ML102571786

OL - FW: Updated NRC I&C RAI Matrix

ML102571786
Person / Time
Site:	Watts Bar
Issue date:	09/07/2010
From:	Office of Nuclear Reactor Regulation
To:	Division of Operating Reactor Licensing
References
Download: ML102571786 (48)

Text

WBN2Public Resource From: Poole, Justin Sent: Tuesday, September 07, 2010 10:04 AM To: Garg, Hukam; Carte, Norbert; Darbali, Samir; Halverson, Derek; Marcus, Barry; Singh, Gursharan Cc: WBN2HearingFile Resource

Subject:

FW: Updated NRC I&C RAI Matrix Attachments: 20100827 Open Items List Master - TVA Update 9-2.xlsx Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)4152048 email: Justin.Poole@nrc.gov From: Crouch, William D [1]

Sent: Tuesday, September 07, 2010 7:16 AM To: Bailey, Stewart; Poole, Justin

Subject:

FW: Updated NRC I&C RAI Matrix See attached updated matrix.

William D. (Bill) Crouch (423) 3652004 WBN (256) 7777676 Cell From: Clark, Mark Steven Sent: Friday, September 03, 2010 2:01 PM To: Crouch, William D; Hilmes, Steven A Cc: Dimitrew, Frederik; Tindell, Tommy Randall; Edmondson, Louvain L Jr

Subject:

Updated NRC I&C RAI Matrix All:

Attached is the updated matrix from the NRC meetings.

Bill:

Please provide this matrix to the NRC.

Fred/Tommy/Louvain:

There are approximately 20 new items added from last weeks matrix. The NRC has added two new reviewers to the project and both expect to have additional questions as they progress through the process.

Regards, Steve 1

Steve Clark Bechtel Power Corp.

Control Systems Watts Bar 2 Completion Project Phone: 865.632.6547 Fax: 865.632.2524 e-mail: msclark0@tva.gov 2

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 98 Mail Envelope Properties (19D990B45D535548840D1118C451C74D67862C595C)

Subject:

FW: Updated NRC I&C RAI Matrix Sent Date: 9/7/2010 10:03:53 AM Received Date: 9/7/2010 10:03:56 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:

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

Tracking Status: None "Garg, Hukam" <Hukam.Garg@nrc.gov>

Tracking Status: None "Carte, Norbert" <Norbert.Carte@nrc.gov>

Tracking Status: None "Darbali, Samir" <Samir.Darbali@nrc.gov>

Tracking Status: None "Halverson, Derek" <Derek.Halverson@nrc.gov>

Tracking Status: None "Marcus, Barry" <Barry.Marcus@nrc.gov>

Tracking Status: None "Singh, Gursharan" <Gursharan.Singh@nrc.gov>

Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 1288 9/7/2010 10:03:56 AM 20100827 Open Items List Master - TVA Update 9-2.xlsx 182302 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 4 19-Nov-09 Originator: EICB (Carte) 1/13/10 Public Meeting: Responder: Webb Date: 3/15/2010 Responsibility: NRC TVA to docket a D3 November 19, 2010 January 13, 2010 NNC 11/19/09: LIC-110 Rev. 1 Section (All) and TVA (Hilmes) analysis for the ML093230343 RAI 4 March 12, 2010 6.2.2 states: "Design features and Please identify the information that will be submitted for each unreviewed digital I&C system TVA identified a schedule for docketing some Post Accident Monitoring System (PAMS) TVA to address the question of how a Foxboro IA common mode or Common Q PAMS. June 30, 2010 administrative programs that are unique and component and the associated docketing schedule. documentation, and the new setpoint methodology. No other documentation was discussed. complete failure impacts the plant accident analysis as described in August 11, 2010 to Unit 2 should then be reviewed in Chapter 15 of the FSAR. (Demonstrate segments are independent NNC 8/19/10: TVA accordance with current staff Add: By letter dated June 30, 2010, TVA docketed WNA-LI-00058-WBT-P &-NP, "PAMS and how a common mode or complete failure is prevented by power segmentation analysis positions.TVA will supply a description Licensing Technical Report." WNA-LI-00058-WBT-P Section 4.11 addressed CCF and BTP 7- supply design and segmentation.) has been received - of the changes implemented at Unit 1

19. NRC to review. but have not been reviewed for Unit 2 NNC 8/19/10: The justification for not performing and D3 analysis by the NRC technical staff...TVA will TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 4 on Page 3 of 15): TVA contained in the CQ PAMS Licensing Technical Report is not also provide the applicable portion of the responded to this request for additional Information acceptable. TVA to docket a D3 analysis for the CQ PAMS. This FSAR and the proposed TSs...In will be responded to in Item 64. addition, the staff should review items Foxboro I/A Segmentation Analysis Calculation DCSSEGMENT, Rev. 0 submitted on TVA that are identical for WBN Units 1 and 2 letter dated August 11, 2010. NNC 8/25/10: The segmentation analysis has been read. Please that have not previously been reviewed explain why it is believed that faliure will not propagate over the peer- and approved by the NRC staff. These Data Storm Testing to-peer network. items are changes in the design and licensing basis for WBN Unit 1 that TVA The procurement specification (Attachment 23) for the Foxboro I/A sytem section 3.11.2 Looking for an architectural description of the network has implemented without NRC prior requires the following as part of the Factory Acceptance Test: interconnections similar to the ICS overview, identification of approval under the 10 CFR 50.59 credible failure modes caused by the mesh network and what process."

Tests shall include realistic message traffic on all communications networks and component(s) prevent mesh network failures from disabiling the NNC 4/15/10: The response addresses subnetworks. In addition, all digital interfaces to external environments such as plant entire system. What prevents a segment failure from propagating many systems and should be read by all computer interface shall be tested to withstand broadcast storm events without across the mesh network and affecting other segments. EICB reviewers.

degradation in the control systems performance. Also, the control system shall be tested for broadcast storm events resulting from component failures on internal communication networks without degradation in the control systems performance.

6 December 11, 2009 (ML093431118, RAI 6) NRC POC: EICB (Garg) By letter dated February 5, 2010: TVA provided the Unit 2 setpoint methodology (WCAP- Date: 2/16/2010 Responsibility: NRC TVA to reference TI-28 for NNC: WCAP-12096 Rev. 7 177044-P Revision 0 - dated December 2009). (Garg) as found and as left (ML073460281) is in ADAMS.

Amendment 95 of the FSAR, Chapter 7.3, shows that change 7.3-1 consists of updating a The Westinghouse Setpoint methodology document (WCAP-17044-P value. Also provide the reference from revision 5 to revision 7 and making it applicable to Unit 1 only, while adding a TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 6 on Page 7 of 15): TVA Revision 0) identifies that the intermediate and source range reference to FSAR NNC: WCAP-12096 Rev. 8 is the new reference, applicable only to Unit 2. responded to this request for additional Information. calculations were performed by TVA (2-NMD-092-0131). Please Section 7.1 for the current revision for Unit 1.

provide the intermediate and source range calculations performed by setpoint methodology.

Reagan, J. R., "Westinghouse Setpoint Methodology for Protection Systems, Watts Bar Units 1 a. TVA to docket Rev. 8 and identify that Rev. 8 is the current revision for Unit 1. TVA to TVA (2-NMD-092-0131). NNC 4/15/10: Hukam, please update and 2, Eagle 21 Version," WCAP-12096 Rev. 7, (Westinghouse Proprietary Class 2). Unit 1 Only identify any NRC approval of Rev. 8. this open item as appropriate.

The Westinghouse Setpoint methodology document (WCAP-17044-P WCAP Westinghouse Setpoint Methodology for Protection System, Watts Bar Unit 2, Eagle 21 In accordance with item 2, below, there is no change to the methodology, therefore revision 8 Revision 0) identifies that the undervoltage and underfrequency TVA to docket Rev. 8 and identify that Version, WCAP-17044-P. Unit 2 Only. is not included in this response. calculations were performed by TVA (2-27-068-0031). Please provide Rev. 8 is the current revision for Unit 1.

the undervoltage and underfrequency calculations performed by TVA TVA to identify any NRC approval of Please provide both setpoint methodology documents identified above. Westinghouse letter WAT-D-10502 (Attachment 1) describes the two changes to WCAP- (2-27-068-0031). Rev. 8.

12096 Revision. 8. The first change addresses the containment sump level transmitter replacement. This change was submitted under 50.59 summary report (ML073460444, Page Work with Item 7 for WCAP-12906 issues. TVA to describe how TVA calculations 77). The second change is to delete the power range negative flux rate trip. This item was for Unit 2 are different than Unit 1. If submitted as a Technical Specification change (ML073201052). The Technical Specification they are the same, TVA to docket such change was subsequently approved. statement under oath and Affirmation.

The current revision of Unit 1 WCAP-12096 is Revision 9. Revision 9 was issued to make the changes required by the Steam Generator Replacement Project. Unit 2 is using the original steam generators, therefore the changes in Revision 9 are not applicable to Unit 2.

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

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

7 December 11, 2009 (ML093431118, RAI 7) NRC POC: EICB (Garg) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 7 on Page 7 of Date: 1/13/2010 Responsibility: NRC Same as Open Item 6 NNC 4/15/10: Related to 15): TVA responded to this request for additional Information. (Garg) above. setpoints and SE Section 7.1.3.1.

File: rad4AB2F.xlsx Page 1 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments The setpoint methodology has been reviewed and approved by the NRC staff in Section 7.1.3.1 RAI response received. NRC to review response.

of NUREG-0847 (ML072060490), NUREG-0847 Supplement No.4 (ML072060524), and a. TVA will submit WCAP-12096, Rev. 8 if there is a change to the NNC 4/15/10: Hukam, please NUREG-0847 Supplement No. 15 (ML072060488). methodology. TVA will submit WCAP-12096, Rev. 8 if there is a change to the update this open item as methodology. appropriate.

