysRS was created to The table purpose is to provide references to docketed. NSSS Completion Program I&C support no documents. Please explain. internal Westinghouse documents and is not Projects Post Accident Monitoring intended to reference TVA documents. System- System Requirements Specification, dated December 2009.

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

Requirements Specification The first requirement in the WBN2 PAMS SysRS (i.e., WBN Unit 2 FSAR Amendment 100 Section TVA to provide R2.2-1) states: The PAMS shall be capable of 7.5.1.8 date when TVA docketed WNA-DS-01617-operation during normal and abnormal environments information will be WBT Rev. 1, RRAS Watts Bar 2 and plant operating modes. The rational for this docketed. NSSS Completion Program I&C requirement is that it is necessary to meet Regulatory Projects Post Accident Monitoring Guide (RG) 1.97. System- System Requirements Specification, dated December

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What document specifies which RG 1.97 variables are 2009.

implemented in the Common Q based WBN2 PAMS?

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

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

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

Requirements Specification The applicable regulatory guidance for reviewing the This item is used to track all traceability TVA to provide WBN2 PAMS SysRS would be IEEE 830 as endorsed issues with the Software Requirements date when TVA docketed WNA-DS-01617-by Regulatory Guide 1.172 and BTP 7-14 Section Specification (SRS). information will be WBT Rev. 1, RRAS Watts Bar 2 B.3.3.1, Requirements Activities - Software docketed. NSSS Completion Program I&C Requirements Specifications. IEEE 830-1994 Section At the September 15 public meeting in Rockville, Projects Post Accident Monitoring 4.3.8, Traceable, states: A [requirements the following actions were agreed to. These items System- System Requirements specification] is traceable of the origin of each of its address the traceability concerns with the Specification, dated December requirements is clear Software Requirements Specification. 2009.

1. How did TVA ensure the traceability of each 1. Westinghouse will perform completed a requirement in the WBN2 PAMS SysRS. review of the Requirements Traceability Matrix(RT), using the issues identified at the

2. Explain the source(s) of the requirements present 9/15 public meeting as a guide (documented in the Post Accident Monitoring Systems Software below) and update the RTM as required.

Requirements Specification. To clarify, many documents have requirements that are 2. The next issue of the IV&V report will include incorporated by reference into the SRS, but what the Requirements phase review of the RTM served to direct the author to include those and a partial review for the Design phase.

various documents in the SRS or, if the requirement is based on the System 3. Westinghouse will add a comments column in Requirements Specification, what directed the the Requirements Traceability Matrix (RTM) author to include the requirement there? to address items not in the SRS or SysRS.

3. Clarify whether the unnumbered paragraphs in the 4. IEEE 830 says you shouldnt have planning Post Accident Monitoring Systems Software information in the SRS. Westinghouse has Requirements Specification, such as in the section agreed to remove this information.

headings, or are all such sections simply considered to be informative? 5. IEEE 830 says you shouldnt have process requirements in the SRS. Westinghouse has Does the same apply to documents referenced by agreed to remove these requirements.

the SRS? Such as WCAP-16096-NP-A, Rev. 1A, Software Program Manual for Common Q 6. Westinghouse will perform and document an Systems, which is incorporated by reference in evaluation of the SRS to ensure compliance requirement R2.3-2 in the SRS. with Reg. Guide 1.172 and justify any deviations.

R2.3-2 [The PAMS software shall comply with

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the requirements and guidelines defined in WCAP- 7. 25 issues identified by V&V where some 16096-NP-A, Software Program Manual for requirements have not been included in the Common Q Systems (reference 5).] SDS (14) and SRS (11) at the revisions reviewed by V&V. Have these been If any requirements are expressed in such addressed? Yes. The next revisions of the unnumbered paragraph form instead of individually SDS and SRS address these issues.

identified requirements, please list them, describe why they satisfy the fundamental requirement of 8. Some hardware requirements are contained unambiguity, and describe how they were verified. in the SRS instead of the System Design Specification (SDS). These will be removed

4. Are there any sources of requirements in parallel from the SRS and incorporated into the next with the Post Accident Monitoring Systems revision of the SDS.

Software Requirements Specification? Meaning does the SRS contain, explicitly or by reference, 9. RTM item R4.2-2 protection class software all the requirements that were used in the design set to 0. Needs to be fixed internally write phase for the application specific software, or do CAPs to revise the application restrictions software design phase activities use requirements document on AC160.

found in any other source or document? If so, what are these sources or documents? 10. Westinghouse to improve the traceability of the tests that are performed with the function

5. References 12, 27, 29, and 31-44 in the Post enable (FE) switch in the ENABLE position.

Accident Monitoring Systems Software Requirements Specification are various types of 11. Westinghouse to revise documents to be Reusable Software Element. consistent with referring to the FE switch in the ENABLE position These references are used in the body of the SRS, for example: 12. The flow of information is from the SysRS to the SDS (hardware) and SRS (software).

R5.3.14-2 [The Addressable Constants CRC error Describe how the documents are used.

signal shall be TRUE when any CAL CRC's Describe in 1.1 of the SysRS. Need a good respective ERROR terminal = TRUE (WNA-DS- write up of how the process works.

00315-GEN, "Reusable Software Element Document CRC for Calibration Data" [Reference 13. Westinghouse and TVA will develop a revised 12]).] schedule for document submittals and provide it to the NRC no later than 9/30/10 They are also included via tables such as found in requirement R7.1.2-1 14. TVA will update the Procurement Requisition Resolution Matrix and submit it to show how

[The Watts Bar 2 PAMS shall use the application- the Common Q PAMS design meets the specific type circuits and custom PC elements contract requirements.

listed in Table 7.1-1.]

15. Westinghouse to add the Software Design Do the referenced reusable software element Descriptions to the RTM documents include requirements not explicitly stated in the SRS? If so what is their origin? 16. Westinghouse to clarify how requirements or documents are incorporated by reference into the Common Q PAMS requirements.

17. Westinghouse to review the use of shall outside of numbered paragraphs in requirements documents to ensure that all

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requirements are captured and clearly identified.

18. Westinghouse to resolve the following questions concerning SDDs

a. Is the SDD a standalone document or will it incorporate the generic SDD by reference?

b. What are the SDDs?

c. PAMS is a delta document so how do we capture all the generic requirements for traceability.

For Reusable Software Elements, Westinghouse to describe as qualified libraries by following the SPM and qualified using the Software Elements Test procedure under Appendix B program.

Provide a summary of RSEDs generic WCAP.

Westinghouse to determine if the WCAP was docketed under the AP1000 RSED concept is not in the SPM. WCAP-15927 AP-1000 does not discuss RCEDs. WCAP process was acceptable.

RSEDs are listed in the SDD References.

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

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

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

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

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

The WBN2 PAMS System Design Specification (WBN2 PAMS SDS) contains a table (see page iii)

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

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

144 6/17/2010 Responder: WEC Open Open WBN2 PAMS Software EICB (Carte)

Requirements Specification The WBN2 PAMS Software Requirements (a) The purpose of NABU-DP-00014-GEN NRC Review and WEC to Responses to Specification (WBN2 PAMS SRS) contains a table document is to define the process for system level complete response. items a and e By letter dated April 8, 2010 (see page iii) titled, Document Traceability & design, software design and implementation, and provided. Need (ML10101050203), TVA docketed Compliance, which states that the WBN2 PAMS SRS hardware design and implementation for Common b-d to be addressed at public response to b-d. WNA-SD-00239-WBT, Revision 1, was created to support the three documents identified Q safety system development. This document meeting and audit. Will require "RRAS Watts Bar 2 NSSS (two of these documents have been provided on the supplements the Common Q SPM, WCAP-16096- information to be docketed. Completion Program I&C Projects, docket). NP-A. The scope of NABU-DP-00014-GEN Software Requirements includes the design and implementation Specification for the Post Accident (a) Please describe the third document (i.e., NABU- processes for the application development. For a Monitoring System, dated DP-00014-GEN Revision 2, Design Process for fuller description of the design process described February 2010 (ML101050202).

Common Q Safety Systems). in NABU-DP-00014-GEN please refer to the Design Process for AP1000 Common Q Safety (b) Please describe the flow of information between Systems, WCAP-15927 on the AP1000 docket.

these three documents. Since this is a Westinghouse process document that is not specifically referenced in the SRS, it (c) Does the PAMS SRS implement the requirements will be removed in the next revision of the in these three documents? document.

(d) Please describe if and how these three documents (b) - Closed to items 142 and 145 are used in the development of the PAMS Software Design Description. (c) - Closed 142 (e) Do the WBN2 V&V activities include verification (d) - Closed to Item 142 that the requirements of these three documents have been incorporated into the WBN2 PAMS SRS. (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

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(WNA-DS-01667-WBT, Rev. 1).

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

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

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

Specification The WBN2 PAMS System Design Specification This item is used to track all traceability TVA to provide (WBN2 PAMS SDS) contains a table (see page iii) issues with the System Design Specification date when TVA docketed WNA-DS-01667-titled, Document Traceability & Compliance, which (SDS). information will be WBT Rev. 1, RRAS Watts Bar 2 states that the WBN2 PAMS SDS was created to docketed. NSSS Completion Program I&C support the WBN2 PAMS SysRS. At the September 15 public meeting in Projects Post Accident Monitoring Rockville, the following actions were agreed System- System Design (a) Does the WBN2 PAMS SDS implement all of the to. These items partially address the Specification, dated December hardware requirements in the WBN2 PAMS SysRS? traceability concerns with the System Design 2009.

Specification. This item will be updated with (b) Please briefly describe all of the documents that the results of the September 20 and 21 implement the hardware requirements of the WBN2 Commercial Grade Dedication and SDS RTM PAMS SysRS. audit.

1. Westinghouse will perform completed a review of the Requirements Traceability Matrix(RT), using the issues identified at the 9/15 public meeting as a guide (documented below) and update the RTM as required.

2. Some hardware requirements are contained in the SRS instead of the System Design Specification (SDS). These will be removed from the SRS and incorporated into the next revision of the SDS.

3. 25 issues identified by V&V where some

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requirements have not been included in the SDS (14) and SRS (11) at the revisions reviewed by V&V. Have these been addressed? Yes. The next revisions of the SDS and SRS address these issues.

4. TVA will update the Procurement Requisition Resolution Matrix and submit it to show how the Common Q PAMS design meets the contract requirements.

5. The next issue of the IV&V report will include the Requirements phase review of the RTM and a partial review for the Design phase.

6. Westinghouse to provide the generic AC160 and flat panel specifications.

7. Westinghouse and TVA to develop a schedule of licensing document submittals that can be met by the project team.

8. The flow of information is from the SysRS to the SDS (hardware) and SRS (software).

Describe how the documents are used.

Describe in 1.1 of the SysRS. Need a good write up of how the process works.

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

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

References:

00000-ICE-30156 Rev.

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

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

References:

00000-ICE-30156 Rev.

6, System Requirements Specification for the Common Q

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

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

References:

00000-ICE-30156 Rev.

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

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

Additional changes were made in FSAR amendments 98 and 99 to correct typographical errors found during FSAR review.

150 7.2 7.2 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System Many of the changes were based on the System description N3-99-4003, Reactor TVA to provide Westinghouse document N3-99-4003. Provide this Protection System is contained in Attachment 3. date when document for staffs review so the staff can determine information will be the basis for these changes. docketed.

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

System Provide the EDCR 52378 and 54504 which discusses EDCR 54504 has been voided and replaced with TVA to provide the basis for many changes to this FSAR section. EDCR 52378 which is contained in Attachment 4 date when and EDCR 52671 is contained in Attachment 5. information will be docketed.

152 7.2 7.2 6/25/2010 Responder: Merten/Clark Open Open FSAR Section 7.2, Reactor Trip EICB System (Garg) Deleted portion of FSAR section 7.2.3.3.4 and moved The text was revised to match the Unit 1 UFSAR. TVA to confirm if to FSAR section 7.2.1.1.5. However, the FSAR The Unit 1 text was modified in Amendment 1 by this description is

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section 7.2.1.1.5 does not include the discussion of FSAR Change Package 1553 S00 which is the same as for ambient temperature and also on the calibration of the contained in Attachment 30. The basis for the Unit 1. If it is sealed reference leg system. No justification was change in the change package is: same as Unit 1 provided for deleting this discussion. Please explain then why this was the bases for deletion of this information. 16 The update to Section 7.2.1.1.5 is taken from shown as change text in Section 7.2.2.3.4 with clarifications and in redline version editorial changes. The relocated discussion of the of FSAR pressurizer water level instrumentation Is more Amendment 96.

appropriately included in this section than Section 7.2.2.3.4, which deals with control and protection TVA to provide system interaction. The changes to 7.2.1.1.5 are date when based on a general description of the information will be Westinghouse pressurizer level design, channel docketed. When independence, and actual installation attributes Unit 1 UFSAR found on TVA physical drawings. Also, the was revised.

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

The Westinghouse Owners Group response to this issue is found in RIMS # L44930216800. The channel error value discrepancy is documented in WBPER980417. The remaining text in 7.2.2.3.4 is revised to clarify the control and protection system interaction discussion.

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

System FSAR section 7.2.1.1.7 added the reference to FSAR EDC E50952-A added an alternate method of TVA will send section 10.4.4.3 for exception to P-12. However, RCS cooldown using additional steam dump 50.59.

FSAR section 10.4.4.3 states bypass condition is not valves after entering Mode 4, by disabling the P-displayed and it is not automatically removed when 12 Interlock. Operators use additional condenser TVA to provide conditions for bypass are no longer met. Provide the dump valves to aid in maintaining a cooldown rate date when basis for this. closer to the administrative limit established by information will be operating procedure. docketed. TVA did not address Refer to Unit 1 UFSAR Amendment 3 Change why bypass Package 1676 S00 (Attachment 6) for the safety condition is not

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evaluation and basis for this change. displayed.

The 50.59 for the change is included in the Change Package.