Please describe all changes from the methodology that has been reviewed and approved by the No change in methodology, therefore WCAP-12906, Revision 8 is not staff. submitted. TVA will supply the 50.59 letter for Rev. 8 TVA to provide Rev. 8 of the Unit 1 document (which is the current

b. TVA will supply the 50.59 letter for Rev. 8 TVA to locate transmittal letter that submitted Rev. 7. one) if there is a change in methodology and identify how the Westinghouse letter WAT-D-10502 (Attachment 1) describes the two changes TVA to determine the last revision of WCAP-12096 where there Unit 2 document differs from it.

to WCAP-12096 Revision. 8. The first change addresses the containment was a change in methodology.

sump level transmitter replacement. This change was submitted under 50.59 summary report (ML073460444, Page 77). The second change is to delete Work with Item 6 for WCAP-12906 issues.

the power range negative flux rate trip. This item was submitted and approved as a Technical Specification change (ML073201052).

c. TVA to locate transmittal letter that submitted Rev. 7.

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

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

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

10 December 11, 2009 (ML093431118, RAI 10) NRC POC: EICB (Darbali) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 10 on Page 8 of Date: 3/15/2010 Responsibility: NRC NRC Review NNC 4/15/10: Related SE 15): TVA responded to this request for additional Information. (Darbali) Section 7.3.

The original SER on Watts Bar (NUREG-0847) documents that the scope of the review of NRC evaluating TVA response.

FSAR Section 7.3, Engineered Safety Features Actuations System, included: included single- TVA Letter (ML073550386) dated FEB 26 1992: docketed WCAP-12374 line, function logic and schematic diagrams, and descriptive information for the ESFAS and Rev. 1 (ML080500664). NRC to discuss document requirements and provide additional those auxiliary supporting systems that are essential to the operation of either the ESFAS or the information to resolve this item.

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

12 December 11, 2009 (ML093431118, RAI 12) NRC POC: EICB (Darbali) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 12 on Page 13 Date: 3/15/2010 Responsibility: TVA Closed NNC 4/15/10: Related SE of 15): TVA responded to this request for additional Information Section 7.4.

The original SER on Watts Bar (NUREG-0847) documents that the scope of the review of TVA provided the following:

FSAR Section 7.4, "Systems Required for Safe Shutdown," included single-line and schematic A revised response was included in the 7/30 letter that provides the requested diagrams: "The scope of the review of the systems required for safe shutdown included the information. 1. Description of what is different from Unit 1 single-line and schematic diagrams and the descriptive information for these systems and for the auxiliary systems essential for their operation." 2. Road map between functions listed in 7.4 and the FSAR section that describes the equipment that performs the function. Item Please provide the single-line and schematic diagrams for the systems required for safe Closed.

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

13 December 11, 2009 (ML093431118, RAI 13) NRC POC: EICB (Garg) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 13 on Page 14 Date: 3/15/2010 Responsibility: NRC This item is closed TS have been docketed.

of 15): TVA responded to this request for additional Information (Garg) for chapter 7. NRC Chapter 7 and Chapter 16 of Amendment 95 to the FSAR do not include any setpoint values. RAI response received. Westinghouse is completing the setpoint will review T.S. NNC 4/15/10: Related to setpoints and Please describe how and when setpoint values (e.g., TS allowable values) will be provided for calculations which will be completed by May 11, 2011. NRC to review under different SE Section 7.1.3.1.

Unit 2. response. chapter.

NNC 4/15/10: Hukam, please update Please describe the information that will be provided to justify the acceptability of these values. this open item as appropriate.

Related to SE Section 7.1.3.1.

17 December 22, 2009 (ML093560019, item 4) NRC POC: EICB (Darbali) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC NRC Review (Darbali)

Identify precedents in LARs, if any, for the solid state protection system. Also, identify any By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Awaiting NRC evaluation of response.

hardware deviation from the precedent. No. 4).

19 December 22, 2009 (ML093560019, item 6) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC NRC Review (Garg)

File: rad4AB2F.xlsx Page 2 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Verify that the containment purge isolation radiation monitor is the same as used in Watts Bar By latter dated April 27, 2010 TVA responded to this request for information (Enclosure 1, Response unacceptable. Should discuss all changes.

Unit 1, or identify any hardware changes. Item No. 6) for the ratemeter.

A newer model, RD-52, of the RD-32 detector assembly used in Unit 1. The detector assembly replacement is due to obsolescence and improved reliability.

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

21 December 22, 2009 (ML093560019, item 8) NRC POC: EICB (Garg) Date: 5/25/10 Responder: D. McNeil Date: 5/24/10 Responsibility: TVA NRC Review For the Foxboro Spec 200 platform, identify any changes in hardware from the precedent No vendor system description is available for the Foxboro Spec 200 system. The hardware The understanding reached in the meeting on April 14, 2010, was that systems. Provide the design report and the equipment qualification information. description and qualification documents are provided on a component level basis. A TVA TVA should identify any changes, or state under oath and affirmation generated system description is provided to assist the reviewer. The hardware differences that there were no changes. If there were no changes, then the NRC from the unit 1 systems are provided in the loop and card comparison documents. As agreed would confirm by inspection.

with the reviewer, the component level documents are not required to be submitted at this time, but may be required later based on the review of attached documents. The following A revised response was requested at the 5/24/10 public meeting.

TVA generated documents are provided (Attachment 1):

1. Analog loop comparison

2. Analog card comparison

3. Analog system description 22 December 22, 2009 (ML093560019, item 9) NRC POC: EICB (Darbali) Date: 4/27/10 Responder: McNeil Date: 4/27/10 Responsibility: NRC NRC Review (Garg)

Verify the auxiliary feedwater control refurbishment results in a like-for-like replacement, and By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item TVA should confirm if Woodward Governer is the only change.

identify any changes from the identified precedents. No. 9).

See Item 285 for follow up question.

The control function of the Auxiliary Feedwater (AFW) Flow for Steam Generator Level is the same as Unit 1. The controllers and signal modifiers/conditioners are Foxboro SPEC 200 discrete analog modules as Unit 1 control loops. The only different Unit 1 uses a 10-50ma signal and Unit 2 is using a 4-20ma. The SPEC 200 control modules operate with a 0-10mv system for both Unit 1 and Unit 2.

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

The four (4) control loops are described below:

2-P-3-122A This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varying valve 2-PCV-3-122. Differential Pressure Indicating Controller 2-PdIC-3-122A (on panel 2-M-4) can be used either in manual mode or in automatic mode. This loop controls this valve from the Main Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the normal position.

2-P-3-122C This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varying valve 2-PCV-3-122. Differential Pressure Indicating Controller 2-PdIC-3-122C (on panel 2-L-

10) can be used either in manual mode or in automatic mode. This loop controls this valve from the Auxiliary Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the auxiliary position.

2-P-3-132A 24 December 22, 2009 (ML093560019, item 11) NRC POC: EICB (Carte) During the January 13, 2010 meeting, TVA presented a schedule for completing various Date: 4/27/10 Responsibility: NRC Closed to Item 43 NNC 4/30/10: Carte to address documents for the PAMS system. This schedule did not support TVA's desired schedule. (Carte & Darbali) response with respect to PAMS Provide a schedule by the January 13, 2010, meeting for providing information in accordance TVA was so informed and said they would work on improving the schedule. TVA said that the The explanations provided by TVA (that certain information is not and Darbali to address response with I&C Interim Staff Guidance (ISG) 6. setpoint methodology would be provided shortly. No other systems of documentation was required) are unacceptable. with respect to RM1000.

discussed.

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

By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item No. 11).

By letter Dated June 18, 2010 (see Attachment 3) TVA providded a table, "Watts Bar 2 -

Common Q PAMS ISG-6 Compliance Matrix."

25 December 22, 2009 (ML093560019, item 12) NRC POC: EICB (Singh) Date: 4/27/10 Responder: TVA Date: 07/28/2010 Responsibility: NRC NRC Review FSAR Section 7.5.1 Post (Singh) Accident Monitoring Instrumentation - SE Section File: rad4AB2F.xlsx Page 3 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments For the containment radiation high radiation monitor, verify that the information provided by TVA By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item NRC review in progress. Instrumentation - SE Section is consistent with the information provided with the previously-approved license amendment No. 12). 7.5.2 request for the Duane Arnold plant or provide Phase 3 information. Need Radiation Monitoring System Description/Design Criteria Are detectors different than Unit 1 Are there any commercially dedicated parts in the RM-1000.

State digital communication ports are not used.

28 December 22, 2009 (ML093560019, item 15) NRC POC: EICB (Garg) Date: 4/27/10 Responder: Mark Scansen Date: 4/27/10 Responsibility: NRC Provide 50.59 (Darbali)

For the turbine control AEH system, verify that the refurbishment results in a like-for-like By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Provide 50.59 evaluation. Response acceptable.

replacement. No. 15).

The requested 50.59 is included in Attachment __.

30 December 22, 2009 (ML093560019, item 17) NRC POC: EICB (Garg) Date: 4/27/10 Responder: Clark Date: 4/27/10 Responsibility: NRC TVA Revised (Garg) Response. TVA to Regarding the refurbishment of I&C equipment, identify any component digital upgrades and, if By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Does not state if there are no other upgrade which contain imbedded document revised so, provide the supporting design information. No. 17). digital processor. Revised response acceptable. response.

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

34 February 4, 2010 NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC NRC Review (All)

In the December 15, 2009 public meeting, TVA listed the significant changes made since the By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Awaiting NRC evaluation of response.

Watts Bar Unit 1 Licensing (see below). For each of the following significant changes: No. 21).

1) Is the change unique to Unit 2, or will it be the same as whats currently installed in Unit 1? Remove all references to Elbow Tap Methodology from Unit 2 Licensing Bases.

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?

Chapter 7.1 - Introduction Responsibility: NRC (Garg)

Reactor Coolant System Flow Rate Measurement Design Basis Analysis Parameters Loose Parts Monitoring Responsibility: NRC (Singh)

Chapter 7.2 - Reactor Trip System Responsibility: NRC Deletion of Neutron Flux Negative Rate Trip (Garg)

Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump Reactor Coolant System Flow Rate Measurement Foxboro I/A Chapter 7.3 - ESFAS Responsibility: NRC (Darbali)

Design Basis Analysis Parameters Alternate Method for Use of Condenser Steam Dump Chapter 7.5 - Instrumentation Systems Important to Safety Responsibility: NRC (Carte)

Plant Process Computer Replacement Containment Sump Level Transmitter Replacement Safety Injection Systems Cold Leg Accumulator Level Measurement System Common Q/PAMs FSAR Section 7.5 Instrumentation Systems Important To Safety - SE Section 7.5.2 Chapter 7.6 - All Other Systems Required for Safety TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 1 on Page Responsibility: NRC 1 of 15): TVA responded to this request for additional Information. (Garg)

Plant Process Computer Replacement Loose Parts Monitoring System NRC POC: EICB (Singh) Responsibility: NRC (Singh)

Chapter 7.7 Control Systems Responsibility: NRC (Garg)

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) 35 February 18, 2010 NRC POC: EICB (Singh) Date: Responder: Clark Date: 2/18/2010 Responsibility: TVA TVA to provide a LIC-110 Section 6.2.2 states: Design File: rad4AB2F.xlsx Page 4 of 45 Tab: Open Items more detailed features and administrative programs

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Please provide a system description of the Digital Metal Impact Monitoring System that TVA Letter dated March 12, 2010 Enclosure 1, item 4 responded to this request for Description provide is not of sufficient detail to allow a regulatory more detailed features and administrative programs contains sufficient detail to support a review of this system using current staff positions. information. determination. TVA to send the proprietary information for NRC description of the that are unique to Unit 2 should be review. At the 9-2 meeting G. Singh stated the system loose parts monitoring reviewed in accordance with the current The attached non-proprietary system description was developed from proprietary descriptionn provided was acceptable and the proprietary system. staff positions. Unit 2 FSAR Section Westinghouse Watts Bar Unit 2 DMIMS-DX Operations and Maintenance Manual, 1TS3176 information was not required at this time. 7.6.7, Loose Part Monitoring (LPMS)

Rev.0 (Reference 1). Westinghouse approved this non-proprietary response via letter WBT-D- system Description, describes a system

____ dated August , 2010. The system description is contained in Attachment 2. design that is unique to Unit 2.

37 February 18, 2010 NRC POC: EICB (Marcus) Date: 5/25/10 Responder: Clark Date: 2/18/2010 Responsibility: TVA NRC Review FSAR Section 7.5, Instrumentation Is the plant computer a safety-related display system? As identified in TVA letter dated March 12, 2010, Enclosure 1, item 2, the plant computer August 19, 2010 - TVA to submit markup of FSAR Amendment 100. System Important to Safety, consists of system is non-safety related. two major subsections: 7.5.1, Post Accident Monitoring Instrumentation FSAR section 7.5 describes both safety and non-safety related devices and systems. FSAR (PAM), and 7.5.2, Plant Computer section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA letter to System.

the NRC dated September 1, 2010.

Regulatory Guide 1.70, Standard format and content of Safety Analysis Reports for Nuclear Power Plants, Revision 3 38 NRC POC: EICB (Marcus) Date: 5/25/10 Responder: Clark Date: Responsibility: TVA NRC Review The slides presented at the December Please provide a description of the interfaces between: (1) the Safety Parameter Display FSAR section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA August 19, 2010 - TVA to submit markup of FSAR Amendment 100. 15, 2010 meeting (ML093520967)

System and (2) the Technical Support Center and Nuclear Data Links with the plant control and letter to the NRC dated September 1, 2010.. indicate that the plant process computer safety systems. This Description should contain sufficient detail to support a review of these has been replaced.

interfaces using current staff positions.

41 February 19, 2010: Audit NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 2/19/2010 Responsibility: TVA TVA to docket FSAR Section 7.5.1 Post Accident Please provide the following Westinghouse documents: Items (1) and (2) were docketed by TVA letter dated April 8, 2010. The SysRS and SRS incorporate requirements from many other information indetified Monitoring Instrumentation - SE Section (1) WNA-DS-01617-WBT Rev. 1, "PAMS System Requirements Specification" documents by reference. in ISG6. 7.5.2 (2) WNA-DS-01667-WBT Rev. 0, "PAMS System Design Specification" Items (3), (4) and (5) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g," WNA-PT-(3) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g" 00058-GEN Rev. 0, "Testing Process for Common Q Safety systems" and WNA-TP-00357- NNC 8/25/10: (3) An earlier version of this report was docketed for the TVA to provide date See also Open Item Nos. 226 & 270.

Please provide the following Westinghouse documents or pointers to where the material was GEN Rev. 4, "Element Software Test Procedure" are available for audit at the Westinghouse Common Q topical report; therefore, there should be no problem to when information will reviewed and approved in the CQ TR or SPM: Rockville office (Westinghouse letter WBT-D-1526, Reference 6). docket this version. (4) Per ML091560352, the testing process be docketed.

(4) WNA-PT-00058-GEN Rev. 0, "Testing Process for Common Q Safety systems" document does not address the test plan requirements of the SPM.

(5) WNA-TP-00357-GEN Rev. 4, "Element Software Test Procedure" 3 will be addressed during September 20 and 21 audit. Please provide a test plan that implements the requirements of the 4 Westinghouse will develop a WBN2 Specific Test Plan to compensate for WNA-PT- SPM.

00058-GEN. TBD 5 WNA-TP-00357-GEN superseded by the SPM compliance matrix in the Licensing Technical Report next revision.

43 February 19, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 5/25/10 Responsibility: WEC TVA to docketed FSAR Section 7.5.1 Post Accident The PAMS ISG6 compliance matrix supplied as Enclosure 1 to TVA letter dated February 5, The PAMS ISG6 compliance matrix supplied as Enclosure 1 to TVA letter Revised compliance matrix is unacceptable. requested material. Monitoring Instrumentation - SE Section 2010 is a first draft of the information needed. The shortcomings of the first three lines in the dated February 5, 2010 is a first draft of the information needed. 7.5.2 matrix are: NNC 8/12/10: It is not quite enough to provide all of the documents TVA to provide date By letter dated April 8, 2010 TVA provided the PAMS Licensing Technical requested. There are two possible routs to review that the NRC can when information will NNC 8/25/10: A CQ PAMS ISG6 Line 1: Section 11 of the Common Q topical report did include a commercial grade dedication Report provided additional information. undertake: (1) follow ISG6, and (2) follow the CQ SPM. The TVA be docketed. compliance matrix was dockated on: (1) program, but this program was not approved in the associated SE. Westinghouse stated that response that was orriginally persued was to follow ISG6, but some of February, 5 12010, (2) March 12, 2010, this was the program and it could now be reviewed. The NRC stated that TVA should identified Attachment 3 contains the revised Common Q PAMS ISG-6 Compliance the compliance items for ISG6 were addresed by referencing the & (3) June 18, 2010. The staff has what they believe was previously reviewed and approved. Matrix, dated June 11, 2010, that addresses these items (Reference 13). SPM. The NRC approved the CQ TR and associated SPM; it may expressed issued with all of these be more appropriate to review the WBN2 PAMS application to for compliance evaluations. The staff is still Line 2: TVA stated the D3 analysis was not applicable to PAMS, but provided no justification. By letter Dated June 18, 2010 (see Attachment 3) TVA providded a table, adherence to the SPM that to ISG6. In either path chosen, the waiting for a good compliance The NRC asked for justification since SRP Chapter 7.5 identified SRM to SECV-93-087 Item "Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix." applican should provide documents and a justification for the evaluation.

II.Q as being SRP acceptance criteria for PAMS. acceptability of any deviation from the path chosen. For example, it This item will be addressed in the next revision of the Licensing appears that the Westinghouse's CDIs are commercial grade Line 3: TVA identified that the Design report for computer integrity was completed as part of the Technical Report. dedication plans, but Westinghouse maintains that they are common Q topical report. The NRC noted that this report is applicable for a system in a plant, commercial grade dedication reports; this apparent deviation should be and the CQ topical report did no specifically address this PAMS system at Watts Bar Unit 2. justified or explained.

NRC then concluded that TVA should go through and provide a more complete and thorough compliance matrix.

47 April 8, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC/Hilmes Date: 4/8/10 Responsibility: TVA TVA to provode aditional FSAR Section 7.5.1 Post Accident The PAMS System Requirements Specification (SysRS) references RG 1.97 Rev. 3 where the The licensing basis for WBN Unit 2 is Regulatory Guide 1.97 Revision 2. The Common Q TVA provided information by letter dated July 30, 2010 information as described. Monitoring Instrumentation - SE Section FSAR References Rev. 2. Please explain. PAMS system was designed to Regulatory Guide 1.97 Revision 3, which is why the basis for (ML102160349) - See Enclosure 1 Item No. 5. 7.5.2 the System Requirements Specification referencinges revision 3. In order to resolve this discrepancy an engineering evaluation of the Common Q PAMS was performed. NNC 8/9/10: There are two aspects of this issue. The first aspect has been addresed by the response. The second aspect is: How could Attachment 2 contains an engineering evaluation of the Common Q PAMS design against the Westinghouse Design, and TVA approve a design to the wrong requirements of Reg. Guide 1.97 Rev. 2. The evaluation concluded that the Common Q requirement?

PAMS 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.

File: rad4AB2F.xlsx Page 5 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 49 April 8, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 4/8/10 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident Please provide 00000-ICE-30156 Rev. 6. The PAMS SysRS incorporates sections of this Per Westinghouse letter WBT-D-2024 (Reference 7), this document is available for audit at the This information must be on the docket. requestd information Monitoring Instrumentation - SE Section document by reference. Westinghouse Rockville office. 7.5.2 TVA to provide date Document not received from This document is being submitted this week. when information will Westinghouse on schedule. This item be docketed. will be delayed.

50 April 8, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 4/8/10 Responsibility: TVA TVA to revise FSAR Section 7.5.1 Post Accident response or other Monitoring Instrumentation - SE Section How should the "shall" statements outside of the bracketed requirements be interpreted? These sections are descriptive text and not requirements. The next revision of the Watts Bar TVA response is inconsistent (e.g., WNA-DS-01667-WBT Rev. 1 page documentation. 7.5.2 Unit 2 PAMS System Requirements Specification will remove shall from the wording in those 1-1, Section 1.3.1 implies that "SysRS Section ###" has requirements.

sections. A date for completing the next revision of the System Requirements Specification See also SDS4.4.2.1-1 on page 4-32). TVA to provide date will be provided no later than August 31, 2010. when information will Is there a requirement on the shall referenced above?? be docketed.

The System Requirements Specficiation will be revised by September 30, 2010 and submitted within two of receipt from Westinghouse.