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

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

issued RIS 2006-17 to provide guidance to the Matrix Item 51. Since all the industry regarding the instrument setpoint setpoint and methodology which complies with 10 CFR 50.36 (Q2) EEB-TI-28's single sided methodology allowable value requirements. Provide the information on how the conforms with WBN's design basis commitment to for Unit 2 is WBN2 setpoint methodology meets the guidance of ensure that 95% of the analyzed population is calculated and RIS 2006-17 and include this discussion in this covered by the calculated tolerance limits as added to TS, TVA section. Also, by letter dated May 13, 2010, TVA defined in NRC Reg Guide 1.105, Revision 2, needs to address provided Rev. 7 of EEB-TI-28 to the staff. The staff 1986 that was in affect during WBN Unit 1 the latest criteria noted that section 4.3.3.6 of EEB-TI-28 discusses the licensing. The single sided methodology is not and that include correction for setpoints with a single side of interest. It used for any TSTF-493 setpoints that use TI-28 95/95 criteria.

should be noted that the staff has not approved this methodology. Why the last aspect of setpoint methodology for Unit 1. The staff sentence has finds this reduction in uncertainties is not justified been modified by unless it can be demonstrated that the 95/95 criteria is adding TI-28. It met. Therefore, either remove this reduction factor for was NRCs single sided uncertainties or justify how you meet the understanding 95/95 criteria given in RG 1.105. that all setpoints have to meet TI-28 155 7.2 7.2 June 25, 2010 Date: Closed Closed FSAR Section 7.2, Reactor Trip EICB (Garg)

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

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

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

from 118%. The justification for this change states Units I and 2 118% vs. 121 % and Correction to docketed that this was done to bring the text of this section in RAI Response SNPB 4.3.2-7, (Reference 17) the agreement with section 4.3.2.2.5, 4.4.2.2.6 and table 118% value should be 121%. Depending on the 4.1-1. However, Table 4.1-1 and section 4.3.2.2.5 still use in the FSAR either 118% or 121% are the show this value as 118%. Justify the change. 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 incorporated in a future FSAR

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

amendment.

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

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

158 7.2 7.2 6/25/2010 Responder: Tindell Open Open EICB (Garg)

FSAR section 7.2.2.1.1, paragraph six was changed to FSAR Amendment 99 reflects the change to TVA to provide state that the design meets the requirements of Criterion 23. date when Criterion 23 of the 1971 GDC instead of the Criterion information will be 21 of the GDC. The Criterion 21 is about protection docketed system reliability and testability, while Criterion 23 is about 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 7.2 7.2 6/25/2010 Responder: Craig Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.1.2 discusses reactor coolant flow For the purposes of measuring reactor coolant TVA to provide measurement by elbow taps. However, it further flow for Reactor Protection functions, elbow taps date when states that for Unit 2, precision calorimetric flow are used for both Unit 1 and 2. The discussion information will be measurement methodology will be used. If elbow taps and equation are valid for establishing the docketed are not used for Unit 2, then why does this section nominal full power flow which is used to establish discuss this methodology? It is the staffs the Reactor Protection System low flow trip understanding that TVA plans to use elbow taps setpoint. However the method used to verify methodology in the future for Unit 2. Please revise this reactor coolant flow, as required by the Technical section to describe the current plant Specifications, is not the same. Unit 1 uses a design/methodology. 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. The plan is for Unit 2 to transition to this method after sufficient data is obtained. Pending this transaction, 7.2.2.1.2 will be revised as follows:

From:

Nominal full power flow is established at the geginning of each fuel cycle by either elbow tap methodology or, performance of the RCS calorimetric flow measurement, (For Unit 1 elbow tap methodology is implemented for RCS flow measurement (Reference [17]) and Unit 2 may implement elbow tap methodology at a future

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date) the results of which are used to normalize the RCS flow indicators. This provides a reference point for the low flow reactor trip setpoint, and also provides a relatively simple method for periodic verification of the thermal design flow assumed in the safety analysis, as required by the Technical Specifications. Accuracy and repeatability of the flow measurement instrumentation are considered in establishment of the low flow setpoint and the minimum required flow and are adequate for these functions. This is for Unit 1 only. For Unit 2, the precision calorimetric flow measurement methodology will be used.

To:

Nominal full power flow is established at the beginning of each fuel cycle by either elbow tap methodology or, performance of the RCS calorimetric flow measurement. Unit 1 utilizes elbow tap methodology Reference [17]. Unit 2 utilizes the RCS calorimetric flow measurement.

The results are used to normalize the RCS flow indicators and provide a reference point for the low flow reactor trip setpoint.

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

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

utilizing 2/4 logic for the trip function or by providing a diverse trip. Provide any exception to this and their 23. (page 7.2-24): Portions of the discussion of basis for acceptability. control and protection system interaction are revised to clarify the requirement. The discussion of how the SG low-low water level protective function and the control system Median Signal Selector satisfy this requirement is deleted since it Is redundant to the information provided In Section 7.2.2.3.5. Reactor Protection System Description N3-99-4003 is also revised to move and clarify the discussion of the requirements for control and protection system Interaction from Section 3.1.1.2 to Section 2.2.11, where the Issue is also discussed.

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

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Foxboro IA design is complete. Provide the schedule docketed for the completion of the design and when this information will be available to the staff for review and approval.

162 7.2 7.2 6/25/2010 Responder: Tindell Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.2(14) states that bypass of a The Bypassed and Inoperable Status Indication TVA to provide protection channel during testing is indicated by an System (BISI) compliance with Reg. Guide 1.47 is date when alarm in the control room. Explain how this meets RG described in detail in FSAR Section 7.5.2.2. information will be 1.47. docketed 163 June 25, 2010 Date: Closed Closed FSAR Section 7.2, Reactor Trip EICB (Garg)

Responder: System deleted 164 7.2 7.2 6/25/2010 Responder: Perkins Open Open FSAR Section 7.2, Reactor Trip EICB (GarglMarcus) 7.5.1. System 1 FSAR section 7.2.2.2(20) has been revised to include The primary purpose of the plant computer is to TVA to provide the plant computer as a means to provide information present plant process and equipment status date when read out for all signals which can cause a reactor trip. information to the control room operators to assist information will be Justify the use of the plant computer for this function. them in the normal operations of the unit, and docketed Include the discussion on the effect of plant computer inform them of any abnormal conditions. The plant failure on the system functions. computer obtains real-time plant parameter information via Data Acquisition Systems(DAS)(multiplexers, etc.) by scanning preassigned analog, pulse, and contact sensors located throughout the plant. The computer is not defined as being primary safety-related and it is not required to meet the single failure criterion or be qualified to IEEE criteria for Class 1E equipment.

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

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

• Any software associated with the computer and the DAS must meet the quality requirements of plant procedure SPP-2.6, Computer Software Control which is based on requirements in

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NUREG/CR-4640, the Watts Bar Nuclear Quality Assurance Plan, and SS-E18.15.01 - Software Requirements for Real-Time Data Acquisition and Control Computer Systems, which complies with IEEE Std. 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations.

The computer software is controlled by a Software Quality Assurance Plan.

• One of the requirements in 10 CFR 50, Appendix A states that Appropriate controls shall be provided to maintain variables monitored and systems within prescribed operating ranges.

Periodic maintenance and calibration will be performed on the computer and DAS. In addition, calibration procedures for instrumentation which is used for input to the computer include verification of the computer input signal at the DAS and as displayed on the display stations.

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

computer accuracy, 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

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

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

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

System Changes to FSAR section 7.2.2.2(20) are justified EDCR 52322 is contained in Attachment . TVA to provide based on the statement that the integrated computer date when system is implemented through EDCR 52322. Provide information will be a copy of EDCR 52322 for staff review. docketed 167 7.2 7.2 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR section 7.2.2.4, provide an analysis or reference Continuous rod withdrawal events are analyzed in TVA to provide to chapter 15 analysis which demonstrate that failure FSAR sections 15.2.1 and 15.2.2. While the rod date when of rod stop during a rod withdrawal event will not affect stops a mentioned, they are not credited in the information will be the safety limit. analysis. docketed 168 7.2 7.2 6/25/2010 Responder: Clark Open Open FSAR Section 7.2, Reactor Trip EICB (Garg)

System FSAR table 7.2-4, item 9 deleted loss of offsite power This change is in accordance with the Unit 1 TVA to provide to station auxiliaries (station blackout) based on the UFSAR. The change was made by FSAR date when fact that station blackout is not listed in AAPC events. Change Package 1553 S00 (Attachment 30). The information will be Explain what are AAPC events and how it justifies justification for the change is: docketed deleting this accident from the list.

38 (Table 7.2-4): This table lists the reactor trips and the various accident analyses for which each trip could provide protection. The intent of the table is to demonstrate the diversity of and comprehensive protection provided by the reactor trip system against various postulated events and

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to correlate the trip functions with the analyses in which they may be utilized, either as a primary or secondary protective function. Chapter 15, along with the Accident Analysis Parameters Checklist, WB-OC-40-70, provides the accident analysis discussion and identifies the protection system functions which provide accident mitigation. The additions and deletions to the table are made for consistency with the safety analyses of record as reflected in the design and licensing basis and do not represent analysis changes or protection system changes. Therefore. they are considered to be non-significant as discussed at the beginning of this section. Neutron Monitoring System Description N3-85-4003 Table 2 is also revised for consistency with WB-DC-40-70.

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

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

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

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

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

171 7.2 7.2 6/17/2010 Responder: Craig Open Open EICB (Garg)

An external unidirectional communications interface This item requires further discussion. It has been TVA to provide was installed between the Eagle 21 test subsystem deleted from the current letter. date when and the plant process computer. TVA should confirm information will be that testing has demonstrated that two way docketed communication is impossible with the described configuration. (Open Item # 3 of Eagle 21 audit) 172 6/17/2010 Responder: Craig Closed Closed EICB (Garg)

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

update. TVA should identify the cause and fix for the problem encountered. (Open Item # 1 of Eagle 21 audit) 173 7.1 7.1 EIC 6/17/2010 Responder: Craig/Webb/Powers Open Open B

(Gar

)

EEB-TI-28 discusses the correction for setpoints with a TVA to provide

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single side of interest. The staff finds this correction date when factor is not justified. TVA should justify this correction information will be factor and demonstrate that, with this correction, factor docketed 95/95 criteria identified in RG 1.105 is met.

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

Placeholder: The staff has identified questions Duplicate of 171 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.

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

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

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

176 7.1 7.1 6/28/2010 Responder: Craig/Webb Open Open EICB (Garg)

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

177 7.5.2. 7.5.1 7/15/2010 Responder: Clark Closed Closed EICB (Marcus) 1 FSAR Amendment 99 Section 7.5.1.2 states: "Type A The type A variables are the same in Unit 1 and August 19, 2010 - TVA to 09/16/10 Variables Those variables that provide primary Unit 2. See calculation WBNOSG4047 Rev. 4 submit calculation.

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

preplanned manually controlled actions for which no Review of Unit 2 FSAR automatic action is provided and that are required for confirms Unit 1 and Unit 2 safety systems to accomplish their safety functions for Type A variables are the Chapter 15 design basis events. Primary information is same.

information that is essential for the direct accomplishment of specified safety functions." Not necessary to docket WBNOSG4047.

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

178 7.5.2. 7.5.1 7/15/2010 Responder: Clark Closed Closed 1 EICB Please provide WBN-OSG4-047, "PAM Type A See response to item 177 above. August 19, 2010 - TVA to 09/16/10 (Marcus) Variable Determination." submit calculation.

Review of Unit 2 FSAR

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confirms Unit 1 and Unit 2 Type A variables are the same.

Not necessary to docket WBOSG4047.

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

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

NRC use of the word should regarding backwards traceability to say Each identifiable requirement in an Closed to Item 142.

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 (and particularly backward traceability) for each requirement. If requirements are not traceable, please explain how the SRS complies with the regulations that underlie the SRP.

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

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

Clarify whether the WBU2 Post Accident Monitoring Closed to Item 142.

Systems Software Requirements Specification adheres to IEEE std 830-1993 as modified by Regulatory Guide 1.172?

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

If no then please provide an evaluation that includes an identification and description of all differences proposed from the acceptance criteria given in SRP ,

BTP 7-14, Section B.3.3.1. Please describe how the alternatives provide an acceptable method of complying with those regulations that underlie the corresponding SRP acceptance criteria.

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

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

NRC use of the word should to say Each identifiable requirement in an SRS must be traceable backwards Closed to Item 142.

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

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

Characteristics that the SRP states that an Software Steve Clark to look at how to combine traceability TVA to provide Requirements Specifications should have include items. date when unambiguity, verifiability, and style, part of the latter is information will be that Each requirement should be uniquely and Will be addressed to during the 9/15 meeting and docketed completely defined in a single location in the SRS. 9/20 - 9/21 audit.

Clarify whether the unnumbered paragraphs in the Closed to Item 142.

Post Accident Monitoring Systems Software Requirements Specification, such as in the section headings, or are all 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.

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

An emphasis is placed on traceability in System The generic Software Requirements Specification October letter Requirements Specifications in the SRP, in the applies except as modified by the WBN Unit 2 unmodified IEEE std 830-1993, and even more so System Requirements Specification.

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 Systems Software Requirements Specification in the background section, is the sentence Those sections of the above references that require modification from the generic PAMS are defined in the document referring purely to the changes from WNA-DS-01617-WBT Post Accident Monitoring System-System Requirements Specification or is it saying that there are additional changes beyond those and that the SRS defines them?

If there are additional changes, what is their origin?

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

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

access to all the requirements.

Closed to Item 142.

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

185 7/15/2010 Responder: WEC Open Open EICB (Halverson)

An emphasis is placed on the traceability of Steve Clark to look at how to combine traceability TVA to provide requirements in Software Requirements Specifications items. date when in the SRP, in the unmodified IEEE std 830-1993, and information will be even more so given the modifications to the standard Will be addressed to during the 9/15 meeting and docketed.

listed in Regulatory Guide 1.172, which breaks with 9/20 - 9/21 audit.

typical NRC use of the word should to say Each identifiable requirement in an SRS must be traceable

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

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

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

R5.3.14-2 [The Addressable Constants CRC error signal shall be TRUE when any CAL CRC's respective ERROR terminal = TRUE (WNA-DS-00315-GEN, "Reusable Software Element Document CRC for Calibration Data" [Reference 12]).]

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

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

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

186 7.7.8 7.7.1.1 7/15/2010 Responder: Perkins/Clark Open Open EICB (Darbali) 2 Along with Amendment 96, TVA submitted a list of No. The previous wording reflected operation of Response is satisfactory. Issue Once FSAR Bechtel changes for each section. Change number 45 the computer based AMSAC system. The change date of Amendment 101 is not Amendment 101 addresses a change to section 7.7.1.12, AMSAC, reflects the operation of the relay logic based yet determined. is received, the however, the Justification column states This change system that replaced the original computer based item will be is not included. EDCR 52408 installs the AMSAC in system in Unit 1. Unit 2 is installing a similar relay Open closed.

Unit 2. It does not have a trouble alarms. The existing logic based system, so the change to the Unit 1 words better reflect the operation of the system. wording is applicable to Unit 2. Response is acceptable awaiting FSAR amendment Even thought this change was not included in EDCR 52408 Summary submittal.

Amendment 96, will it be included in a future amendment? A Purchase Order was issued to Nutherm International to provide a Unit 2 cabinet with the Also, please submit a summary of EDCR 52408. 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.

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In the Main Control Room, three cables will be installed for the AMSAC handswitch on 2-M-3 and AMSAC NOT ARMED and AMSAC ACTUATED annunciator windows.

In the Turbine Building, two pressure transmitters will be installed in two local panels to sense turbine pressure. 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.