54 April 19, 2010 NRC POC: EICB (Singh) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC NRC Review FSAR Section 7.5.1 Post Accident Please describe all the different environments in which the RM-1000 will be required to operate. The only safety-related application for the RM-1000 is the Containment High Range radiation Monitoring Instrumentation - SE Section Please group these environments into two categories (a) Harsh environment, per 10 CFR 50.49, monitors. The Containment High Range radiation monitors will be installed in the Main 7.5.2 and (b) Mild Environment. Control Room, a mild environment. The detectors will be installed remotely in the containment.

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

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

55 April 19, 2010 NRC POC: EICB (Singh) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC NRC Review FSAR Section 7.5.1 Post Accident The "Qualification Test Report Supplement, RM-1000 Upgrades," Document No. 04508905-1SP The detectors for these loops will be located in a harsh environment (inside containment). The Monitoring Instrumentation - SE Section Rev. A states that the qualification was done in accordance with IEEE 323-1974 and -1983. RM-1000 will be located in the main control room, which is a mild environment. The RM-1000 7.5.2 Please describe and justify all differences in this qualification methodology and that endorsed by and associated I/F converters have been tested to the requirements present in IEEE Std. 323-Regulatory Guide 1.209. Specifically address EMI and RFI 1983 and -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) 57 April 19, 2010 NRC POC: EICB (Singh) Date: 5/25/10 Responder: TVA I&C Staff Date: 4/19/10 Responsibility: NRC Response path FSAR Section 7.5.1 Post Accident Please describe the ability to change the software of the RM-1000 at site, including all required Firmware/software changes are done by connecting a laptop to a port on the front of the RM- Requested information provided. NRC to review. acceptable. TVA to Monitoring Instrumentation - SE Section equipment and administrative controls (e.g., temporary digital connections). 1000 and placing the Operate/Calibrate switch in the Calibrate position. The first physical Further Information Requested: Please confirm that the laptop is submit the 7.5.2 barrier to access is the location of the RM-1000 in the main control room which has limited secure and access to this laptop is commensurate with the access to information for access. The RM-1000 Operate/Calibrate switch is located behind the hinged front panel. The the equipment for which it will be used. Is the laptop dedicated for docketing.

front panel must be opened (held closed by two thumbscrews) to access the switch. This calibration of radiation monitors? If the laptop is used for more than provides a physical barrier to inadvertent switch operation. The system malfunction alarm is one application then please describe the equipment for which the visible locally and will annunciate on the control board when the switch is in the Calibrate laptop may be used. In addition please explain how software security position. is assured and that only the software intended for the specific application is used. Is the connection to the radiation monitors made Administrative control of software/firmware updates is in accordance with TVA Standard via a special cable/connectors? Please confirm that the RS-232 Specification SS-E18.15.01, Software Requirements for Real-Time Data Acquisition and communication port of the radiation monitors will only be used for Control Computer Systems, and TVA procedures SPP-9.3, Plant Modifications and calibration purposes. Also please confirm that the radiation monitor Engineering Change Control, and SPP-2.6, Computer Software Control. Approved changes will not be in operation during the calibration mode. In addition please to software/firmware are implemented utilizing the TVA work order process. confirm that password protection is provided for logging on to the laptop prior to start of calibration.

(1) A laptop is not used to calibrate the monitor. All TVA in-house activities (calibration, alarm setpoint adjustment, etc.) are performed using the touchpad on the monitor. An external computer (laptop etc.) is only used to perform software or firmware updates. TVA does not perform software or firmware updates using in-house resources therefore no TVA computer is ever connected to the monitor. If software or firmware updates are required, they are approved via the TVA design change process previously described and implemented by a vendor representative under the TVA work order and Quality Assurance processes.

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

(3) See the response to Item 1.

File: rad4AB2F.xlsx Page 6 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments (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.

64 March 12, 2010 NRC POC: EICB (Carte) Date: 4/8/2010 Responder: Webb Date: 4/8/10 Responsibility: NRC TVA to provide FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the D3 Analysis By letter dated April 8, 2010 TVA docketed WNA-LI-00058-WBT Rev. 0, April 2010. Section TVA provided roughly a page of description as to why a D3 analysis is requested information. Monitoring Instrumentation - SE Section was April 2, 2010. 4.11, "Plant Specific Action Item 6.11." addresses the D3 Analysis. not required. The NRC requires additional information to determine 7.5.2 the acceptability of this response. TVA to provide date when information will be docketed.

65 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the FMEA was WEC to provide the P version ASAP. Awaiting for document to be docketed by TVA. Due 9/15/10 Monitoring Instrumentation - SE Section August 31, 2010. 7.5.2 66 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 Per Westinghouse letter WBT-D-1961 (Reference 8), these items are available for audit at the Regulations require that the NRC review be based on docketed remaining information. Monitoring Instrumentation - SE Section PAMS Software Design Description (two documents, one for flat panel display and one for Westinghouse Rockville office. material. The SRP directs that reviewer to review the Software 7.5.2 AC160)" was March 31, 2010. Design Specification (softimes called an SDD). NRC to review

• WNA-SD-00250-WBT Rev. 0 (AC160) was submitted on TVA letter to the NRC dated information provided.

August __, 2010 (Reference 7). NNC 8/25/10: By letter dated august 20, 2010, one (Reference 7)

• WNA-SD-00248-WBT, Rev. 0 (FPDS) was submitted on TVA letter to the NRC dated SEPT SDD has been provided.

2, 2010 ( Reference 8 ).

67 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Commercial The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix Regulations require that the NRC review be based on docketed requested information. Monitoring Instrumentation - SE Section Grade Dedication Instructions for AI687, AI688, Upgraded PC node box and flat panels." was submitted in response to Item 43: material. 7.5.0 & 7.5.2 September 28, 2010. TVA to provide date

a. AI687, AI688 - Scheduled for September 28, 2010 when information will be docketed.

b. Upgraded PC node box and flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), these items are available for audit at the Westinghouse Rockville office.

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

To be addressed during 9/20-9/21 audit 68 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Summary The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix Awaiting for document to be docketed by TVA. requested information. Monitoring Instrumentation - SE Section Report on acceptance of AI687, AI688, Upgraded PC node box, flat panels, and power submitted in response to Item 43: 7.5.2 supplies." was September 28, 2010. TVA to provide date

a. AI687, AI688 - Scheduled for September 28, 2010 when information will be docketed.

b. Upgraded PC node box - Per Westinghouse 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 69 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 Awaiting for document to be docketed by TVA. Due 11/30/10 Monitoring Instrumentation - SE Section PAMS Specific FAT Report" was October 2010. 7.5.2 70 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 5/6/10 Responsibility: TVA NRC to review FSAR Section 7.5.1 Post Accident information provided Monitoring Instrumentation - SE Section File: rad4AB2F.xlsx Page 7 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments By letter dated March 12, 2010 TVA stated that the target submittal date for the "Concept and Per Westinghouse letter WBT-D-1961, (Reference 8) this document is available for audit at the Regulations require that the NRC review be based on docketed information provided Monitoring Instrumentation - SE Section Definition Phase V&V Report" was March 31, 2010. Westinghouse Rockville office. material. Awaiting for document to be docketed by TVA. 7.5.2 WNA-VR- 00283-WBT, Rev 0 was submitted on TVA letter to the NRC dated August __, NNC 8/25/10: Requirements Phase SVVR provided by TVA letter 2010 (Reference 7). dated 8/20/10.

V&V did not address the RTM and did not summarize anomilies. To be addressed at the 9/15 public meeting at NRC.

71 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Design Phase Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 9/23/10 Monitoring Instrumentation - SE Section V&V Report" was July 30, 2010. 7.5.2 72 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 10/15/10 Monitoring Instrumentation - SE Section "Implementation Phase V&V Report" was September 30, 2010. 7.5.2 73 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Integration Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 11/15/10 Monitoring Instrumentation - SE Section Phase V&V Report" was October 29, 2010. 7.5.2 74 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Final V&V Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 12/15/10 Monitoring Instrumentation - SE Section Report" was November 30, 2010. 7.5.2 75 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 10/15/10 Monitoring Instrumentation - SE Section PAMS Specific FAT Procedure" was September 30, 2010. 7.5.2 76 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 3/12/10 Responsibility: TVA Open FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 Verify schedule dates for the next submittal of this matrix against update WEC schedule. Awaiting for document to be docketed by TVA. Due 9/15/10 Monitoring Instrumentation - SE Section PAMS Specific Processor Module Software Test" was August 31, 2010. 7.5.2 77 March 12, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 3/12/10 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident By letter dated March 12, 2010 TVA stated that the target submittal date for seven other The availability dates for these documents are included in the revised WBN2 Common Q ISG- Regulations require that the NRC review be based on docketed requested information. Monitoring Instrumentation - SE Section documents was "TDB". Please provide a schedule for the docketing of the remaining 6 Compliance Matrix submitted in response to item 43. As stated in the March 12, 2010 letter material. Awaiting for document to be docketed by TVA. 7.5.2 documents. (Reference 4), the dates in the matrix are the dates the documents will be available to TVA to TVA to provide date prepare for submittal or being Available for Audit. They do not reflect the dates the when information will documents will be submitted to the NRC. Expected submittal date is two weeks after TVA be docketed.

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.

78 April 26, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Clark Date: 4/26/2010 Responsibility: TVA FSAR Amd 100 FSAR Section 7.1.2.1.8 adds a reference 6 to the FSAR. However, Reference 6 is for (Q1) The cross reference information is corrected in FSAR Amendment 100 submitted to the Awaiting TVA response. SSER 13 for unit 1 instrument setpoint and has nothing to do with the diversity discussion on the FSAR Section. NRC on TVA letter to the NRC dated August __, 2010 (Reference 2). references rev. 1 of We believe the TVA wants to add reference 7 which is the diversity document, WCAP 13869, WCAP 13869. Rev. 2 "Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors." Please (Q2) WCAP-13869 Rev. 1 was previously reviewed under WBN Unit 1 SER SSER 13 is used for Unit 2.

confirm this and add commitment to revise FSAR to correct the reference. (Q1) Also, confirm (Reference 9). Need to identify differences to Revision 2. Identify all the whether this WCAP has been reviewed by NRC, if yes, provide reference and if not, then differences between submit the WCAP to NRC. (Q2) Also provide the justification for this reference to WBN2. (Q3) (Q3) Westinghouse confirmed the applicability of this WCAP to Watts Bar Unit 2 in letter WBT- Rev.1 and Rev.2 and D-1321, Final Response to WBT-TVA-0713 Unit 2 WCAP Reviews, dated December 2, 2009 justify their (Reference 10). acceptability.

79 April 26, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Clark Date: 4/26/2010 Responsibility: TVA This item is closed File: rad4AB2F.xlsx Page 8 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments FSAR Section 7.1.2.1.9, Trip Setpoints, adds reference to 3, 4, and 5. However, reference 3 (Q1) WBN Unit 2 is licensed based on WBN Unit 1. The WBN Unit 1 licensing basis is ISA-DS- Awaiting TVA response. as it will be reviewed was deleted by FSAR amendment 81. Reference 4 has been changed to ISA-DS-67.04-1982. 67.04-1982. Therefore this methodology is used for the same SSDs for WBN Unit 2. This under item 154.

Justify applicability of this standard for WBN 2.(Q1) Why the latest ISA standard endorsed by maintains consistency in the licensing bases for both units. FSAR Amd 100 NRC has not been used? (Q2) Also reference 5 is a topical report for Eagle 21, system. Please confirm that this topical report also discusses the setpoint for Eagle 21 system and whether it (Q2) Please refer to the response to Q1.

meets the recent guidance for the setpoint issued by the staff. (Q3) Also, W setpoint methodology do not provide discussion on the AS Found Tolerance and As left value (Q3) FSAR Reference 4 is the Eagle 21 Topical Report. FSAR Reference 5, WCAP-17044, determination and how these values are used for the instrument operability, therefore, add the Westinghouse Setpoint Methodology for Protection Systems Watts Bar Unit 2 submitted discussion of these topics in the FSAR. (Q4) and add reference to other documents if it is under TVA letter to the NRC dated February 12, 2010 (Reference 11) discusses the setpoint discussed in some other document. (Q5) Provide this document to the staff for review and methodology used for Eagle 21 loops.

approval. (Q6)

(Q4) (Q4) FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August __, 2010 (Reference 2) incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to 7.1.2.1.9 to section 7.2.1.1.10.

(Q5) Please refer to the response to Q4.

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

80 April 26, 2010 NRC POC: EICB (Singh) Date: Responder: WEC Date: 4/26/2010 Responsibility: TVA NRC Review FSAR Table 7.1-1, Note 12 has been added to the table but it's justification has not been A revised note was included in the 7/30 letter along with justification for the note.

provided to the staff for review and approval.

81 May 6, 2010 NRC POC: EICB (Carte) Date: 6/18/10 Responder: Merten/WEC Date: 5/6/2010 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in The codes and standards documents listed in Section 7 of the Common Q PAMS Licensing ML101600092 Item No.1: There are three sets of regulatory criteria requested information. Monitoring Instrumentation - SE Section Section 7, lists codes and standards applicable to the Common Q PAMS. This list contains Technical Report are the documents that the Common Q platform was licensed to when the that relate to a Common Q application (e.g. WBN2 PAMS): 7.5.2 references to old revisions of several regulatory documents, for example: NRC approved the original topical report and issued the approved SER. The WBN Unit 2 (a) Common Q platform components - Common Q TR TVA to provide date (1) RG 1.29 - September 1978 vs. March 2007 Common Q PAMS is designed in accordance with the approved Common Q topical report (b) Application Development Processes - Common Q SPM when information will (2) RG 1.53 - June 1973 vs. November 2003 and approved SER and the codes and standards on which the SER was based. Since the (c) Application Specific - current regulatory criteria be docketed.

(a) IEEE 379-1994 vs. -2000 current versions referenced are not applicable to WBN Unit 2, there is no basis for a The Common Q Topical Report and associated appendices primarily (3) RG 1.75 - September 1975 vs. February 2005 comparison review. addressed (a) and (b). The Common Q SER states:

(a) IEEE 384-1992 vs. -1992 (4) RG 1.100 - June 1988 vs. September 2009 Bechtel to develop a matrix and work with Westinghouse to provide justification. Appendix 1, Post Accident Monitoring Systems, provides the (a) IEEE 344-1987 vs. -2004 functional requirements and conceptual design approach for upgrading (5) RG 1.152 - January 1996 vs. January 2006 an existing PAMS based on Common Q components (page 58, (a) IEEE 7-4.33.2-1993 vs. -2003 Section 4.4.1.1, Description)On the basis of the above review, the (6) RG 1.168 - September 1997 vs. February 2004 staff concludes that Appendix 1 does not contain sufficient information (a) IEEE 1012-1986 vs. -1998 to establish the generic acceptability of the proposed PAMS design (b) IEEE 1028-1988 vs. -1997 (page 56, Section 4.4.1.3, PAMS Evaluation)

(7) IEEE 279-1991 vs. 603-1991 (8) IEEE 323-1983 vs. -1974 (RG 1.89 Rev. 1 June 1984 endorses 323-1974) The NRC did not approve the proposed PAMS design. Section 6, However, LIC-110, "Watts Bar Unit 2 License Application Review," states: "Design features and References, and Section 7, Codes and Standards Applicable to the administrative programs that are unique to Unit 2 should then be reviewed in accordance with Common Q PAMS, of the PAMS Licensing Technical Report contain the current staff positions." Please identify all differences between the versions referenced and items that are not the current regulatory criteria.

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

82 May 6, 2010 NRC POC: EICB (Carte) Date: 6/18/10 Responder: WEC Date: 5/6/2010 Responsibility: TVA Updated compliance FSAR Section 7.5.1 Post Accident matrix provided. Monitoring Instrumentation - SE Section The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in These components can be found in the Summary Qualification Report Of Hardware Testing Regulations require that the NRC review be based on docketed Awaiting WEC submittal 7.5.2 Section 2.3, lists hardware/software changes to the Common Q PAMS previously reviewed by For Common Q Applications, 00000-ICE-37764, Rev 3 and material. Awaiting for document to be docketed by TVA. of documents to TVA.

the NRC. However the Common Q ISG-6 Compliance Matrix does not contain activities that TWICE Qualification Status Report, WNAQR-00011-SSP Per Westinghouse letter WBT-D-address qualification of all changes specifically: 2024, (Reference __) dated June 9, 2010, these documents are available for audit at the NNC 8/9/10: per telephone conversation on 8/5/10, it is not clear how Westinghouse Rockville Office. Westinghouse Commercial Grade Dedication Plans and Reports for 2.c - CI527 AF100 Peripheral Component Interconnect (PCI) interface card Digital I&C. Westinhouse agree to present to the NRC in a public

3. - Common Q TC514 AF100 Fiber Optic Modems (Evolutionary Product TVA provided information by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 meeting on August 17, 2010, and explanation of how their system Maintenance/Improvements) Item No. 7. addreses regulatory criteria for both commercial grade dedication and 4.a - PM646A Processor Module equipment qualification.

4.b - CI631 AF100 Communication Interface Module Revision 1 of the Licensing Technical Report provides additional detail on the platform specific 4.e - DO620 Digital Output Card to WBN2 and references to the evaluation documentation. NNC 8/25/10: In the August 17, 2010 public meeting Westinghouse stated that the CDi were the plans. The NRC requested that the Please provide sufficient detail regarding the changes for the NRC to independently evaluate the plans and associated reports be docketed.

acceptability of the changes.

85 May 6, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: 5/6/2010 Responsibility: TVA Need WEC to provide FSAR Section 7.5.1 Post Accident make and model Monitoring Instrumentation - SE Section File: rad4AB2F.xlsx Page 9 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Please provide a detailed description of the PAMS MTP data link to the plant computer. This Is the WEC ISG4 evaluation inadequate? A response will be provided by 10/31/10 make and model Monitoring Instrumentation - SE Section description should identify all equipment (model & version) and describe the functions that each information after FAT. 7.5.2 piece of equipment performs. This description should be of sufficient detail for the NRC to Operation of the MTP as a barrier device. MTP Fails as a barrier NNC 8/11/10: Design information should be avaialble now. By letter independently evaluate the statements made in WNA-LI-00058-WBT Rev. 0, Section 5.3. dated July 30, 2010 (ML102160349) TVA stated that the MTP was NNC 8/25/10: Disagree device. Describe what prevents a MTP failure from propagating to connected to a Red Hat Linux Server (see Enclosure 1, Item No. 14 with path forward input by the AC160? part b.). It is presumed that this server is not safety-related. IEEE TVA above. An 603-1991 Clause 5.6.3(1) states, "Isolation devices used to affect a explanation is about the Node loss on the bus? Bus loss? safety system boundry shall be classified as part of the safety design is needed.

system."

Revise the ISG4 section of the Licensing Technical Report (Rev. 2) to provide a more detailed description of the MTP as a barrier Please describe how the MTP serves as the isolation device.

device.

86 May 6, 2010 NRC POC: EICB (Carte) Date: 5/24/10 Responder: WEC Date: 5/6/2010 Responsibility: TVA TVA to provide FSAR Section 7.5.1 Post Accident The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in The regulatory documents listed in the Common Q PAMS Licensing Technical Report are the The response does not address the request. This request was requested information. Monitoring Instrumentation - SE Section Section 6, lists references applicable to the Common Q PAMS. This list contains references to documents that the Common Q platform was licensed to when the NRC approved the regarding guidance that did not exist at the time that the CQ topical 7.5.2 old revisions of several regulatory documents, for example: original topical report and issued the approved SER. The WBN Unit 2 Common Q PAMS is report was reviewed. The WBN2 PAMS applicaton must address TVA to provide date (1) DI&C-ISG04 - Rev. 0 (ML072540138) vs. Rev. 1 (ML083310185) designed in accordance with the approved Common Q topical report and approved SER and current regulatory criteria. when information will However, LIC-110, "Watts Bar Unit 2 License Application Review," states: "Design features and the regulatory documents on which the SER was based. Since the current versions be docketed.

administrative programs that are unique to Unit 2 should then be reviewed in accordance with referenced are not applicable to WBN Unit 2, there is no basis for a comparison review.

the current staff positions." Please identify all differences between the versions referenced and the current staff positions. Please provide a justification for the acceptability PAMS with respect Rev 0 of the Licensing Technical Report references Rev. 1 of ISG4 to these differences.