In the Control Building, three cables will be routed to separation relays which will provide the start signal for the Motor Driven Auxiliary Feedwater Pumps, Turbine Driven Auxiliary Feedwater Pump, and initiate a Turbine Trip. Additionally, a cable will be routed to Unit 2 ICS for AMSAC NOT ARMED and AMSAC ACTUATED log points.

This EDCR is intended to configure Unit 2 AMSAC like Unit 1 when possible.

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

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

1) Enclosure 1, Item No. 33 of the TVA letter dated This required both to be connected to the plant Does TVA check that the CQ June 18, 2010, did not identify any connection from the computer. Westinghouse did not perceive this as PAMS system meets the PAMS Operator Modules (OMs) to the plant computer an issue, because the standard Common Q requirements in its purchase and printers; however, Figure 2.1-1 of the PAMS PAMS design includes both the flat panel displays specifications?

System Requirements Specification (WNA-DS-01617- and individual control panel indicators. The WBT Rev. 1 - ML101680578) shows a TCP Westinghouse Common Q team did not realize connection from the OMs to the plant computer and that WBN does not use the individual control printer. Please explain. panel indicators. As a result, the original design documents provided by Westinghouse included

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

path to non-safety-related systems or with safety related systems in another division. If so, NRC staff The TVA team did not realize that the will need these paths identified on the docket. 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

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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 to delete the OM connection to the plant computer.

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

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

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

Licensing Technical Report, (Document Number This required both to be connected to the plant WNA-LI-00058-WBT- P, Revision 0, June 2010) computer. Westinghouse did not perceive this as (Westinghouse Proprietary Class 2). an issue, because the standard Common Q PAMS design includes both the flat panel displays

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

explain.

The TVA team did not realize that the

2) Section 5.3, Response to individual criteria in Westinghouse design relied on the OM and MTP DI&C-ISG-04, of the PAMS Licensing Topical Report to be qualified isolation devices that protected the does not address the TCP connection between the AC160 functions and individual control panel OM and non-safety components depicted in Figure indicators from interference from the plant 2.1-1 of the PAMS System Requirements Specification computer. It was not until a meeting was held to (WNA-DS-01617-WBT Rev. 1 - ML101680578). discuss the design of the OM that the issues Please explain. 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 to delete the OM connection to the plant computer.

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

189 7.6.7EIC B 7/20/2010 Responder: Clark Closed Closed (Sin h)

FSAR Section 7.6.7States: Conformance with This is a typographical error. The correct NNC 8/25/10: Acceptable By FSAR

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Regulatory Guide 1.133, Revision 1 is discussed in reference is Table 7.1-1. The reference will be response. Amendment 100, Table 7.1-7. FSAR Chapter 7 does not contain any corrected in FSAR Amendment 100. page 7.6-4.

such numbered table. Please explain.

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

FSAR Table 7.1-1 states: Regulatory Guide 1.133, 1) TSR 3.3.6.3 specifies 18 months as the TVA to revise May 1981 Loose-Part Detection Program for the calibration frequency. response to Primary System of Light-Water Cooled Reactors, indicate proper Revision 1 (See Note 12)Note 12 Conforms except 2) Per the Technical Requirements Manual (TRM) reference as noted belowPositi[o]ns C.3.a.(3) and C.5.c. Bases 3.3.6 (Attachment 9) the surveillance documents for recommend a channel calibration be performed at requirements and frequency are provided in Attachment 9.

least once pe[r] 18 months. In lieu of this Regulatory Guide 1.133, "Loose-Part Detection recommendation, the DMIMS will be calibrated at the Program for the Primary System of Light-Water-frequency stated in subsection TSR 3.3.6.3 of TR Cooled Reactors."

3.3.6 (Loose-Part Detection System).

3) TRM section 3.3.6 and its bases are contained

1) Clarify what frequency is specified in TSR 3.3.6.3. in Attachment 9.

2) Please explain why the stated calibration frequency is adequate for meeting regulatory requirements.

3) Please provide sufficient documentation for the NRC to independently evaluate the conformance claims stated in the FSAR.

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

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

data communication systems. The WBN2 FSAR did as described in Attachment 34 (Data not include any description of data communications Communications Systems Description and systems. Regulatory Compliance Analysis).

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.

192 7.5.1. 7.5.2 7/20/2010 Responder: Clark Open Open EICB (Marcus) 1 The NRC Staff is using SRP (NUREG-0800) Chapter 7 1. At WBN Unit 1 and 2, there is a single August 19, 2010 - NRC to NRC to review Section 7.5, Instrumentation Systems Important to computer system named the Integrated review TVA response. response.

Safety, to review the WBU2 FSAR Section 7.5, Computer System or ICS. That system is Instrumentation Systems Important to Safety. The sometimes described as the Plant Computer following requests are for information that the SRP System, the Process Computer, the Technical directs the reviewers to evaluate. Support Center Data System (TSCDS) or the Emergency Response Facility Data System The role of the EICB Technical reviewer is to (ERFDS). At one time, the TSCDS and ERFDS determine if there is reasonable assurance that the were separate computers on Unit 1 but their equipment will perform the required functions. The functions were all incorporated into the ICS when WBU2 FSAR, Section 7.5.2, Plant Computer System, it was installed.

does not contain any description of the equipment that

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performs the functions described in the section. 2. The Watts Nuclear Plant ICS is a non-safety Enclosure 1 Item 3 of letter dated March 12, 2010, related system, is designed as a single, large-TVA stated that the platform of the Process scale nuclear plant computer system which Computer was, Hewlett Packard RX2660 and Dell integrates balance of plant (BOP) monitoring with Poweredge R200 servers with RTP Corp 8707 I/O. In extensive nuclear steam supply system (NSSS) addition TVA provided (a) two pages of marketing application software into a comprehensive literature by DELL on the Poweredge R200 Server, (b) computer based tool for plant operations. The the HP Integrity rx2660 Server Unser Service Guide, system is comprised of the following major and (c) the Integrated Computer System Network components:

Configuration Connection Diagram (2-45W2697-1-1

• Remote multiplexers in the Computer Room, dated 8/27/09). This provided information is not Auxiliary Instrument Room and 480V Board sufficient for evaluating whether the equipment will, rooms.

with reasonable assurance, perform the functions

• Redundant Central Processing Units (CPUs) described in the FSAR.

• Data Storage Devices

• Man-Machine Interfaces (MMI) - Satellite

1) Is the Plant Computer System another name for Display Stations (SDS) terminals in the Main the Process Computer? Control Room (MCR), Technical Support Center (TSC) and Computer Room.

2) Please provide an architectural description of the

• Networking equipment including switches, Plant Computer System. firewalls and terminal servers

• Printers

3) Please describe the relationship between the Plant

• Data Links to other plant computer devices Computer System and the Integrated Computer (serial and network)- These systems or devices System. include but are not limited to:

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

In support of normal plant operations, each units ICS:

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

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

• Performs data validity checking.

• Performs calculations to obtain parameters such

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as difference, flows, and rates.

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

• Displays alarms received from the digital Annunciator system.

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

• Performs BOP and NSSS related calculations.

• Provides graphical and digital trending displays of plant data.

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

In support of emergency plant operations each units ICS:

• Provides plant emergency support with the Safety Parameter Display System (SPDS) functions based upon the Westinghouse Owners Group CSF status trees and historical data collection, storage, and 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 7.5.1. 7.5.2 7/20/2010 Responder: Clark Open Open EICB (Marcus) 1 The WBU2 FSAR, Section 7.5.2, Plant Computer There is a single set of hardware that incorporates TVA to respond or System, contains three subsections, the functionality of Safety Parameter Display provide proposed 7.5.2.1, Safety Parameter Display System System (SPDS), Bypass and Inoperable Status date of response.

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

7.5.2.3, Technical Support Center and Nuclear Data Links Also refer to the response to item 59 (RAI Matrix Item 193).

Are there three separate sets of hardware that implement these functions, or are these three The function of the Nuclear Data Links or functions that are implemented on a single set of Emergency Response Data System (ERDS) is hardware? actually provided by the TVA Central Emergency

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Control Center (CECC) which acts as the Emergency Offsite Facility (EOF) for all of TVAs nuclear units. Plant data will be sent on a periodic basis from the ICS to the CECC via the Plant Engineering Data System (PEDS). That data is then available to be sent from the CECC to the NRC.

194 7.5.1. 7.5.2.1 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus) 1.1 The WBU2 FSAR Section 7.5.2.1, Safety Parameter The principal purpose and function of the SPDS is TVA to respond or Display System, contains a description of the Safety to aid control room personnel during abnormal provide proposed Parameter Display System. and emergency conditions in determining the date of response.

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

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

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

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• 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 7.5.1. 7.5.2.2 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus) 1.2 Bypassed and Inoperable Status Indication (BISI) The BISI system is a computer based system that TVA to respond or provides automatic indication and annunciation of provide proposed The WBU2 FSAR Section 7.5.2.2, Bypassed and the abnormal status of each ESFAS actuated date of response.

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

Indication System (BISI).

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

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

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provide assurance that the BISI system will perform its intended function correctly.

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

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

• Changes to BISI software from remote locations is prohibited.

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

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

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

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

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

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

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

196 7.5.1. 7.5.2.2 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus) 1.2 Bypassed and Inoperable Status Indication (BISI) Section C of the Regulatory Guide lists the TVA to respond or following six regulatory positions for guidance to provide proposed The NRC staff is performing its review in accordance satisfy the NRC requirements with respect to the date of response.

with LIC-110, Rev. 1, Watts Bar Unit 2 License bypassed and inoperable status indication(BISI)

Application Review. LIC-110 directs the staff to for nuclear power plant safety systems:

review systems unique to Unit 2 in accordance with current staff guidance. Regulatory Guide (RG) 1.47 1. Administrative procedures should be Revision 1, Bypassed and Inoperable Status supplemented by an indication system that indication for Nuclear Power Plant Safety Systems, is automatically indicates, for each affected safety the current regulatory guidance for BISI. Please system or subsystem, the bypass or deliberately provide a regulatory evaluation of BISI against the induced inoperability of a safety function and the current RG. 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

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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:

• Main and Aux Feedwater

• Safety Injection

• Residual Heat Removal

• Containment Spray

• Emergency Gas Treatment

• Essential Raw Cooling Water

• Chemical and Volume Control

• Ventilating

• Component Cooling

• Control Air( including Aux Control Air)

• Standby Diesel Generator The system level displays/indicating lights indicate the status of each systems train functional path as well as the status of any support system that might put the system in an inoperable or bypassed condition.

The BISI system software runs on the Integrated Computer System(ICS) and it provides the capability to monitor in real time the parameters required to provide a BISI system as described in the Reg Guide.

The system level display or indicating lights indicate NORMAL status when a previously bypassed system returns to normal operational status. The Operations staff will determine the impact of each alarm on the process flow path indication during plant modes of operation. The final decision of system operability is left up to the Operations staff to determine per Technical Specifications.

2. The indicating system for BISI should also be activated automatically by the bypassing or the deliberately induced inoperability of any auxiliary or supporting system that effectively bypasses or renders inoperable a safety function and the systems actuated or controlled by the safety function.

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Response: The Integrated Computer System(ICS) obtains real-time plant parameter information system by continuously scanning pre-assigned analog, pulse, and contact sensors located throughout the plant to provide status information to the BISI system and automatically displays that information on the BISI terminals in the Main Control Room. Alarms are also initiated to gain the Operations staffs attention.

3. Annunciating functions for system failure and automatic actions based on the self-test or self-diagnostic capabilities of digital computer-based I&C safety systems should be consistent with Positions 1 and 2.

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

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.

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If an alarm condition exists, additional detailed information is provided to the operations staff so as to allow determination of the abnormal condition. The information provided will identify to the Operations staff the exact nature of the initiating condition for the abnormal alarm. Each BISI system point will allow the user to access a detailed system screen.

These indicators and alarms will provide critical information to help the operations staff determine whether continued reactor operation is/is not permissible. As stated previously, the final decision of system operability/inoperability is left to the Operations staff to determine per Technical Specifications.

6. Bypass and inoperable status indicators should be designed and installed in a manner that precludes the possibility of adverse effects on plant safety systems. The indication system should not be used to perform functions that are essential to safety, unless it is designed in conformance with criteria established for safety systems.

Response: The BISI system is not designed to safety system criteria and therefore is not to be used to perform functions essential to the health and safety of the public, nor are operator actions based solely on BISI indications.

Appropriate electrical and physical isolation from safety-related equipment to the non-safety system is provided to meet the requirements identified in the FSAR. The ICS is independent of existing sensors and equipment in safety-related systems.

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

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and wiring for Class 1E electrical systems and components in the plant.

197 X Open Item 197 was never issued. Closed Closed 198 7.5.1. 7.5.2.2 7/20/2010 Responder: Costley/Norman Open Open EICB (Marcus) 1.2 SRP Section 7.5, Subsection III, Review Procedures F. The scope of the WBN BISI indications are TVA to respond or states: Recommended review emphasis for BISI based on engineering calculation provide proposed F. Scope of BISI indications - As a minimum, BISI WBPEVAR8807025 Rev. 7 (Attachment 10). This date of response.

should be provided for the following systems: calculation has not been updated for Unit 2. The

- Reactor trip system (RTS) and engineered safety calculation does include Common and Unit 2 features actuation system (ESFAS) - See SRP equipment required to support Unit 1 operation.

Appendix 7.1-B subsection 4.13, Indication of G. Compliance to Regulatory Guide 1.47 is Bypasses, and SRP Appendix 7.1-C subsection 5.8.3, described in design criteria document WB-DC Indication of Bypasses. 29 Rev. 8, Integrated Computer System

- Interlocks for isolation of low-pressure systems from (submitted under TVA letter dated August 11, the reactor coolant system - See SRP BTP 7-1. 2010 (Reference 1)) which is a design input to

- ECCS accumulator isolation valves - See SRP BTP calculation WBPEVAR8807025 Rev. 7.

7-2. H. Design criteria document WB-DC-30-29 Rev.

- Controls for changeover of residual heat removal 8, Integrated Computer System submitted under from injection to recirculation mode - See SRP BTP 7- TVA letter dated August 11, 2010 (Reference 1))

6. section 3.4.1, BISI Design and Operation states:

G. Conformance with Regulatory Guide 1.47, The BISI shall not be designed to safety related Bypassed and Inoperable Status Indication for system criteria and therefore is not to be used to Nuclear Power Plant Safety Systems. perform functions essential to the health and H. Independence - See SRP Appendix 7.1-B safety of the public. Class 1E isolation is required, subsection 4.7, Control and Protection System however, to maintain the independence of safety Interaction, and SRP Appendix 7.1-C subsections 5.6, related equipment and systems.