89 May 6, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: 5/24/2010 Responsibility: NRC NRC Review NNC: Docketed response states that What FSAR functions are implemented using Foxboro Intelligent Automation (IA)? The list of FSAR functions is listed in TVA letter dated March 12, 2010, Enclosure 1, item 12 the applicable FSAR Sections are:

5.6 -

FSAR Section 7.7.11 will add a discussion of the DCS. 7.2.2.3.2 - Garg 7.2.2.3.3 - Garg See item 4 for questions on failure modes and mesh network. 7.2.2.3.4 - Garg 7.2.2.3.5 - Garg 7.2.3 - Garg 7.6.8 -

7.7.1.6 -

90 May 6, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 5/24/2010 Responsibility: NRC NRC Review What FSAR Systems are implemented using Foxboro Intelligent Automation (IA)? The list of FSAR functions is listed in TVA letter dated March 12, 2010, Enclosure 1, item 12 FSAR Section 7.7.11 will add a discussion of the DCS.

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

92 May 20, 2010 NRC POC: DORL (Bailey) Date: Responder: Hilmes Date: Responsibility: Continuous review TVA to review Licensee Open Item list and determine which items are proprietary. Next review due 6/18/10 as items are added 94 May 20, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Clark Date: Responsibility: Closed TVA to locate and provide information on the TMI action item to add an anticipated reactor trip This item is described in FSAR amendment 98, Section 7.2.1.1.2 item 6 page 7.2.9, and NRC staff will review.

on turbine trip to the design bases in the FSAR Table 7.2-1 item 14, page 7.2-39.

96 May 20, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: This items will be closed TVA to provide information on implementation of IEN 79-22 and how it is addressed in the IEN 79-22 is not specifically listed or discussed in the WBN Unit 1 Response provided. NRC staff to review response. upon the resolution of item FSAR UFSAR or Unit 2 FSAR. IEN 79-22 is one of the precursors to 283.

10CFR50.49 environmental qualification. The initial SQN and WBN See Follow up question 283.

Unit 1 response was developed prior to TVA implementing 10CFR50.49. As such, the discussion of safety-related actuations is no longer valid. In implementing 10CFR50.49, TVA upgraded susceptible safety-related devices located in harsh environments to fully qualified devices. For WBN Unit 2, only fully qualified safey-related devices are installed in areas susceptible to a high energy line break. The non-safety-related device/systems within the scope of IEN 79-22 are:

1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

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

File: rad4AB2F.xlsx Page 10 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 100 April 12, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Closed The following Common Q proprietary documents listed in the response and the affidavits for the The documents, and affidavits for withholding for the listed documents were submitted to the TVA has not yet docketed all items requested.

proprietary documents will be provided by April 9, 2010. NRC 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 April 12, 2010 NRC POC: DORL (Bailey) Date: Responder: Slifer Date: Responsibility: NRC Review TVA is working with the vendor to meet The non-proprietary versions of the following RM-1000, Containment High Range Post Accident The documents, and affidavits for withholding for the listed documents were submitted to the the 6/30 date, however there is the Radiation Monitor documents will be provided by June 30, 2010. NRC on TVA letter to the NRC dated July 15, 2010. potential this will slip to 7/14.

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 103 May 27, 2010 NRC POC: EICB (Darbali) Date: 5/27/10 Responder: Clark Date: 5/27/10 Responsibility: TVA Open Submittal date is based on current TVA to submit excerpts of EDCR 52321 EDCR is scheduled for issue 10/13/10 Due 10/31/10 EDCR scheduled issue date.

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

109 a May 6, 2010 NRC POC: EICB (Darbali) Date: NA Responder: NA Date: NRC Responsibility: NRC Action The reviewer was unable to identify the sections of the FSAR that correspond to the standard TVA Provided response J. Wiebe accepted this action.

review plan sections 7.8.

109 b May 6, 2010 NRC POC: EICB (Carte) Date: NA Responder: NA Date: NRC Responsibility: NRC Action The reviewer was unable to identify the sections of the FSAR that correspond to the standard TVA Provided response J. Wiebe accepted this action.

review plan sections7.9.

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

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

2010.

As documented in WBT-D-1917, Eagle-21 Rack 5 LCP Diagnostic Failures, (Reference 14),

during the factory acceptance testing for the Unit 2 Eagle-21 System, Westinghouse noted an occasional diagnostic failure while performing the parameter update function on Rack 5.

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

Based on Westinghouse examination and testing, a difference in hardware was identified between the Unit 1 LCP shipped to Westinghouse, the new Unit 2 Rack 5 LCP, and an older LCP (older than the Unit 1 LCP) from the Westinghouse Eagle 21 test bed. Installed on the Unit 1 LCP was a different version of an 80287 math coprocessor chip (80287 XL).

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

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

File: rad4AB2F.xlsx Page 11 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 115 February 25, 2010 NRC POC: EICB (Carte) Date: 6/2/10 Responder: Clark Date: Responsibility: TVA to Update Provide a list of digital 1E systems that have a digital communications path to non safety related Response states that Eagle21 and the CQ PMAS MTP have The CQ PAMS SysRS (WNA-DS-01617-WBT Rev. 1 Figure 2..1-1) response systems and if it has: communications links to non-safety-related systems.. shows that the OM has a TCP interface to non-safety. Please

a. Been reviewed before for unit 1 provide a list of ALL digital communications paths to non-safety-

b. Or installed in unit 1 under 50.59, or This item was identified during TVA review of Figure 2.2-1 of the PAMS related systems.

c. Is unique to unit 2 Licensing Technical Report WNA-LI-00058-WBT, Rev.0 and the figure NNC 8/12/10: The staff pinted out this inconsistency to TVA. The was revised to remove the connection. It was addressed with staff could consider PAMS Licensing Technical Report to be a Westinghouse at that time. However other Common Q PAMS correction if TVA specifically identified the inconsistency to the staff, or documents had been issued before the issue was identified to identified where the error in the SysRSs, SRS, & SDS had already Westinghouse. The Licensing Technical has been corrected and the been identified. This apppreas to be a feature in the CQ TR appendix other documents will be corrected at the next revision that was carried forward to WBN2 PAMS inappropriately Design change after documents were produced that deleted the connection from the OM to plant computer.

There are no communications from the Operators Module to the plant computer or any other system. The Common Q PAMS SysRS WNA-DS-01617-WBT Rev. 1, Figure 2.1-1 will be revised to remove this connection by April 1, 2011 and submitted to the NRC by April 15, 2011.

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

conformal coating was credited to protect against tin whisker issue.

117 NRC POC: EICB (Garg) Date: Responder: Webb/Powers Date: Responsibility: OPEN TVA need to Does TVA use a single sided or double sided methodology for as-found and as-left instrument TVA uses double-sided as-found and as-left tolerances for trip setpoints as described in FSAR address that trip setpoint values. (RIS2006-7) amendment 100. setpoint and allowable value uncertainties are not reduced by the reduction factor for the single sided reduction factor.

118 June 8, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: Open Submittal date is based on current TVA to submit excerpts from EDCR 55385 TVA has agreed to submit the EDCR by 11/15/10. Due 11/15/10 EDCR scheduled issue date. Note: The RVLIS EDCR has been split into two 120 May 6, 2010 NRC POC: EICB (Carte) Date: Responder: Hilmes/Merten/Costley Date: Responsibility: Closed In reviewing the Maintenance Test Panel (MTP) link to the plant computer, the reviewer noted TVA respinded by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item No. 14: NNC 8/9/10: By letter dated July 30, 2010 (ML102160349) - See that the MTP software is not purely one directional in that it does allow low level handshaking to Detailed discussion is provided including technical information on the data diode. Enclosure 1 Item No. 14 -

support the communications protocol. M. Merten/S. Hilmes a. TVA stated no new information was found in Westinghouse See Item 85. TVA not crediting the data diode. documentation and that this information would be addressed in the

a. The reviewer stated that this was a potential concern and requested additional information on V&V reports, and that the final hardware drawing will be provided.

how the MTP ws protected from feedback from the plant computer. Neither of these two documents will contain the information requested. Please provide a detailed description of the MTP hardware

b. The reviewer stated that in the Oconee review, it was found that the non-safety related data connections and the software that perform the communications.

diode was easier to credit than a software barrier. It was suggested we look at changing our b. The information provided indicates that the MTP is connected position to credit the data diode provided it provided a physical barrier to feedback. Need OWL directly to a non-safety-related Red Hat Linux Server which is then Information SAH connected to the data diode divices. Please describe the secure development and operational environment of these Red Hat Linux

c. During this discussion, the reviewer asked if we had information from Westinghouse that Servers.

demonstrated the ability of Common Q PAMs to withstand a data storm. A verbal response c. The answer is not complete. A chattering node is one of the failure was that this was required by contract as part of the Factory Acceptance Test and would not be modes of an ethernet link. The MTP is connected to a linux server available until the FAT was completed. Need to docket the verbal response and provide a date over an ethernet link. What prevents this link from locking up the MTP the information will be available. Believe we stated this in the Tech Report. SAH by a data storm?

121 May 6, 2010 NRC POC: EICB (Garg) Date: Responder: Webb/Webber Date: Responsibility: NRC Review If not previously provided, provide the requested information in items a, b and c for changes to The information in the letter provides references to previous submittals and a cross reference all platforms between Unit 1 and 2. (Specific request for information on Foxboro IA). D. for the Foxboro I/A system.

Webb/H. Webber

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

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

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

123 June 14, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: Closed File: rad4AB2F.xlsx Page 12 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Safety Evaluation(SE) Section 7.7.3 Volume Control Tank Level Control System 1. The devices in the Volume Control Tank Level Control System have been replaced. The Staff is reviewing response.

Volume Control Tank Level Indication and Control functions have been relocated to the

1. Confirm whether or not any Instrumentation & Control (I&C) systems or equipment have Foxboro IA system. The transmitters and indicators have been replaced with 4-20mA Follow up question is to request a logic diagram 283.

been changed in the Volume Control Tank Level Control System. technology and the transmitters have been changed to Rosemount.

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

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

124 June 14, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: Closed SE Section 7.7.5 IE Information Notice 79-22 Duplicate of item 96 Staff is reviewing response.

1. In the original SE, Section 7.7.5, the staff determined that Information Notice 79-22 was resolved based on your statement that the control and logic functions of the Watts Bar plant were identical to the Sequoyah plant, thus making the Sequoyah evaluation applicable to Watts Bar. Confirm that your statements regarding the control and logic functions are applicable to Unit 2s control and logic functions or describe any changes and why they are acceptable.

125 June 14, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: NRC Review SE Section 7.7.8 AMSAC 1. The AMSAC system was not previously installed in Unit 2. EDCR 52408 installs the Staff is reviewing response.

system. Attachment 3 contains excerpts from the EDCR that describe the Unit 2 system and

1. Confirm whether or not any I&C systems or equipment have been changed in the AMSAC? how it differs from the Unit 1 system.

Describe the changes, if any.

2. EDCR 52408 incorporates the AMSAC system into the Unit 2 drawings.

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

127 June 16, 2010 NRC POC: EICB (Garg) Date: 6/16/10 Responder: WEC/Clark Date: Responsibility: NRC Review Provide the status of the Eagle 21 Rack 2 RTD accuracy issue. The following non-proprietary response was developed from proprietary Westinghouse letter WBT-D-2034 (Reference 15), which provided the details of this issue. Westinghouse approved this non-proprietary response via e-mail from A. Drake to M. Clark on June 16, 2010.

During the Watts Bar Unit 2 Eagle 21 Factory Acceptance Test (FAT) of Rack 2 it was discovered that the narrow range Resistance Temperature Detector (RTD) temperature inputs were consistently reading about 0.2 °F higher than expected. Investigation revealed that these inputs are configured in the Loop Calculation Processor software as a shared RTD. This is incorrect. Rack 2 RTD's are not shared. Racks 6, 10 and 13 RTD's are. Configuration as a shared RTD input alters the equation used for the temperature calculation. Watts Bar Unit 1 uses identical software to Unit 2.

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

auctioneered high), would cause the controlling temperature to result in an actual temperature 0.2°F low; which is in the conservative direction for consideration of DNB. The Tavg - Low-Low function (P-12) would be non-conservative by 0.2 °F, which would cause the permissive/interlock for block of steam dump post reactor trip to be delayed slightly via that channel. This delay would not be considered significant. Westinghouse will discuss this issue with Watts Bar Unit 1 personnel in accordance with their Part 21/Potential Issue process.

Westinghouse initiated a corrective action item (CAPS # 10-140-M021) and performed an Evaluation of Potential Nuclear Safety Issue. Based upon the above investigations, Westinghouse determined that this issue does not represent a substantial safety hazard at Watts Bar Unit 1 even it left uncorrected.

128 June 18, 2010 NRC POC: EICB (Garg) Date: Responder: WEC Date: Responsibility: Open. Staff will TVA Unit 1 has to address first and Unit Submit the report on the final resolution of the Eagle 21 Rack 2 RTD input issue issue SE with this as 2 will follow Unit 1.

an open item.

Due 12/3/10 129 April 12, 2010 NRC POC: DORL (Bailey) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 13 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments TVA will provide non-proprietary versions of the following Common Q attached proprietary The documents, and affidavits for withholding for the listed documents were submitted to the Due 7/16/10 documents and the affidavits for the proprietary documents by June 30, 2010. NRC on TVA letter to the NRC dated July 14, 2010.

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

2. System Requirements Specification WNA-DS-01617-WBT, Rev. 1 Andy to Verify the documents have been submitted and then close this item.

3. Software Requirements Specification WNA-SD-00239-WBT, Rev. 1 130 June 28, 2010 NRC POC: DORL(Bailey) Date: Responder: Clark Date: Responsibility: FSAR Amd 100 TVA committed to revise in Amendment 100: table 4.3-1 to add ID and OD nomenclature to FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __,

thimble guide tube dimensions . 2010 added the ID and OD nomenclature.

131 June 28, 2010 NRC POC: DORL(Bailey) Date: Responder: Clark Date: Responsibility: FSAR Amd 100 TVA committed to revise in Amendment 100: FSAR 3.10 references to eliminate (LATER) for FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __,

document numbers. 2010 updated the reference document number information.

132 June 28, 2010 NRC POC: DORL(Bailey) Date: Responder: Clark Date: Responsibility: FSAR Amd 100 TVA committed to revise in Amendment 100: FSAR 3.10 to correct differences between the list FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __,

on page 3.10-4 and the numbering refrenced by the text below the list. 2010 corrected the numbering in the text.

133 June 28, 2010 NRC POC: DORL(Bailey) Date: Responder: Clark Date: Responsibility: FSAR Amd 100 TVA committed to revise in Amendment 100: FSAR 3.10 to remove references to IEEE 344- FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __,

1987. 2010 removed the reference to IEEE 344-1987.

134 June 28, 2010 NRC POC: DORL(Bailey) Date: Responder: Clark Date: Responsibility: FSAR Amd 100 TVA committed to revise in Amendment 100: FSAR Table 1.3-3 to reflect modifications to FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __,

WBN2 . 2010 updated the table to reflect the WBN2 modifications.

135 June 30, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: NRC Review TVA committed to add in Amendment 100 a reference to 7.3.1.1.1 in 6.2.5.2.b. FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated Sept 1, 2010 added the reference.

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

137 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open Several WBN2 PAMS documents contain a table titled, Document Traceability & Compliance. (a) The table is to show the document hierarchy (i.e., what documents are predecessors to Carte accepted this response 9/1 the document in relationship to the design life cycle). TVA to provide date (a) Please explain the purpose of this table. when information (b) This table is showing a hierarchical relationship between documents. These documents will be docketed.

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

(c) What does it mean for a document to be listed in this table?

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

138 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By letter dated February 3, 2010, Westinghouse informed TVA that certain PAMS To be addressed during 9/20-9/21 audit.

documentation has been completed. TVA to provide date when information (a) The draft ISG6 states that a commercial grade dedication plan should be provided with an will be docketed.

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.

File: rad4AB2F.xlsx Page 14 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments (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 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS System Requirements The WBN2 PAMS System Requirements Specification (WBN2 PAMS SysRS) contains a table (a) The table is to show the document hierarchy (i.e., what documents are predecessors to Specification (see page iii) titled, Document Traceability & Compliance, which states that the WBN2 PAMS the document in relationship to the design life cycle). TVA to provide date SysRS was created to support no documents. Please explain. when information TVA docketed WNA-DS-01617-WBT (b) This table is showing a hierarchical relationship between documents. These documents will be docketed. Rev. 1, RRAS Watts Bar 2 NSSS are also in the reference list along with other documents that have no hierarchical relationship Completion Program I&C Projects Post with the document. Accident Monitoring System- System Requirements Specification, dated (c) This question is similar to (a). It is to identify the documents that are predecessors to this December 2009.

document in relationship to the design life cycle.

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

140 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS System Requirements The first requirement in the WBN2 PAMS SysRS (i.e., R2.2-1) states: The PAMS shall be Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be Specification capable of operation during normal and abnormal environments and plant operating modes. provided. TVA to provide date The rational for this requirement is that it is necessary to meet Regulatory Guide (RG) 1.97. when information TVA docketed WNA-DS-01617-WBT will be docketed. Rev. 1, RRAS Watts Bar 2 NSSS What document specifies which RG 1.97 variables are implemented in the Common Q based Completion Program I&C Projects Post WBN2 PAMS? Accident Monitoring System- System Requirements Specification, dated December 2009.

142 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS System Requirements The applicable regulatory guidance for reviewing the WBN2 PAMS SysRS would be IEEE 830 Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be Specification as endorsed by Regulatory Guide 1.172 and BTP 7-14 Section B.3.3.1, Requirements Activities provided. TVA to provide date

- Software Requirements Specifications. IEEE 830-1994 Section 4.3.8, Traceable, states: A when information TVA docketed WNA-DS-01617-WBT

[requirements specification] is traceable of the origin of each of its requirements is clear will be docketed. Rev. 1, RRAS Watts Bar 2 NSSS How did TVA ensure the traceability of each requirement in the WBN2 PAMS SysRS. Completion Program I&C Projects Post Accident Monitoring System- System Requirements Specification, dated 143 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS System Requirements The WBN2 PAMS Software Requirements Specification (WBN2 PAMS SRS - ML101050202) Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be Specification contains a table (see page iii) titled, Document Traceability & Compliance, which states that the provided. TVA to provide date WBN2 PAMS SRS was created to support the three documents identified (one of which is the when information TVA docketed WNA-DS-01617-WBT WBN2 PAMS SysRS). Section 1.1, Overview, of the WBN2 PAMS SRS states: This will be docketed. Rev. 1, RRAS Watts Bar 2 NSSS document describes requirements for the major software components Completion Program I&C Projects Post Accident Monitoring System- System (a) Please list and describe each of the major software components. Please include a Requirements Specification, dated description of any NRC review for each of these components. December 2009.

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

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

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

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

144 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS Software Requirements Specification File: rad4AB2F.xlsx Page 15 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments The WBN2 PAMS Software Requirements Specification (WBN2 PAMS SRS) contains a table (a) The purpose of NABU-DP-00014-GEN document is to define the process for system level NRC Review and WEC to complete response. Specification (see page iii) titled, Document Traceability & Compliance, which states that the WBN2 PAMS design, software design and implementation, and hardware design and implementation for Responses to items SRS was created to support the three documents identified (two of these documents have been Common Q safety system development. This document supplements the Common Q SPM, b-d to be addressed at public meeting and audit. Will require a and e provided. By letter dated April 8, 2010 provided on the docket). WCAP-16096-NP-A. The scope of NABU-DP-00014-GEN includes the design and information to be docketed. Need response to b- (ML10101050203), TVA docketed WNA-implementation processes for the application development. For a fuller description of the d. SD-00239-WBT, Revision 1, "RRAS (a) Please describe the third document (i.e., NABU-DP-00014-GEN Revision 2, Design Process design process described in NABU-DP-00014-GEN please refer to the Design Process for Watts Bar 2 NSSS Completion Program for Common Q Safety Systems). AP1000 Common Q Safety Systems, WCAP-15927 on the AP1000 docket. This document I&C Projects, Software Requirements describes the process used for the WB2 PAMS. Specification for the Post Accident (b) Please describe the flow of information between these three documents. Monitoring System, dated February (b) - (d) pending 2010 (ML101050202).