Independence, and 6.3, Interaction Between the I. Development of the Bypassed and Inoperable Sense and Command Features and Other Systems. Status Indication (BISI) application of the The indication system should be designed and Integrated Computer System (ICS) is performed installed in a manner that precludes the possibility of in accordance with NPG SPP 2.6, Computer adverse effects on plant safety systems. Failure or Software Control, Rev. 12 (Attachment 35). The bypass of a protective function should not be a development process starts with classifying the credible consequence of failures occurring in the application depending on how the output of the indication equipment, and the bypass indication should software will be used. BISI software is currently not reduce the required independence between classified as category C in accordance with .

redundant safety systems. Appendix B which defines Category C as:

I. Use of digital systems - See SRP Appendix 7.0-A and Appendix 7.1-D. Application Software Categories Category Description Please provide a description of how BISI meets each item above, or provide appropriate justification for not C Software and data which are an integral part of doing so. a quality-related but not safety-related plant system or component and are essential to the performance of that function.

Software, portions of software, and data essential to the implementation of quality-related programs listed in Section 5.1.B of the Nuclear Quality Assurance Plan, including software used to

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implement regulatory physical security requirements.

Software and data which implements NQAP requirements but not specifically identified as an augmented quality-related program as defined in Section 5.1.B of the NQAP.

Software, not associated with a specific plant system, which stores, maintains, controls, distributes or manages data which can be used without further verification in activities which affect safety- or quality- related plant structures, systems, and components.

Software, portions of software, and data which are an integral part of a non safety-related, non-quality related plant system or component whose failure would significantly impact plant operations.

Software used in the design of non quality-related, non safety-related plant structures, systems, and components Based on category C classification, SPP 2.6, Annex C defines the documentation that is required for the software..

For BISI, a Software Requirements Specification (SRS) based on the engineering calculation will be generated along with a Software Design Description. A Software Verification and Validation Report (SVVR) consisting of a Validation Test and results and an Operability Test and results will be prepared. User documentation for BISI will be incorporated into the overall ICS user documents.

Future changes to BISI will be driven foremost by changes to the engineering calculation that defines the overall functionality of the system.

Any changes to the engineering calculation will cause a Software Services Request (SSR) to be generated. Depending on the scope of the change, the various documents (SRS, SDD, SVVR and user documentation) will be updated or re-issued.

199 7.5.1. 7.5.2.3 EICB 7/20/2010 Responder: Costley/Norman Open Open Related SE Section 7.5.5.3 1.3 (Marcu s)The WBU2 FSAR Section 7.5.2.3, Technical Support The Technical Support Center is intended to be TVA to respond or Center and Nuclear Data Links, contains a description an accident mitigation support center and provide proposed

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of the Technical Support Center and Nuclear Data provides Satellite Display Stations (SDS) capable date of response.

Links. of displaying information on plant systems for Unit 1, Unit 2 or the Simulator. Stations in the TSC SRP Section 7.5, Subsection II, Acceptance Criteria receive data from the plant Integrated Computer states: System (ICS) over the ICS network. Separate Requirements applicable to the review ofERF PCs receive data from the simulator computer information systems, and ERDS information systems over the WBN site network to support drills and 10 CFR 50.55a(a)(1), Quality Standards. training exercises. Those PCs can also access the Plant Engineering Data System (PEDS) as a Please provide a description of how the nuclear data backup to ICS. The TSC also has a separate links meets this regulatory requirement. computer that connects to the CECC to allow additional access to meteorological station.

The ICS data is also transmitted from the PEDS server through the PEDS Firewall over the WBN Site Network to the CECC computers (Chattanooga). The CECC computers transmit the data over the TVA Corporate Network, through the TVA Firewall (provided by NRC), through the NRC Firewall to the NRC. Transmission of this data from the ICS and Meteorological Station over data link (High Speed Communications Link) to the CECC and NRC meet the requirements of NUREG-0696, Functional Criteria for Emergency Response Facilities and NUREG-1394, Emergency Response Data System Implementation.

200 7/21/2010 Responder: Clark Open Open Related to SE Section 7.5 EICB (Carte)

Amendment 99 of the Watts Bar Unit 2 FSAR Section The statement in SER Section 7.5.1 is supported NRC Review 7.5, Instrumentation Systems Important to Safety, by the following:

does not include any description of instrumentation for normal operation; therefore, Section 7.5 of the FSAR I&C Systems for Normal Operation FSAR Section does not support statements made in the SER Section Eagle 21 7.2 7.5; compare SER (ML072060490) Section 7.5.1 and Neutron Monitoring 7.2 FSAR Amendment 99 Section 7.5. Please identify Foxboro Spec 200 7.3 (List of other sections in where, in the docketed material, information exists to attachment 34) support the statements in the SER Section 7.5.1. Foxboro I/A 7.7.11 (new section will be added by amendment 101) (other sections have been previously provided)

Plant Computer 7.5.2 Rod Control 7.7.1.2 CERPI 7.7.1.2 Control Rod Drive 7.7.1.1 Incore Neutron Monitoring 7.7.1.9 Lose Part Detection/Monitoring 7.6.7 Vibration Monitoring RCP 5.5.1.2 Control Boards 7.1.1.10 RVLIS 7.5, 5.6 201 C B

(C 7/21/2010 Responder: Webb Open Open Related to SE Section 7.7.1.1.1 t

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Amendment 99, FSAR Section 7.7.1.1.1, "Reactor These functions are within the scope of the TVA to docket Control Input Signals (Unit 2 Only)," contains a Foxboro I/A system. Section 7.7.11 will be added amendment 101.

description of functions performed uniquely for Unit 2. to the FSAR in amendment 101 to provide a Please describe the equipment that performs this discussion of the DCS.

function (in sufficient detail to support a regulatory evaluation), and evaluate this equipment against the appropriate regulatory criteria.

202 7/22/2010 Responder: WEC Open Open Relates to SE Section 7.5.2, PAMS EICB (Carte)

The letter (ML0003740165) which transmitted the Revision 1 of the Licensing Technical Report will TVA to respond or Safety Evaluation for the Common Q topical report to provide more detailed information on the changes provide proposed Westinghouse stated: "Should our criteria or to the platform. This revision is scheduled to be date of response.

regulations change so that our conclusions as to the issued by Westinghouse no later than September acceptability of the report are invalidated, CE Nuclear 30, 2010 and will be submitted to the NRC within Power and/or the applicant referencing the topical 2 weeks of receipt.

report will be expected to revise and resubmit their respective documentation, or submit justification for Rev. 2 of the Licensing Technical Report will continued applicability of the topical report without include the applicability of guidance. This item is revision of the respective documentation." Question currently not scheduled. A schedule date will be No 81 identified many criteria changes; please revise provided by Westinghouse no later than the respective documentation or submit justification for September 30, 2010 and the document will be continued applicability of the topical report. submitted to the NRC within two weeks of receipt.

203 7.5.1. 7.5.2 7/26/2010 Responder: Clark Open Open EICB (Marcus) 1 By letter dated April 27, 2010 (ML101230248), TVA The plant computer system is one set of TVA to respond or stated (Enclosure Item No.19): "The WBN Unit 2 hardware. The Safety Parameter Display provide proposed Integrated Computer System(ICS) modification merges System, Bypassed and Inoperable Status date of response.

the ERFDS and plant computer into a single computer Indication System (BISI), Technical Support network." Center and Nuclear Data Links are all functions of the Plant Computer System. Historically the FSAR Section 7.5.2, "Plant Computer System," has Westinghouse P2500 Plant Process Computer three subsections: and Emergency Response Facilities Data System 7.5.2.1, "Safety Parameter Display System" (ERFDS) were individual systems but were 7.5.2.2, "Bypassed and Inoperable Status Indication merged together with the implementation of DCN System (BISI)" 39911-A, implemented for WBN Unit 1 in 7.5.2.3, "Technical Support Center and Nuclear Data December 1998, to become the Plant Integrated Links" Computer System (ICS). A similar system is being This arrangement implies that the each of these installed for WBN Unit 2 based on the same function are part of the plant computer, and not a software with more modern hardware.

separate sets of equipment. Please describe the equipment for each function and identify any The ICS is composed of a number of pieces of equipment common to more than one function. 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

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is no separate set of equipment for any of the functions referenced in FSAR Section 7.5.2.1 and 7.5.2.2.

The Nuclear Data Link and EOF functions described in 7.5.2.3 are provided by the CECC in Chattanooga. In order for the CECC to have access to ICS data, both the PEDS and the data diode isolating the PEDS from the ICS must be operational.

Meteorological data from the Environmental Data Station (EDS) is gathered by the Unit 1 ICS.

That data is sent over to the unit 2 ICS via the inter-unit firewall.

204 7.5.1. 7.5.2 7/26/2010 Responder: Costley/Norman Open Open Relates to SE Section 7.5.2, PAMS EICB (Marcus) 1 By letter dated March 12, 2010 (ML101680577) TVA 1. Three data diodes. TVA to respond or provided drawing No. 2-45W2697-1-1, "Integrated 2. Two provide an interface between train A and B provide proposed Computer System Network Configuration Connection of Common Q. date of response.

Diagram," that depicts three "Data Diodes. Please a. These are identical systems consisting of the provide a detailed description of the equipment, following:

software, and configurations of each "Data Diode". i. Dual DELL R200 computers ii. Red Hat Enterprise Linux software that is locked down by CTI iii. 55 Mbs Owl cards iv. Fiber optic Ethernet interface to trained Maintenance test panel

b. Software is configured to allow only specific traffic from the MTP to pass through to the ICS

c. The secure side of the data diode will initiate the 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:

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i. Once per second current values and qualities for all points ii. History data archived by the ICS iii. Data files

c. The data diode does not allow any data to be transferred between the PEDS network and the ICS network.

205 7/26/2010 Responder: Clark Open Open Question B related to prior NRC EICB (Garg) approval of this system or 50.59 Regarding the Foxboro Spec 200 system installed at As discussed at the August 3 and 4 meeting in TVA to respond or information. This question will be Unit 2: Knoxville between TVA and the NRC, the Foxboro provide proposed addressed in the August plant visit.

Spec 200 is not a system. The Foxboro Spec 200 date of response.

a- Is it similar to Unit 1? If not, identify the differences analog hardware is used to replace the existing and evaluation of the acceptability of these obsolete hardware with the same functions.

differences. There are no interconnections between the analog loops unless such interconnections existed b- deleted prior to the replacement. This is strictly an analog to analog upgrade due to equipment c- For each system which is discussed in the FSAR obsolescence. The Foxboro hardware is installed and utilizes the Spec 200 system, please provide the in existing cabinets which require modifications to instrument logic diagram, loop/block diagram with accept the Foxboro hardware racks.

reference to where the system is discussed in the FSAR. a- A listing of the replacements and differences was previously provided as Attachment 1 to TVA letter to the NRC dated June 18, 2010. Within Unit 1, only portions of the AFW controls were replaced. In Unit 2 all safety-related analog loops were replaced. The Foxboro Spec 200 is a fully qualified industry standard for replacement of obsolete analog instrument and control loop hardware.

b- deleted c- c- The Foxboro Spec 200 hardware has not been installed. Therefore the revised drawings have not been issued. Based on this, EDCR excerpts for the logic diagrams and loop/logic drawings were provided as attachments to TVA letter to the NRC dated July 30, 2010. The cross reference between the functions upgraded as part of the Foxboro Spec 200 change is contained in Attachment 33.

206 7.5.1. 7.5.2 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.1.1, 1 EICB Integrated Computer System The NRC Requested a description of the plant (1) The Plant Computer is not just a computer WB-DC-30-29 Rev. 8 is NRC to review (Marcus) computer and TVA provided: but is a system and is designated the Integrated Enclosure 1 of TVA letter WB-DC-30-29 (1) Dell marketing literature for Dell Poweredge R200 Computer System or ICS. The ICS is composed dated August 11, 2010 Rev. 8.

Server, which can be found on the internet of multiple computer CPUs, LCD displays, RTP (ML102240382 letter and

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

(http://www.dell.com/downloads/global/products/pedge Multiplexer Assemblies, network fiber optic ML102240383 Enclosure 1).

/en/pe_R200_spec_sheet_new.pdf), and panels, fiber optic converters, Ethernet switches (2) HP Integrity rx2660 Server User Service guide and network taps previously described in items (edition 6), which has not yet been found on the 71, 81 and 82 above. For a detailed discussion of internet, but many other editions have been found. the ICS functions refer to design criteria document This information is not adequate for answering the WB-DC-30-29 Rev. 8, Integrated Computer question. (Note: TVA also provided a network System submitted under TVA letter dated August configuration connection diagram, which is necessary __, 2010.

but not sufficient.)

(2) As previously discussed in item 82, there is no Please provide a description of the plant computer: unique set of hardware for any specific function.

(1) Please include sufficient detail so that an evaluation can be made against the SRP acceptance criteria in SRP Section 7.7.

(2) Please identify the equipment (hardware and software) that performs each function described in the FSAR.

207 July 27, 2010 Date: Closed Closed EICB (Carte)

Responder:

deleted 208 7.5.2. 7.5.1 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB (Marcus) 1 By letter dated June 18, 2010 (ML101940236), TVA The notes provided with the table include the TVA to respond or responded to an NRC request for additional change to the variable under 10 CFR 50.59. For provide proposed information. Enclosure 1 Item No. 6 of this letter ease of review, the other note references have date of response.

identified, for each PAM variable whether the variable been deleted for these variables and only the note was: (1) implemented identically to Unit 1 and dealing with the Unit 1 change has been retained reviewed by the NRC, (2) implemented identically to in the Notes column of the table excerpt. The Unit 1 but modified under 10 CFR 50.59 after it was applicable notes are highlighted in the notes list.

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.

209 7.5.2. 7.5.1 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB (Marcus) 1 By letter dated June 18, 2010 (ML101940236), TVA The first eight variables in question are primary TVA to respond or responded to an NRC request for additional chemistry parameter. The parameters are the provide proposed information. Enclosure 1 Item No. 6 of this letter same for both units, but in Unit 1, the sample is date of response.

identified, for each PAM variable whether the variable obtained via the post accident sampling system, was: (1) implemented identically to Unit 1 and while in Unit 2 the sample is obtained using a reviewed by the NRC, (2) implemented identically to grab sample via the normal sample system.

Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) implemented in a The last variable was somewhat difficult to manner that is unique to Unit 2. There were nine characterize. The method of detection and the variables that were identified as both Unique to Unit 2 hardware manufacturer is the same in both units.

and identical to what was reviewed and approved on However, due to obsolescence some of the parts

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Unit 1. Please explain. are different than what is installed in Unit 1. The differences are described in Note 21 of the original response.

210 7.5.2. 7.5.1 7/27/2010 Responder: Clark Open Open Relates to SE Section: 7.5.2, PAMS EICB (Marcus) 1 By letter dated June 18, 2010 (ML101940236), TVA The design basis for Unit 2 is to match Unit 1 as TVA to respond or responded to an NRC request for additional closely as possible. This includes incorporating provide proposed information. Enclosure 1 Item No. 6 of this letter changes made to Unit 1 after licensing under 10 date of response.

identified, for each PAM variable whether the variable CFR 50.59. The changes in question fall into this was: (1) implemented identically to Unit 1 and category and are described in the Notes for each reviewed by the NRC, (2) implemented identically to variable in the original submittal.

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.

211 7.5.1. 7/27/2010 Responder: Clark Open Open Relates to SE Sections:

EICB (Carte) 1 7.5.5, Plant Computer 7.5.2 FSA Table 7.1-1 shows: "The extent to which the The WBN 2 FSAR Section 7.5 defines the TVA to respond or 7.6.10, Loose Part Monitoring 7.6.1 recommendations of the applicable NRC regulatory following systems as important to safety provide proposed 7.7.1, Control System Description 7.7.1 guides and IEEE standards are followed for the Class date of response. 7.7.2, Safety System Status 7.7.2 1E instrumentation and control systems is shown 1. Post Accident Monitoring including: Monitoring System 7.7.4 below. The symbol (F) indicates full compliance. Those a. Common Q Post Accident Monitoring System 7.7.4, PZR & SG Overfill 7.9 which are not fully implemented are discussed in the (Safety-Related) 7.9, Data Communications referenced sections of the FSAR and in the footnotes i. Reactor Vessel Level as indicated." ii. Core Exit Thermocouples iii. Subcooling Margin Monitor Please describe how systems that are important to b. Eagle 21 indications (Safety-Related) safety, but not 1E, comply with 10 CFR 50.55a(a)1: c. Foxboro Spec 200 indications (Safety-Related)

"Structures, systems, and components must be d. Neutron Monitoring (Source and Intermediate designed, fabricated, erected, constructed, tested, and Range) (Safety-Related) inspected to quality standards commensurate with the e. Radiation Monitors (Safety-Related) importance of the safety function to be performed." 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

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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 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. A description of the distributed control system will be added as FSAR section 7.7.1.11 in FSAR Amendment 101.

Installation is performed in accordance with the quality requirements of either the Bechtel or TVA work order processes based on the quality classification of the equipment being installed.

Vendor testing is performed in accordance with procurement specification requirements which are based on the type and quality classification of the equipment. Preoperational testing is performed in accordance with Chapter 14 of the FSAR.

212 7/27/2010 Responder: WEC Open Open Relates to SE Section 7.5.2 EICB (Carte) By letter dated June 18, 2010 (ML101940236) TVA Application specific requirements for testing. This TVA to respond or stated (Enclosure 1, Attachment 3, Item No. 3) that the cannot be addressed in a topical report. provide proposed

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PAMS system design specification and software Evaluation of how the hardware meets the date of response.

requirements specification contain information to regulatory requirements.

address the "Design Report on Computer Integrity, Test and Calibration..." The staff has reviewed these WEC to provide the information and determine documents, and it is not clear how this is the case. where the information will be located.

(1) Please describe how the information provided demonstrates compliance with IEEE 603-1991 Clauses 5.5, 5.7, 5.10, & 6.5.

(2) Please describe how the information provided demonstrates conformance with IEEE 7-4.3.2-2003 Clauses 5.5 & 57.

213 7/27/2010 Responder: WEC Open Open Relates to SE Section 7.5.2 EICB (Carte)

By letter dated June 18, 2010 (ML101940236) TVA Carte to review and revise this TVA to respond or stated (Enclosure 1, Attachment 3, Item No. 3) that the question. provide proposed PAMS system design specification and software date of response.

requirements specification contain information to address the "Theory of Operation Description." The staff has reviewed these documents, and it is not clear how this is the case. The docketed material does not appear to contain the design basis information that is required to evaluate compliance with the Clause of IEEE 603.

(1) Please provide the design basis (as described in IEEE 604 Clause 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 operation.

For example: Regarding IEEE 603 Clause 5.8.4 (1)

What are the manually controlled protective actions?

(2) How do the documents identified demonstrate compliance with this clause?

214 7/27/2010 Responder: WEC Open Open EICB (Carte)

By letter dated June 18, 2010 (ML101940236) TVA According to "The Software Program Manual for WEC References Common Q TVA to respond or stated (Enclosure 1, Attachment 3, Item No. 10) that Common Q Systems," WCAP-16096-NP-1A, the PAMS preliminary hazards provide proposed the approved Common Q Topical Report contains Software Safety Plan only applies to Protection analysis is referenced in the date of response.

information to address the "Safety Analysis." The class software and PAMS is classified as SRS. WEC to delete.

Common Q SPM however states that a Preliminary Important-to-safety. Exhibit 4-1 of the SPM Hazards Analysis Report and the V&V reports shows that PAMS is classified as Important-to-document the software hazards analysis. Please Safety Provide these documents.

215 7/29/2010 Responder: WEC Open Open DORL (Bailey)

By letter dated June 18, 2010, TVA provided a table Close this item TVA to respond or showing the documents that had been completed and provide proposed were available for staff review. In a conference call on date of response.

July 27, 2010, TVA agreed to submit the requested documents on the docket. Please provide the

( schedule for submitting the documents.

216 7.5.1. 7.5.2 7/29/2010 Responder: Clark Open Open M

a

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1 By letter dated March 12, 2010 (ML101680577), TVA 1) EDCR 52322 is contained in Attachment 7. TVA to respond or stated that it would provide five documents to describe 5) The design change referred to is the addition of provide proposed the Process computer: (1) EDCR 52322 Rev. A a data diode. This has not been incorporated into date of response.

excerpts, (2) HP RX2660 Users Guide AB419-9002C- the drawing. Please see the response to letter ed6, (3) Dell Poweredge R200 Server sheet November item 88 (RAI Matrix Item 224).

2007, (4) RTP Corp 8707 I/O Brochure RTP 8707-02, 2004, and (5) Integrated Computer System Drawing.

217 7/6/2010 Responder: Clark Open Open EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that Attachment 7 contains excerpts of the following NRC Review provide the block and logic diagrams for the Foxboro change documents:

Spec 200 implementation.

DCN 52376 Note: These changes are scheduled to be implemented after Unit 2 Fuel Load DCN 52641 NOTE: DCN 52376 and 52641 impact loops already in service for Unit 1 and as such are implemented under 10CFR50.59.

EDCR 52343 EDCR 52427 218 7/6/2010 Responder: Clark Open Open EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that The excerpt of work order WO 08-813412-000 Attachment 8 contains the NRC Review provide the block and logic diagrams for the Foxboro provided with the June 18 letter did not contain required correct work order Spec 200 implementation. the information showing that the new type excerpt.

(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.

219 8/4/2010 Responder: TVA Licensing Open Open EICB (Garg) Transmit copy of February 8, 2008 FSAR Red-Line for A copy was hand carried by Mr. W. Crouch and Check what sent by Terry Unit 2 letter with attachments [CD]. delivered to Stewart Bailey at the August 17 missing attachments.

meeting at NRC headquarters.

220 8/4/2010 Responder: Ayala Open Open EICB (Garg)

For Safety Related SSPS, submit letter justifying delta The Westinghouse ARLA latch attachment is Are there any open issues? TVA to respond or between U1 [utilizing ARs] & U2 [utilizing ARs and obsolete. In order to provide a latching relay for Docket plant specific provide proposed MDRs]. [Requires TS change ???] Unit 2 Solid State Protection System (SSPS), a responses to the individual. date of response.

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 MDR ESFAS Slave relays on an 18-month interval based on the assessment done in

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

WCAP-13878-P-A, Revision 2, Reliability Assessment of Potter & Brumfield MDR Series Relays.

An initial Unit 2 ESFAS SSPS Slave Relay Service Life and Contact Load study similar to that done in Unit 1 has been completed to show that Unit 2 satisfies the conditions of WCAP-13877-P-A, Revision 2, Reliability Assessment of Westinghouse Type AR Relays used as SSPS Slave Relays, and WCAP-13878, Revision 2, Reliability Assessment of Potter & Brumfield MDR Series Relays. The Contact Load study also identifies locations in which MDR relays are not acceptable for use.

221 7.7.1. 7.7.1.3 8/4/2010 Responder: Trelease Open Open EICB (Marcus) 2 Submit EDCR Technical Evaluation for the source and The EDCR 52421 Source and Intermediate TVA to respond or intermediate range updated electronics for Unit 2 Range, Scope and Intent, Unit Difference and provide proposed Technical Evaluations are contained in date of response.

Attachment Error! Reference source not found..

222 8/4/2010 Responder: Clark Open Open EICB (Garg) Submit updated list for Foxboro Spec 200 The updated listing of Foxboro Spec 200 loop

[replacement of Bailey and Robert-Shaw electronics functions is contained in Attachment 33.

223 8/4/2010 Responder: Clark Closed Closed EICB (Garg)

Submit EDCR Technical Evaluation for Foxboro I/A Duplicate of item 233.

replacing obsolete non-safety related Foxboro H-Line analog electronics with a digital CDS. [selected single point failures being addressed in design]

224 7.5.1. 7.5.2 8/4/2010 Responder: Norman (TVA CEG) Open Open EICB (Marcus) 1 Mike Norman [TVA Computer Eng. Group] will check The Data diode to isolate the WBN Unit 1 and TVA to respond or status of DCN/50.59 for Integrated Computer System Unit 2 ICS computers from the WBN PEDS provide proposed upgrade that will install the data diode between the computers will be installed in PIC 56278 as part of date of response.

WBN PEDS and the Unit 1 and Unit 2 ICS. 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.

225 8/4/2010 Responder: Scansen Open Open EICB (Garg)

Provide EDCR Technical Evaluation Justify/explain The requested information is contained in the TVA to respond or updated hardware [functionally equivalent to Unit 1] for Scope and Intent, Unit Difference and Technical provide proposed the RCP and Turbine Generator vibration monitoring Evaluations for EDCRs 52420 (Attachment 11) date of response.

equipment. and 53559 (Attachment 12) 226 (C art 8/4/2010 Responder: TVA Licensing Closed Closed See also Open Item Nos. 41 & 270.

e/

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Submit the Foxboro I/A segmentation analysis and ICS These documents were submitted under TVA NNC 8/25/10: Segmentation Design Criteria documents on an expedited separate letter dated August 11, 2010. analysis has been received letter. Provide a date when the Segmentation analysis and read. Please describe will be revised based on discussions at the meeting. why a failure or error will not propagate over the -peer-to-peer network, and cause more than one segment to fail.

227 8/4/2010 Responder: Clark Open Open EICB (Garg)

Provide copies of 50.59s for the following Unit 1 A. CERPI, initial installation DCN 51072 and TVA to respond or changes 2009 upgrade DCN 52957 (Attachment provide proposed Error! Reference source not found.) date of response.

a. CERPI (initial installation and 2009 upgrade) B. Upgrade of RCP, TG and FW pumps

b. Vibration monitoring (RCP, TG and FW pumps to vibration monitoring to Bentley-Nevada 3300, Bentley-Nevada 3300) DCN 39242, DCN 39506, DCN 39548, and

c. Containment Sump Level Transmitter replacement DCN 50750 (Attachment )

d. Turbine Servo Control Valve Card replacement C. Containment Sump Level Transmitter

e. Pressurizer Heater deletion of Backup Heaters on replacement, DCN 39608 (Attachment )

for PZR High Level D. Turbine Servo Control Valve Card

f. AMSAC replacement, DCN 38993 (Attachment )

g. Significant ESFAS changes E. Pressurizer Heater deletion of Backup Heaters on for PZR High Level, DCN 51102 (Attachment )

F. AMSAC DCN 50475 (Attachment )

G. Significant ESFAS changes

i. Relocate containment isolation valve function and relocate the 6.9KV Shutdown Boards Emergency Feeder Breaker Trip function from K626 and K602, respectively, to minimize disruption on plant operation. DCN 38238 (Attachment Error!

Reference source not found.)

ii. Revise OTT and OPT turbine runback setpoints, DCN 38842 (Attachment )

iii. Install Integrated Computer System (ICS) Stages 4 and 5, DCN 50301 (Attachment )

228 8/4/2010 Responder: Clark Open Open EICB (Carte/Sin Submit rod control system description N3-85-4003 The Rod Control System Description N3-85-4003 TVA to respond or gh) is contained in Attachment 21. provide proposed date of response.

229 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit Annunciator system description/design criteria Condition Status/Alarm Design Criteria Document NNC 8/25/10: Document not TVA to respond or WB-DC-30-21 is contained in Attachment 22. yet received. provide proposed date of response.

(

230 C 8/4/2010 Responder: Webb Open Open

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Submit Foxboro I/A Procurement Specification The requested Foxboro I/A Procurement NNC 8/25/10: Document not TVA to respond or excerpts that provide system description information Specification is contained in Attachment 23. yet received. provide proposed date of response.

231 8/4/2010 Responder: Clark Close Open EICB (Garg)

Update FSAR Amendment 100 Section 7.1.1.2 FSAR section 7.1.1.2 is revised in FSAR FSAR AMD 100 markup based on discussion with Hukam Garg. Amendment 100 submitted to the NRC on TVA letter to the NRC dated September 1, 2010 includes the requested clarifications.

232 8/4/2010 Responder: Clark Open Open EICB (Singh)

Submit EDCR Technical Evaluation for LPMS EDCR The EDCR 52418 Lose Part Monitoring Scope TVA to respond or and Intent, Unit Difference and Technical provide proposed Evaluations are contained in Attachment 24. date of response.

Clarify Att 24 to which document.

233 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit EDCR Technical Evaluation for Foxboro I/A Foxboro I/A EDCRs 52378 and 52671 Scope and NNC 8/25/10: Documents NRC to review EDCR Intent, Unit Difference and Technical Evaluations received. documents.

are contained in Attachment 25.

234 8/4/2010 Responder: Closed Closed EICB (Carte) Bechtel to perform D3 analysis for Common Q PAMS Duplicate of Item 64 which will be incorporated into Westinghouse Licensing Technical Report.

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

236 8/4/2010 Responder: Clark Open Open EICB (Garg)

Submit EDCR Technical Evaluation for Foxboro Spec Foxboro Spec 200 EDCRs 52343, 52427 and TVA to respond or 200 EDCRs 52641, Scope and Intent, Unit Difference and provide proposed Technical Evaluations are contained in date of response.

Attachment 26.

237 8/4/2010 Responder: Clark Open Open EICB (Carte) Submit EDCR Technical Evaluation for Annunciator The Annunciator EDCR 52315 Scope and Intent, NNC 8/25/10: Documents not TVA to respond or EDCR Unit Difference and Technical Evaluations are yet received. provide proposed contained in Attachment 27. date of response.

238 8/4/2010 Responder: Webb/Hilmes Closed Closed EICB (Carte) Discuss with TVA adding a description of the Foxboro Duplicate of item 201 I/A system to chapter 7 of the FSAR.

239 EIC 8/4/2010 Responder: Hilmes Closed Closed B

(Cart

)

Plan a meeting with TVA the NRC and Westinghouse meeting held 8/17/10

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

to review Common Q PAMS documentation.

240 8/4/2010 Responder: Clark Open Open EICB (Garg) Submit EDCR Technical Evaluation for Vibration The Scope and Intent, Unit Difference and TVA to respond or Monitoring EDCR(s) Technical Evaluations for EDCRs 53559 and provide proposed 52420 are contained in Attachment 28. date of response.

241 8/4/2010 Responder: Davies Open Open EICB (Singh)

Review CERPI WCAPs for system description CERPI was designed after Westinghouse stopped TVA to respond or information to be submitted to the NRC. using WCAPs. The document that provides the provide proposed most detailed information is the CERPI System date of response.

Requirements Specification WN-DS-00001-WBT TVA to add the Rev. 2. The proprietary version of this document document number and the affidavit for withholding are contained in for Att 29.

Attachment 29.

242 8/4/2010 Responder: Hilmes Open Open EICB (Garg)

TVA to make firm decision on date of transfer (before The Unit 2 loops in service for Unit that are TVA to respond or or after initial startup) of Unit 2 loops in service for Unit scheduled to be transferred to the Foxboro Spec provide proposed 1 to new Foxboro Spec 200 hardware 200 hardware will be transferred prior to Unit 2 date of response.

fuel load.

243 8/3/2010 Responder: WEC Open Closed.

EICB (Carte)

Section 8.2.1 of the Common Q SPM (ML050350234) WEC to address at the 9/15 meeting TVA to respond or states that the System Requirements Specification provide proposed (SysRS) includes the system design basis. Section Closed to Item 142 date of response.

1.2, "System Scope," of the WBN2 PAM SysRS (ML101680578) includes a description of the PAMS design bases that does not meet the requirements of IEEE 603-199 Clause 4. Please provide a description of the PAMs design bases that conforms to the requirements of IEEE 603-1991 Clause 4.

244 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the Section 8.2.2 of the Common Q SPM (ML050350234) WEC agreed to remove process related items TVA to respond or information relied upon in the SE states that the Software Requirements Specification from all docs. Close to previous item and revise provide proposed must be docketed (SRS) shall be developed using IEEE 830 and RE previous item to include all documents. date of response. correspondence."

1.172. Clause 4.8, "Embedding project requirements in the SRS," of the IEEE 830 states that an SRS LIC-101 Rev. 3 states: "The safety should address the software product, not the process analysis that supports the change of producing the software. In addition Section 4.3.2.1 requested should include technical of the SPM states "Any alternatives to the SPM information in sufficient detail to processes or additional project specific information for enable the NRC staff to make an the ...SCMP...shall be specified in the PQP. independent assessment regarding the acceptability of the proposal in Contrary to these two statements in the SPM, the terms of regulatory requirements WBN2 PAMS SRS (ML101050202) contains many and the protection of public health process related requirements, for example all and safety."

seventeen requirements in Section 2.3.2, "Configuration Control," address process requirements

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for configuration control.

Please explain how the above meets the intent of the approved SPM.

245 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the Section 5.8 of the Common Q SPM (ML050350234) Relates to the commitment to provide the test TVA to respond or information relied upon in the SE identifies the required test documentation for systems plan and the SPM compliance matrix provide proposed must be docketed developed using the Common Q SPM. Please provide date of response. correspondence."

sufficient information for the NRC staff to independently assess whether the test plan for WBN2 LIC-101 Rev. 3 states: "The safety PAMS, is as described in the SPM (e.g., Section analysis that supports the change 5.8.1). requested should include technical information in sufficient detail to enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

246 8/3/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the Section 4.3.2.1, "Initiation Phase" of the Common Q There is a PQP and SPM compliance matrix will TVA to respond or information relied upon in the SE SPM (ML050350234) requires that a Project Quality be referenced in the Licensing Technical Report. provide proposed must be docketed Plan (PQP) be developed. Many other section of the date of response. correspondence."

SPM identify that this PQP should contain information WEC to identify the elements of the SPM in the required by ISG6. Please provide the PQP. If "PQP" compliance matrix LIC-101 Rev. 3 states: "The safety is not the name of the documentation produced, analysis that supports the change please describe the documentation produced and requested should include technical provide the information that the SPM states should be information in sufficient detail to in the PQP. enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

247 8/8/2010 Responder: WEC Open Open (TVA) LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the As part of the Common Q topical report development The documents will be identified in Rev. 1 of the TVA to respond or information relied upon in the SE effort, Westinghouse developed the Software Program Licensing Technical Report in the compliance provide proposed must be docketed Manual for Common Q Systems (ML050350234) to matrix. WEC to make the documents available date of response. correspondence."

address software planning documentation. The NRC ASAP in Rockville. May require later submittal.

reviewed the SPM and concluded: the SPM specifies LIC-101 Rev. 3 states: "The safety plans that will provide a quality software life cycle analysis that supports the change process, and that these plans commit to requested should include technical documentation of life cycle activities that will permit the information in sufficient detail to staff or others to evaluate the quality of the design enable the NRC staff to make an features upon which the safety determination will be independent assessment regarding based. The staff will review the Implementation of the the acceptability of the proposal in life cycle process and the software life cycle process terms of regulatory requirements design outputs for specific applications on a plant- and the protection of public health

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

specific basis. Please identify the implementation and safety."

documentation produced as a result of following the SPM, and state what information will be docketed.

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

address software planning documentation. The NRC ASAP in Rockville. May require later submittal.

reviewed the SPM and concluded: the SPM specifies LIC-101 Rev. 3 states: "The safety plans that will provide a quality software life cycle analysis that supports the change process, and that these plans commit to requested should include technical documentation of life cycle activities that will permit the information in sufficient detail to staff or others to evaluate the quality of the design enable the NRC staff to make an features upon which the safety determination will be independent assessment regarding based. The staff will review the Implementation of the the acceptability of the proposal in life cycle process and the software life cycle process terms of regulatory requirements design outputs for specific applications on a plant- and the protection of public health specific basis. Please identify the design outputs and safety."

produced as a result of following the SPM, and state when what information will be docketed.

249 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the The SVVP in the SPM describes the V&V Close to previous items to provide the V&V TVA to respond or information relied upon in the SE implementation tasks that are to be carried out. The Reports. provide proposed must be docketed acceptance criterion for software V&V implementation date of response. correspondence."

is that the tasks in the SVVP have been carried out in their entirety. Documentation should exist that shows LIC-101 Rev. 3 states: "The safety that the V&V tasks have been successfully analysis that supports the change accomplished for each life cycle activity group. Please requested should include technical provide information that shows that the V&V tasks information in sufficient detail to have been successfully accomplished for each life enable the NRC staff to make an cycle activity group. independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

250 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the The SPM describes the software and documents that Westinghouse develops Software Release TVA to respond or information relied upon in the SE will be created and placed under configuration control. Reports/Records and a Configuration provide proposed must be docketed The SCMP (e.g., SPM Section 6, Software Management Release Report. Describe the date of response. correspondence."

Configuration Management Plan) describes the documents and when they will be produced.

implementation tasks that are to be carried out. The Summarize guidance on how to produce these LIC-101 Rev. 3 states: "The safety acceptance criterion for software CM implementation is records, focus on project specific requirements in analysis that supports the change that the tasks in the SCMP have been carried out in SPM etc. requested should include technical their entirety. Documentation should exist that shows information in sufficient detail to that the configuration management tasks for that enable the NRC staff to make an activity group have been successfully accomplished. independent assessment regarding Please provide information that shows that the CM the acceptability of the proposal in tasks have been successfully accomplished for each terms of regulatory requirements

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

life cycle activity group. and the protection of public health and safety."

251 8/8/2010 Responder: WEC Open Open LIC-101 Rev. 3 Appendix B Section EICB (Carte) 4, "Safety Evaluation" states: "the The SPM describes the software testing and Addressed by SPM Compliance matrix in Rev. 1 TVA to respond or information relied upon in the SE documents that will be created. The SPM also of the Licensing Technical Report. provide proposed must be docketed describes the testing tasks that are to be carried out. Norbert is looking for guidance on how to ask for date of response. correspondence."

The acceptance criterion for software test less.

implementation is that the tasks in the SPM have been LIC-101 Rev. 3 states: "The safety carried out in their entirety. Please provide analysis that supports the change information that shows that testing been successfully requested should include technical accomplished. information in sufficient detail to enable the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory requirements and the protection of public health and safety."

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

Traceability Analysis). Please provide information that demonstrates that requirements traceability LIC-101 Rev. 3 states: "The safety analysis has been successfully accomplished. 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 8/8/2010 Responder: Clark Open Open Related to Open Item no. 83.

EICB (Carte)

TVA provided information by letter dated July 30, 2010 All AC160 modules used for the Common Q TVA to respond or LIC-110 Rev. 1 Section 6.2.2 (ML102160349) - See Enclosure 1 Item No. 8 - that PAMS have been previously approved. The provide proposed states: "Design features and some AC160 module contain FPGAs. For those original response listed all FPGAs when the date of response. administrative programs that are modules that have not been previously approved, request was only for components that had not unique to Unit 2 should then be please provide information to address regulatory been previously approved. reviewed in accordance with criteria for FPGAs. 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 B 8/10/2010 Responder: WEC Open Closed (Hal vers Please make the following available in Westinghouse's Documents are available in the Rockville office TVA to respond or

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Rockville office. per WEC letter WBT-D-2268 dated 8/16/10. provide proposed date of response.

WNA-PD-00056-WBT, Rev 1 Watts Bar Unit 2 NSSS Completion I&C Projects As the indicated source of customer specific requirements for deliverables, as indicated in the project plan, this document may serve as one end of a thread audit, and may contain information relevant to evaluating the completeness of later requirements.

956080, Rev 1. Cabinet mounted electronics -

Inadequate core cool monitor (ICCM-86)

Believe this to be the source of the requirements or at least algorithms and justifications for RIVLIS.

NABU-DP-00014-GEN, rev 2 Design Process for Common Q Safety Systems. As it defines the scope of other documents we are reviewing, it may clarify what documents are expected to contain what information.

255 8/10/2010 Responder: WEC Open Closed EICB (Halverson)

Please make the following available in Westinghouse's Documents are available in the Rockville office TVA to respond or Rockville office. per WEC letter WBT-D-2268 dated 8/16/10. provide proposed The Reusable Software Elements Documents. These date of response.

contain requirements for the software.

WNA-DS-01564-GEN, Rev 1. ; WNA-DS-00315-GEN, Rev. 2 ; WNA-DS-01715-GEN, Rev 2 ; WNA-DS-01838-GEN, Rev. 3 ; WNA-DS-01839-GEN, Rev. 3 ;

WNA-DS-01840-GEN, Rev 2. ; WNA-DS-01841, Rev

2. ; WNA-DS-01842-GEN Rev 2.; WNA-DS-01845-GEN Rev. 1. ; WNA-DS-01846-GEN Rev. 2 ; WNA-DS-01847-GEN Rev. 0 ; WNA-DS-01848 Rev. 1. ;

WNA-DS-01849-GEN Rev. 2. ; WNA-DS-01994-GEN Rev. 0 ; WNA-DS-00306-GEN Rev. 5 ; WNA-DS-02065-GEN Rev. 2 ; WNA-DS-01505-GEN Rev. 0 Further documentation for application-specific type circuits and custom PC elements are indicated by the SRS to be in 00000-ICE-3238, Rev 5 ; 00000-ICE-30140, rev 4 and 00000-ICE-30152, Rev. 5 256 8/10/2010 Responder: WEC Open Closed EICB (Halverson)

Please make the following available in Westinghouse's Documents are available in the Rockville office TVA to respond or Rockville office. per WEC letter WBT-D-2268 dated 8/16/10. provide proposed date of response.

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

Coding Standards and Guidelines for Common Q Systems, 00000-ICE-3889, Rev. 10, Westinghouse

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Electric Company LLC.

Application Restrictions for Generic Common Q Qualification, WNA-DS-01070-GEN, Rev. 3, Westinghouse Electric Company LLC.

System Requirements Specification for the Common Q Generic Flat Panel Display 00000-ICE-30155, Rev.

9, Westinghouse Electric Company LLC.

Software Requirements Specification for the Common Q Generic Flat Panel Display Software, 00000-ICE-3239, Rev. 12, Westinghouse Electric Company LLC.

Common Q Software Configuration Management Guidelines, NABU-DP-00015-GEN, Rev. 2, Westinghouse Electric Company LLC, Standard General Requirements for Cyber security, WNA-DS-01150-GEN, Rev. 0, Westinghouse Electric Company LLC, 257 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

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

AC160 CPU Loading Restrictions, AN03007Sp, ABB WBT-D-2268, 8/16/2010 Memo, ABB Process Automation Corporation, Software Design Description for the Common Q WEC still needs to make/confirm this document is Generic Flat-Panel Display Software, 00000-ICE- available.

30157, Rev. 16, Westinghouse Electric Company LLC.

System Requirements Specification for the Common WBT-D-2024, 6/9/2010 Q Post Accident Monitoring System, 0000-ICE-30156, Rev. 06, Westinghouse Electric Company LLC.

Software Requirements Specification for the WBT-D-2024, 6/9/2010 Common Q Post Accident Monitoring System 00000-ICE-3238, Rev. 5, Westinghouse Electric Company LLC.

WBT-D-2268, 8/16/2010 Commercial Dedication Report for QNX 4.25G for Common Q Applications, WNA-CD-00018-GEN, Rev.

3, Westinghouse Electric Company LLC, WBT-D-2268, 8/16/2010 Generic Common Q Software Installation Procedure,

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

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

258 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The IV&V Phase Summary Report, (WNA-VR-00283-WBT Rev . 0 ) indicated that the IV&V team had created some information that may facilitate the approval process. However the form the information may have taken was not indicated or referenced in the Phase Summary Report. Information requested for the Rockville office includes:

-The excel spreadsheet described in section 2.2.2 that verifies all low level requirements have a basis in a higher one, and that all higher level requirements decompose into a lower level.

-A review of the WBU2 SysRS, SDS, and SRS for clarity, completeness, correctness and compatibility

-Comparison of the WBU2 SysRS, SDS, and SRS to source level documents

-An evaluation, per section 2.2.3, of the baseline report

-a second party peer review for the source level documents 259 8/10/2010 Responder: WEC Open Closed EICB (Halverson)

Please make the following available in Westinghouse's Documents are available in the Rockville office TVA to respond or Rockville office. per WEC letter WBT-D-2268 dated 8/16/10. provide proposed date of response.

As they may demonstrate that a number of issues raised by, or that will be raised by, the NRC staff are already being resolved by the vendor, we would like to have access to V&V-769 and V&V-770 in the Exception Reports (ER) database for common Q systems.

260 8/10/2010 Responder: WEC Open Open EICB (Halverson)

Please make the following available in Westinghouse's WEC Reviewing to ensure all documents are TVA to respond or Rockville office. available in Rockville office. provide proposed date of response.

The Source level documents for the requirements WBT-D-2268, 8/16/2010 WBT-TVA-0070 Safety Related Digital Logic Cards Circuitry and Related Instrument Racks Restrictions WBT-D-0088 Transmittal Westinghouse comments on WBT-D-2268, 8/16/2010 TVA specification EDSR 52451 Contract Number 65717 Tennessee Valley Authority WBT-D-2268, 8/16/2010 Watts Bar Nuclear Plant Unit 2 NSSS Completion Project

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

WEST-WBT-2008-25 TVA Contract Word Hilmes to determine if this document can be Authorization provided.

261 8/10/2010 Responder: WEC Open Closed LIC-110 Rev. 1 Section 6.2.2 EICB (Halverson) states: "Design features and Please provide the Requirements Traceability Matrix WEC to make available in Rockville ASAP. May TVA to respond or administrative programs that are for generic PAMS and/or any other RTMs applicable to require later submittal per 9/15 meeting. provide proposed unique to Unit 2 should then be WBN2 PAMS. Some requirements in the Software date of response. reviewed in accordance with Requirements Specification are simply not present in Closed to Item 142 current staff positions" the Watts Bar 2 PAMS specific RTM (WNA-VR-00279-WBT). LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the information relied upon in the SE must be docketed correspondence."

262 8/10/2010 Responder: WEC Open Open EICB (Halverson)

In order to facilitate visits to the Rockville office, please WEC Reviewing to ensure all documents are TVA to respond or make the following documents available at the available in Rockville office. provide proposed Rockville office. date of response.

Watts Bar 2 PAMS licensing technical report 00000- WBT-D-1526, 01/28/10; WBT-D-2268, 8/16/10 ICE-37722 Rev. 0 (ML003733136)

Common Q Software Programming manual (ML050350234)

Common Q topical report. (ML031830959) 263 8/11/2010 Responder: WEC Open Open EICB (Carte)

Based on an examination of document available at the Westinghouse Rockville offices (i.e., NA 7.4, WEC 7.2, Addressed in 9/20 - 9/21 audit. TVA to respond or WEC 7.3, CDI-3803, & CDI-3722) a CDI appears to provide proposed identify the verification activities for each critical Combine with item 138 after audit. date of response.

characteristic. These activities appear to be documented on the associated dedication data sheets; therefore, it appears that the Westinghouse Commercial Grade Dedication Plan is called a CDI and the completed CDI data sheets are the commercial grade dedication Report. If so, please provide the CDI for each new (not previously approved) component and the associated completed dedication data sheets.

264 8/11/2010 Responder: WEC Open Open EICB (Carte) Please provide a copy of the commercial grade After the 9/20 - 9/21 audit. TVA to respond or survey(s) applicable to each new (not previously provide proposed approved) Common Q component. Combine with item 138 after audit. date of response.

265 8/11/2010 Responder: WEC Open Open EICB (Carte) Please provide: After the 9/20 - 9/21 audit. TVA to respond or WNA-CD-00018-GEN Rev. 3 provide proposed 00000-ICE-35444 Rev. 1 Combine with item 138 after audit. date of response.

(

266 C 8/11/2010 Responder: Webb/Webber Open Open

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Please provide a high level description of the Foxboro SER Level write-up. Steve Hilmes TVA to respond or IA equipment used at WBN2. This description should provide proposed be more detailed than a brochure on the product line date of response.

(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.

267 8/11/2010 Responder: WEC Open Open EICB (Carte)

By letter dated June 18, 2010 (ML101940236) TVA References will be removed as appropriate. October Letter 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 Software Preliminary Hazard Analysis for the Common Q PAMS Project." A Preliminary Hazard Analysis is required by the SSP.

Please explain.

268 8/19/2010 Responder: WEC Open Open EICB (Carte)

By letter dated March 12, 2010 (ML101680577), TVA TVA to respond or stated that the application specific hardware and Andy to see what can be done. provide proposed software architecture descriptions are addressed in the date of response.

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.

269 8/20/2010 Responder: NRC Open Closed DORL (Bailey) DORL to send the Eagle-21 Audit Report to TVA.

270 8/23/2010 Responder: Clark Open Closed See also Open Item Nod. 41 & 245.

EICB (Carte)

By letter dated June 18, 2009 (ML091560352) the NRC informed Westinghouse that WNA-PT-00058- Close to items 41 and 245 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.

(

271 C 8/23/2010 Responder: WEC Open Closed

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

By letter dated August 20, 2010 TVA docketed a 9/15 meeting and 9/20 audit Requirements Traceability Matrix for the Common Q PAMS (Requirements Phase).This document does not Closed to Item 142 identify the source of each requirement. The Common Q PAMS System Requirements Specification (SysRS -

ML101680578, ML102040483, & ML102040484) does not explicitly identify the origin of each requirement.

The SRP acceptance criteria for requirements specifications is that the origin of the requirements is know. Please explain how to trace each requirement in the SysRS to its origin.

272 7.5.2. 7.5.1 8/26/2010 Responder: Clark Open Open EICB (Marcus) 1 In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations)," (WBNP-96) for Variable 19, "Containment Hydrogen Concentration," Deviation 2 (page 19 of 41), the variable number is listed as 15.

The variable number should be listed as 19.

273 7.5.2. 7.5.1 8/26/2010 Responder: Clark Open Open EICB (Marcus) 1 In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Post accident samples will be obtained from the Variable List (Deviation and Justification for normal sample system.

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.

274. 7.5.2. 7.5.1 8/26/2010 Responder: Clark Open Open EICB (Marcus) a 1 In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations)," (WBNP-96) for Variable 82, "Steam Generator Level Wide Range," Deviation 10 (page 24 of 41), in the last sentence, of the Justification, SC should be SG.

274. 8/26/2010 Responder: Clark Open Open (TVA)

EICB (Singh) b Loose Parts Monitoring System: TR 3.3 refers to section 4.4.6 of the FSAR for description of the loose parts monitoring system. However, this section of the FSAR is not available. TVA to check the reference and respond.

(

275 8/27/2010 Responder: Clark Closed Closed S

i

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Loose Parts Monitoring System: RG 1.133, sections C.1.a and C.1.c address sensor locations and channel separation respectively. TR 3.3, FSAR section 7.6.7 and the DMIMMS-DX System Description do not clearly explain the location or address channel separation per the guidance of RG 1.133. Please update the documents as needed.

276 7.6 7.6 8/27/2010 Responder: Tindell Open Open EICB (Garg)

In order for the staff to review the effects of multi control systems failure, provide the summary of the analyses documenting the effect on the plant based on the following events: (1) loss of power to all control systems powered by a single power supply; (2) failure of each instrument sensor which provides signal to two or more control systems; (3) Break of any sensor impulse line which is used for sensors providing signals to two or more control systems; and (4) failure of digital system based on the common cause software failure affecting two or more control systems.

For each of these events, confirm that the consequences of these events will not be outside chapter 15 analyses or beyond the capability of operators or safety systems.

277 7.6 7.6.3 8/27/2010 Responder: Clark Open Open EICB (Garg)

NUREG 0847, "Safety evaluation report Related to the operation of Watts Bar Nuclear Plant, Units 1 and 2."

has section 7.6.3 which discusses the, "Upper Head Injection Manual Control" system but has been removed from the FSAR. Please provide the information regarding when this system was removed, and the justification for the removal of the system and if the NRC staff has previously reviewed and accepted the removal of the system provide the reference to the staff's SE.

278 7.6 7.6.6 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.6, provide the justification for WBPER980417 and FSAR Change Package adding valves FCV 63-8 and FCV 63-11, which require 1584S0 that power to be removed and will be administratively controlled prior to use of RHR system for plant The following statement is added to the end of cooldown. Provide the P & ID and block diagram FSAR Section 7.6.6. -For FCV-63-8 and -11 showing the operation of these valves. power will be removed and will be administratively controlled just prior to use of the RHR system for plant cooldown (-<350°F) to prevent inadvertent valve opening and over pressurization of the SIP and CCP suction piping:. This statement is added based on special operations section 4.7 of the Safety Injection System Description, N3-63-4001.

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

General Operating Instructions GO-1 and GO-6 The logic and flow diagrams will be attached.

279 7.6 7.6.6 8/27/2010 Responder: Clark Open Open EICB (Garg)

FSAR Amendment 95 did not update section 7.6 For FSAR Section 7.6.6, provide the justification for of the FSAR. FSAR section 7.6 was updated in the addition of protective covers which operator has to amendment 96. In amendment 96 an exception is remove before he can have access to control switch to taken that states that protective covers are not operate two additional valves FCV62-98 and FCV62- installed over the switches for valves FCV62-98

99. and FCV62-99.

280 7.6 7.6.6 8/27/2010 Responder: Clark Open Open EICB (Garg)

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 7.6.8 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.8 in amendment 96, redline version has completely rewritten this section of the FSAR, however, the staff is not able to determine any changes made to the section. Explain what changes have been made to this FSAR Section.

282 7.6 7.6.9 8/27/2010 Responder: Clark Open Open EICB (Garg)

For FSAR Section 7.6.9 which discusses the switch over from injection to recirculation, and is a ESF system, the compliance with IEEE 279 has been removed from the FSAR. Justify this deletion.

283 7.7.5 XX 8/27/2010 Responder: Clark Open Open This item is a follow-up question to EICB (Darbali) item 96.

Follow-up to item 96 On Open Item 96, regarding the implementation of IEN 79-22, part of TVAs response was:

The non-safety-related device/systems within the scope of IEN 79-22 are:

1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

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

Agenda for Weekly Telecom with TVA (I&C Chapter 7 only) rad2EDBB.docx Open Items to be Resolved for SER Approval NR SE FSAR RAI C Prop No. Secti Sectio Issue TVA Response(s) Status/ Current Actions Resolution Path RAI No. & Date Response Comments PO Y/N on n Date C

Please identify the sections of FSAR Chapter 15 that address the failures of these systems.

284 7.7.3 7.4.1 8/27/2010 Responder: Troutman Open Open This item is a follow-up question to EICB item 123 Follow-up to item 123 (Darbali)

Please provide a readable electrical logic diagram of the Volume Control Tank Level Control System.

285 7.3 7.3 8/27/2010 Responder: Clark Open Open This item is a follow-up question to EICB (Darbali) item 22 Follow-up to item 22 Do the control loops meet the requirements of IEEE-279? If not are they isolated from the circuit which meets the requirements of 279.

286 7.7.3 9.3.4.2 8/27/2010 Responder: Webber Open Open EICB (Darbali)

.4 SE 7.7.3, Volume Control Tank Level Control System Low alarm is correct - the setpoint is above the Response is satisfactory. Item will be closed low-low interlock that opens the isolation valve, upon receipt of In FSAR section 9.3.4.2.4 a change was made to the mentioned earlier in the paragraph. the October Letter last paragraph of the Volume Control Tank description Editorial change to correct a typo.

(page 9.3-31 of the Amendment 97 redline), where the "low-low level alarm" was changed to "low level alarm".

Please explain if this deletion was an editorial change to correct a typo.

287 7.3 7.3-1 8/27/2010 The AMSAC start is not included based on Unit 1 Open Open EICB (Darbali)

UFSAR Change Package 1554S0 which states:

In Amendment 95 of FSAR section 7.3.2.3 Further October Letter Considerations, the list of signals that would start the 20 (page 7.3-17. 18 and Table 7.3-1): The auxiliary feedwater motor driven and turbine driven initiating signals for Auxiliary Feedwater (AFW) pumps was moved to table 7.3-1 item 3, Auxiliary are moved from Section 7.3.2.3 to Table 7.3-1, Feedwater. However, item (6) AMSAC was not which lists ESF instrumentation. A reference included in table 7.3-1. to*the Table is added. This change also clarifies that the AFW pumps are started by tljp of both Please explain this omission or state your commitment Turbine-Driven Main Feedwater (MFW) pumps to correct this in a future amendment. rather than all MFW pumps as currently stated since trip of the Standby MFW pump does not initiate AFW. This is consistent with the description of the Auxiliary Feedwater System in Section 10.4.9. This change also deletes AMSAC from the list of AFW start signals. As described in Section 7.7.1.12, the AMSAC system is non-safety and provides a diverse means of initiating AFW and turbine trip under conditions indicative of an ATWS event. AMSAC was not designed as an Engineered Safety Feature and is not included in the ESFAS Technical Specification 3.3.2 for AFW start. Therefore, it does not belong in the Table which identifies ESF instrumentation. The change does not alter the AMSAC functions of

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AFW start and turbine trip. The Switchover from Injection to recirculation and the switchover initiating signals are also added to Table 7.3-1 since they are considered to be part of the ESFAS. The listing of switchover instrumentation is consistent with the description of the switchover function in Section 7.6.9. Also numbered the notes at the bottom of the Table.

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

289 9/2/2010 Responder: Faulkner Open Open (TVA)

EICB (Singh) Provide an ISG4 diversity analysis for the containment high range accident monitors RM-1000.

290 7.7 9/7/2010 Responder: Clark Open Open EICB (Carte) The equation at the bottom of Amendment 99 page 7.7-3 is wrong. There are two ways that this equation is inconsistent with the text above it.

291 7.7 9/7/2010 Responder: Clark Open Open EICB (Carte) The equation at the bottom of Amendment 100 page 7.7-3 is wrong. There are two ways that this equation is inconsistent with the text above it.

292 7.2.5 7.2 9/7/2010 Open Open EICB (Garg)

FSAR Section 7.2, Steam Generator Reference Leg:

By letter dated July 27, 1994, TVA had withdrawn its commitment on Unit 1 to insulate SG reference leg.

TVA had provided an analysis to justify this action which was accepted by the staff. Confirm whether SG reference leg in Unit 2 are insulated and if not then confirm that the analysis which was submitted for Unit 1 is also applicable to Unit 2.

293 7.7.4 7.2.2.3 9/8/2010 Open Open EICB (Marcus)

.5 FSAR Amendment 100, Section 7.2.2.3.5 discusses Steam Generator Water Level and protection against low water level. However, this section does not discuss protection against Steam Generator overfill.

Additionally, FSAR Section 7.2.2.3.4 discusses Pressurizer Water Level and provides minimal information concerning Pressurizer overfill. Please provide a discussion of protection against Pressurizer

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and Steam Generator overfill.

294 7.3 7.3.1.1 9/9/2010 Closure of the main steam isolation valves is not Open Open EICB (Darbali)

.1 included based on Unit 1 UFSAR Change In Amendment 95 of FSAR section 7.3.1.1.1 Function Package 1896S0 which states:

Initiation, item (13) was arranged into paragraph form from what used to be a listing of items (a), (b) and (c). FSAR section 7.3.1.1.1 item 12 contains information which is incorrect and conflicts with The second bullet under item (c) was omitted in the information in the same chapter and other new paragraph. sections. Specifically, item 12 indicates that containment spray initiates Phase B containment Initiates Phase B containment isolation of the isolation and that Phase B initiates main steam following: line isolation. Actually, containment spray, Phase

• Closure of the main steam isolation valves (MSIV) B containment isolation, and main steam isolation are all actuated by high-high containment to limit reactor coolant system cooldown for breaks pressure as shown on Figures 7.3-3 Sheet 4 and downstream of the MSIVs. 6.2.4-21. Both of these figures depict the functional logic shown on configuration control Please explain this omission or state your commitment drawing 1-47W611-88-1. This logic is also to correct this in a future amendment. described in other sections, e.g., 6.2.1.3.10, 6.2.2.5, 6.2.4.2, 10.3.3. This change will clarify the information in 7.3.1.1.1 to resolve these inconsistencies.

295 7.3 7.3.1.1 9/9/2010 References to section 7.6 and 7.7 are not Open Open EICB (Darbali)

.2 included based on Unit 1 UFSAR Change In Amendment 95 of FSAR section 7.3.1.1.2 Process Package 1554S0 item 5 which states:

Protection Circuitry, item (3), references to sections 7.6 and 7.7 were removed. 5 (page 7.3-4): Revise item 3 of Section 7.3.1.1.2 to simplify the discussion of valve position Please explain the reason for removal. information available during the post-LOCA recovery period.

296 7.3 7.3.1.2 9/9/2010 The changes are based on Unit 1 UFSAR Change Open Open EICB (Darbali)

.1 Package 1554S0 item 8 which states:

In Amendment 95 of FSAR section 7.3.1.2.1 Generating Station Conditions, the new paragraph 8 (page 7.3-6): Revise the section summarizing was arranged from what used to be a listing of items the generating station conditions which require (1.b), (1.c), and (2.b), leaving out items (1.a) and (2.a).

protective action. The list is not intended to be a Even if the paragraph contains the word include, thecomplete list of the design basis events which the breaks in items (1.a) and (2.a) should be listed. protection system is designed to mitigate. The change simplifies the summary, adds feedwater Please explain this omission or state your commitment line break, and adds a reference to Chapter 15 for to correct this in a future amendment. identification of the conditions requiring protective action. System Description N3-99-4003 is similarly revised.

297 7.3 7.3.1.2 9/9/2010 The changes are based on Unit 1 UFSAR Change Open Open

.2 EICB Package 1554S0 item 9 which states:

In Amendment 95 of FSAR section 7.3.1.2.2 (Darbali) Generating Station Variables, the following sentence 9 (page 7.3-7 and Table 7.3-2, item 3): Revise was erased: the summary of the generating station variables which are required for initiation of protective

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Post accident monitoring requirements and variables action by the ESFAS. The change simplifies the are given in Tables 7.5-1 and 7.5-2. summary, eliminates repetition, and adds steam generator level and reactor coolant temperature Please explain the reason for removal. (Tavg) as monitored variables. Low-Low SG level starts Auxiliary Feedwater. High-High SG level initiates Feedwater Isolation. Low Tavg coincident with a Reactor Trip also initiates Feedwater Isolation. Low Tavg with a note to identify the interlock with Permissive P-4 (reactor trip), is also added to Table 7.3-2, item 3, which lists the conditions that initiate Feedwater Isolation.

Addition of these variables is consistent with discussions of the Main and Auxiliary Feedwater Systems in Sections 10.4.7, 10.4.9, various Chapter 15 events (e.g., Sections 15.2.10,15.3.1,15.4.2), and Technical Specification Bases 3.3.2 for the P-4 interlock.

System Description N3-99-4003 is similarly revised to add steam generator level and reactor coolant temperature.

298 7.3 XX 9/9/2010 A review of the schematic diagrams for the WBN Open Open EICB (Darbali)

Unit 2 valves listed in SER 3 found the following:

IE Bulletin 80-06 calls for review of engineered safety features with the objective of ensuring that no device (1) For feedwater isolation valves (FCV-3-33, will change position solely because of the reset FCV-3-47, FCV-3-87, and FCV-3-100),

action. feedwater check valve bypass valves (FCV 185, FCV-3-186, FCV-3-187, and FCV In Supplement 3 of NUREG-0847, section 7.3.5, the 188), and upper tap main feedwater isolation staff approved the design modifications proposed by valves (FCV 3-236, FCV-3-239, FCV-3-242, the applicant that would allow certain devices to and FCV-3-245), the Unit 2 equivalent reset remain unchanged upon an ESF reset. The staff also switch and a relay have been added for each found acceptable the applicants justification for some steam generator loop. When the engineered safety-related equipment that does not remain in its safety feature (ESF) signal is reset, the emergency mode after an ESF reset. individual valve will not change state until both the loop and the ESF train reset switches Please confirm whether or not the equipment that was have been reset.

determined in NUREG-0847 and its supplements to remain unchanged upon an ESF reset will still remain (2) For steam generator blowdown isolation unchanged in Unit 2. valves (FCV-43-54D, FCV-43-56D, FCV 59D, FCV-43-63D, FCV-43-55, FCV-43-58, FCV-43-61, and FCV-43-64), the ESF signal is sealed in by means of a seal in relay. The individual valve will not change state until a hand switch in the sample room is used to reopen the individual valve.

(3) For residual heat removal heat exchanger outlet flow control valves (FCV-74-16 and FCV-74-28), the ESF signal is sealed in by the limit switch. The Unit 2 equivalent reset switch has been added at the control room

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control board. When the ESF signal is reset, the individual valve will not change state until the individual reset switch has been reset.

299 Provide Common Q Software Requirements Open Open EICB Specification Post Accident Monitoring System 00000- Attachment 41 contains the Common Q Software ICE-3238 Rev. 5 Requirements Specification Post Accident (Carte) Monitoring System 00000-ICE-3238 Rev. 5 and the affidavit for withholding.

300 Need Radiation Monitoring System Description/Design Open Open Criteria EICB (Singh)

Are detectors different from Unit 1. Describe any differences.

Are there any commercially dedicated parts in the RM-1000? If so, how are they dedicated?

Please confirm that digital communication ports available in RM-1000 are not used.

301 TVA is requested to address the consequences of total loss of CERPI. In addition, address how the actions stipulated in the plant Technical Specifications will be taken when the CERPI system indications are lost. Information notice IN 2010-10 (ML100080281) addresses the need to consider software failures and the actions required to assure that the plant will stay within its licensing basis. Provide FMEA in support of your response.

FSAR Table 7.7-1, Plant Control System Interlocks lists interlock C-11 to block automatic EICB (Singh) rod withdrawal when 1/1 Control Bank D rod position is above setpoint. This interlock capability would be lost in case of total loss of CERPI. How is the rod block assured for this event?

How is automatic rod withdrawal affected in case of total loss of signals from the CERPI to the ICS?

Is this interlock fail safe?

FSAR chapter 15, Section 2.3.2.1states that the resolution of the rod position indicator channel is 5% of span (7.2 inches). The CERPI system accuracy specified in the CERPI System requirements Specification, WNDS-DS-00001_WBT, Rev. 2 is 12 steps or 5.19%. The

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specified system accuracy seems to be greater than the accuracy assumed in the FSAR Chapter

15. Please clarify this anomaly.

302 7.5.2. 7.5.1 09/17/2010 Open Open 1

Item 208 requested a description of the changes that EICB (Marcus) were performed under 10 CFR 50.59 for 16 Unit 1 PAM variables that were identified in Enclosure 1 Item No.6 of the letter dated June 18, 2010 (ML101940236). Please identify the specific 10 CFR 50.59 documentation that applies to each of these 16 variables.

303 7.5.2. 7.5.1 09/17/2010 Open Open 1

Enclosure 1 Item 6 of the letter dated June 18, 2010 EICB (Marcus) included a column to indicate the Unit 2 variable source for each PAM variable and also if the variable was unique to Unit 2. For each variable that was indicated as unique to Unit 2 and the Unit 2 variable source is (1) Foxboro Spec 200, (2) Common Q PAMS, or (3) Foxboro IA, identify the Unit 1 variable source.

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304 7.5.2. 7.5.1 09/17/2010 Open Open 1

EICB (Marcus)

Enclosure 1 Item 6 of the letter dated June 18, 2010 indicated that the Unit 2 variable source for 14 PAM variables is Eagle 21. Please confirm that for each of these 14 variables the Unit 1 variable source is also the Eagle 21.

305 7.5.2. 7.5.1 09/17/2010 Open Open 1

EICB (Marcus)

Enclosure 1 Item 6 of the letter dated June 18, 2010 indicated that the Unit 2 variable source for 2 PAM variables is the Integrated Computer System. Please confirm that for these 2 variables the Unit 1 variable source was the Unit 1 plant computer system.

306 7.1 7.1 FSAR amendment 100, page 7.1-12 provides the Open Open definition of Allowable value which is not consistent with TSTF-493 as allowable value is the value beyond EICB(Garg) which instrument channel is declared inoperable.

307 7.1 7.1 FSAR amendment 100, Section 7.1, page 7.1-12, Open Open definition of Acceptable as found tolerance is not in accordance with TSTF-493 as AAF is the limit beyond which the instrument channel is degraded but may be operable and its operability must be evaluated. Also it EICB(Garg) states that AAF is based on measurable instrument channel uncertainties, such as drift, expected during the surveillance interval. These wording should be revised to agree with the wording given in RIS2006-17 as these wordings are very vague. Also it states that RPS functions use double sided tolerance limits for the AAF. Since AAF is a band it will always be double sided and therefore, this clarification does not mean anything and it clouds the issue.

308 7.1 7.1 FSAR Amendment 100, Section 7.1, page 7.1-13, definition of Acceptable as left tolerance is not in accordance with TSTF-493 as it states that this may EICB(Garg) take calibration history into consideration. This is very vague and ambiguous. Also it states that RPS functions use double sided tolerance limits. Since ALF is a band it will always be double sided and therefore, this clarification does not mean anything and clouds the issue.

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309 7.1 7.1.2.1 FSAR amendment 100, Page 7.1-14, Westinghouse Open Open

.9.1 setpoint methodology, states that AAF is the algebraic sum of of the .. This is not acceptable. As algebraic EICB(Garg) sum is non conservative compared to the SRSS method and will mask the operability of the instrument channel and therefore, it is not acceptable to the staff.

It also make the statement that ALT may take calibration history into consideration which is vague and ambiguous.

310 7.1 7.1.2.1 FSAR amendment 100, Page 7.1-14, TVA setpoint Open Open

.9.2 methodology, states that for AAF .and other measurable uncertainties as appropriate (i.e., those EICB(Garg) present during calibration.) should be changed to present during normal operation Also on page 7.1-15 , states that ALT may take calibration history into consideration which is vague and ambiguous.

311 7.1 7.1 Both Westinghouse and TVA setpoint methodology do Open Open not have any discussion on single sided calculation.

Please confirm that single sided calculation has not EICB(Garg) been used for all setpoints with TSTF-493 and provide a statement to that effect in the FSAR.

312 7.0 By letter dated September 10,2010, TVA provided the Open Open summary evaluation of 50.59 reports which were related to FSAR Chapter 7.0. However, these EICB(Garg) evaluation only covers Amendments 0 thru 8. Provide all other evaluation which have been done since these amendments and which forms the basis for FSAR Chapter 7.0 systems.

313 7.7.8 7.7.1.1 EDCR 52408 (installation of AMSAC in Unit 2) states Open Open 2 that Design Criteria WB-DC-40-57 needs to be modified to reflect AMSAC in Unit 2.

EICB (Darbali)

1. Has WB-DC-40-57 been completed for Unit 2? If so, please submit.

2. If WB-DC-40-57 has not been completed for Unit 2, please give an estimated date of completion and submittal.

3. Please submit WB-DC-40-57 for Unit 1 and identify any changes to the Unit 2 version.

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314 7.3 7.3 The following 50.59 changes were listed in the March Open Open 12 RAI response letter (item 10) but were not included in the September 9 submittal of 50.59 safety evaluations. Please submit the 50.59 safety EICB (Darbali) evaluations for the following changes:

• DCN 38842 (Revise OTT and OPT turbine runback setpoints)

• DCN 50991 (Install Test Points)

• DCN 51124 (Eliminate spurious ICS alarms associated with the SSPS 315 7.5.3 7.5.3 IE Bulletin 79-27 required that emergency operating procedures to be used by control room operators to attain safe shutdown upon loss of any Class IE or non EICB(Garg)

Class IE bus are adequate. WBN1 has performed the review and documented their conclusion. Confirm that WBN2 emergency procedures are adequate to achieve safe shutdown in the event of loss of any Class IE or non-Class IE bus.

316 7.5.2. 7.5 TVA has provided various documents in support of 3 RM-1000 high range monitors for WBN2.

Please clarify the following:

RM-1000 v1.1 Software Verification Report 04508006 (Sequoyah)

EICB (Singh)

RM-1000 v1.2 Software Verification Report 04508006 (Sequoyah)

RM-1000 System Verification Test Results (Sequoyah)

These documents were prepared for the Sequoyah plant. IS the version provided applicable to WBN2?

Please confirm and explain if these documents are applicable to WBN 2 as provided or with differences?

317 7.5.2. 7.5 TVA has provided a proprietary and a non-proprietary 3 version of Technical Manual for RM-1000 Digital Radiation Processor under ML101680582 and ML101680587).

EICB (Singh)

(i) Are these documents applicable to WBN2 as provided (October 2003 version).

(ii) Why is DCN38993-A attached at the back of the proprietary version? It is for WBN1 Turbine Governor Control Valve.

(iii) This document does not state the requirements for RM-1000 units. Please provide a document that states the requirements for the RM-1000 radiation monitors for WBN2.

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318 7.5.2. 7.5 TVA has provided the following documents for RM-3 1000 equipment qualification:

Qualification Test Report for RM-1000 Processor Module and Current-To-Frequency Converter 04508905-QR (January 2001)

Qualification Test Report Supplement, RM-1000 Upgrades 04508905-1SP (June 2006)

Qualification Test Report Supplement, RM-1000 Upgrades 04508905-2SP (June 2008)

EICB (Singh)

Qualification Test Report Supplement, RM-1000 Upgrades 04508905-3SP (May 2008)

Please clarify whether all of these are fully applicable to WBN2 or are they applicable with exceptions? If with exceptions, then please clarify what those are.

Supplement 3 was issued one month prior to supplement 2. Please explain the reason for the same.

319 7.5.2. 7.5 TVA provided System Verification Test Results 3 04507007-1TR (July 1999) for Sequoyah to support test verification. However, the document states (page v) that it is not applicable for high range monitors with an action noted for fixing a problem with the high EICB (Singh) range RM-1000 monitors on page vi. TVA to respond to the following clarifications:

Has the anomaly noted on page vi been resolved for the high range monitors?

Provide the high range verification document for WBN2.