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

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

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

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

145 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open WBN2 PAMS System Design The WBN2 PAMS System Design Specification (WBN2 PAMS SDS) contains a table (see page Addressed in the 9/15 public meeting and 9/20 - 9/21 audit. A detailed explination will be Specification iii) titled, Document Traceability & Compliance, which states that the WBN2 PAMS SDS was provided. TVA to provide date created to support the WBN2 PAMS SysRS. when information TVA docketed WNA-DS-01667-WBT will be docketed. Rev. 1, RRAS Watts Bar 2 NSSS (a) Does the WBN2 PAMS SDS implement all of the hardware requirements in the WBN2 Completion Program I&C Projects Post PAMS SysRS? Accident Monitoring System- System Design Specification, dated December (b) Please briefly describe all of the documents that implement the hardware requirements of 2009.

the WBN2 PAMS SysRS.

146 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: Date: Responsibility: Closed PAMS System Requirements deleted Specifications 147 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: Date: Responsibility: Closed PAMS System Requirements deleted Specifications 148 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: Date: Responsibility: Closed PAMS System Requirements deleted Specifications 149 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Tindell Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR Section 7.1.1.2(2), Overtemperature delta T and Overpressure delta T equations have In FSAR amendment 96 the equations were revised to agree with the Unit 1 UFSAR which is In FSAR amendment 96, the values of the constants have been been simplified and many values are removed from the FSAR. Provide the justification for this the basis document for the Unit 2 FSAR. This resulted in the equations being simplified and moved to TS or plant procedures. Need to document the basis for this TVA to provide date change. the removal of the values for the constants. The equations were revised to match those used change. when information in the Technical Specifications. The values for the constants are contained in the Technical will be docketed.

Specifications and were removed as redundant.

150 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System Many of the changes were based on the Westinghouse document N3-99-4003. Provide this System description N3-99-4003, Reactor Protection System is contained in Attachment __

document for staffs review so the staff can determine the basis for these changes. TVA to provide date when information will be docketed.

151 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System Provide the EDCR 52378 and 54504 which discusses the basis for many changes to this FSAR EDCR 54504 has been voided and replaced with EDCR 52378 which is contained in section. (Attachment ___ ) and EDCR 52671 is contained in (Attachment ___ ). TVA to provide date when information will be docketed.

152 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Merten/Clark Date: Responsibility: Open. TVA to FSAR Section 7.2, Reactor Trip System File: rad4AB2F.xlsx Page 16 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Deleted portion of FSAR section 7.2.3.3.4 and moved to FSAR section 7.2.1.1.5. However, the The text was revised to match the Unit 1 UFSAR. The Unit 1 text was modified in confirm if this FSAR section 7.2.1.1.5 does not include the discussion of ambient temperature and also on the Amendment 1 by FSAR Change Package 1553 S00 which is contained in Attachment 30. description is the calibration of the sealed reference leg system. No justification was provided for deleting this The basis for the change in the change package is: same as for Unit 1.

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

installation attributes found on TVA physical drawings. Also, the hydrogen gas entrainment issue documented in NRC Information Bulletin No. 92-54, Level Instrumentation Inaccuracies TVA to provide date Caused by Rapid Depressurization, is retained and clarified. Similar clarification is made to when information Reactor Protection System Description N3-9g.4003 Section 3.1.1.2(d). The original text in will be docketed.

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 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Craig/Webb Date: Responsibility: Open TVA will send FSAR Section 7.2, Reactor Trip System FSAR section 7.2.1.1.7 added the reference to FSAR section 10.4.4.3 for exception to P-12. Add alternate method of RCS cooldown using additional steam dump valves after entering 50.59.

However, FSAR section 10.4.4.3 states bypass condition is not displayed and it is not Mode 4, by disabling the P-12 Interlock. Operators use additional condenser dump valves to automatically removed when conditions for bypass are no longer met. Provide the basis for aid in maintaining a cooldown rate closer to the administrative limit established by operating TVA to provide date this. procedure. when information will be docketed.

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

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

154 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Craig/Webb Date: Responsibility: FSAR Amd 100. FSAR Section 7.2, Reactor Trip System FSAR section 7.2.1.1.10, setpoints: NRC staff has issued RIS 2006-17 to provide guidance to (Q1) Refer to the response to letter item 13, RAI Matrix Item 51. Since all the setpoint the industry regarding the instrument setpoint methodology which complies with 10 CFR 50.36 and allowable value requirements. Provide the information on how the WBN2 setpoint methodology meets the (Q2) EEB-TI-28's single sided methodology conforms with WBN's design basis commitment for Unit 2 is guidance of RIS 2006-17 and include this discussion in this section. Also, by letter dated May to ensure that 95% of the analyzed population is covered by the calculated tolerance limits as calculated and 13, 2010, TVA provided Rev. 7 of EEB-TI-28 to the staff. The staff noted that section 4.3.3.6 defined in NRC Reg Guide 1.105, Revision 2, 1986 that was in affect during WBN Unit 1 added to TS, TVA of EEB-TI-28 discusses the correction for setpoints with a single side of interest. It should be licensing. needs to address noted that the staff has not approved this aspect of setpoint methodology for Unit 1. The staff the latest criteria finds this reduction in uncertainties is not justified unless it can be demonstrated that the 95/95 and that include criteria is met. Therefore, either remove this reduction factor for single sided uncertainties or 95/95 criteria.

justify how you meet the 95/95 criteria given in RG 1.105.

156 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: WEC Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.1.1 states that dashed lines in Figure 15.1-1designed to prevent Per Westinghouse letter WBT-D-2340, TENNESSEE VALLEY AUTHORITY WATTS BAR exceeding 121% of power.The value of 121% is changed from 118%. The justification for NUCLEAR PLANT UNIT 2 FSAR Markups Units I and 2 118% vs 121 % and Correction to TVA to provide date Response on hold pending this change states that this was done to bring the text of this section in agreement with section RAI Response SNPB 4.3.2-7, (Reference 17) the 118% value should be 121%. Depending when information Westinghouse review.

4.3.2.2.5, 4.4.2.2.6 and table 4.1-1. However, Table 4.1-1 and section 4.3.2.2.5 still show this on the use in the FSAR either 118% or 121% are the correct values. As a result of the will be docketed.

value as 118%. Justify the change. question, Westinghouse reviewed all locations where either 118% or 121% are used and the context of use and provided a FSAR markup to reflect the correct value at the specific location. These changes will be incorporated in a future FSAR amendment.

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

158 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Tindell Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.1.1, paragraph six was changed to state that the design meets the FSAR Amedment 99 reflects the change to Criterion 23.

requirements of Criterion 23 of the 1971 GDC instead of the Criterion 21 of the GDC. The TVA to provide date Criterion 21 is about protection system reliability and testability, while Criterion 23 is about when information protection system failure modes. Since this paragraph deals with the evaluation of design with will be docketed.

respect to common-mode failure, the staff believes that Criterion 23 is the right reference for this paragraph. Please clarify.

File: rad4AB2F.xlsx Page 17 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 159 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Craig Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.1.2 discusses reactor coolant flow measurement by elbow taps. However, Elbow taps are used to measure reactor coolant flow for both Unit 1 and 2. However the it further states that for Unit 2, precision calorimetric flow measurement methodology will be method used to verify reactor coolant flow, as required by the Technical Specifications, is not TVA to provide date used. If elbow taps are not used for Unit 2, then why does this section discuss this the same. Unit 1 uses a simplified methodology based on elbow tap P measurements when information methodology? It is the staffs understanding that TVA plans to use elbow taps methodology in correlated with precision calorimetric data over several cycles of operation as described in will be docketed.

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

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

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

160 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Tindell Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.2(7) deleted text which has references 12 and 14. These references are not The text was revised to match the Unit 1 UFSAR. The Unit 1 text was modified in included in the revised text. Provide the basis for the deletion of these references. Also, the Amendment 1 by FSAR Change Package 1553 S00 which is contained in Attachment 30. TVA to provide date revised text states that typically this requirement is satisfied by utilizing 2/4 logic for the trip The basis for the change in the change package is: when information function or by providing a diverse trip. Provide any exception to this and their basis for will be docketed.

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

161 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.3 states that changes to the control function description in this section are FSAR Amendment 99 reflects the changes associated with the Foxboro I/A system design.

expected to be required after vendor design of the Unit 2 Foxboro IA design is complete. TVA to provide date Provide the schedule for the completion of the design and when this information will be available when information to the staff for review and approval. will be docketed.

162 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Tindell Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.2(14) states that bypass of a protection channel during testing is indicated The Bypassed and Inoperable Status Indication System (BISI) compliance with Reg. Guide by an alarm in the control room. Explain how this meets RG 1.47. 1.47 is described in detail in FSAR Section 7.5.2.2. TVA to provide date when information 164 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Perkins Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR section 7.2.2.2(20) has been revised to include the plant computer as a means to provide The primary purpose of the plant computer is to present plant process and equipment status information read out for all signals which can cause a reactor trip. Justify the use of the plant information to the control room operators to assist them in the normal operations of the unit, TVA to provide date computer for this function. Include the discussion on the effect of plant computer failure on the and inform them of any abnormal conditions. The plant computer obtains real-time plant when information system functions. parameter information via Data Acquisition Systems(DAS)(multiplexers, etc.) by scanning will be docketed.

preassigned analog, pulse, and contact sensors located throughout the plant. The computer is not defined as being primary safety-related and it is not required to meet the single failure criterion or be qualified to IEEE criteria for Class 1E equipment.

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

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

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

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

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

• The software and associated hardware undergoes a detailed Factory Acceptance Test prior to installation in the plant. After installation in the plant, a Site Acceptance Test (SAT) will be conducted. The SAT will include several tests: computer accuracy, analog input accuracy, calculated value accuracy, computer performance, system response times, all input/output 165 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System File: rad4AB2F.xlsx Page 18 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments FSAR section 7.2.2.3.2, last paragraph of this section has been deleted. The basis for this The reference to Section 7.2.2.2 for the general discussion for control and protection deletion is that discussion regarding the compliance with IEEE-279, 1971 and GDC 24 is interactions is provided in Section 7.2.2.3. The reference in Section 7.2.2.3 is applicable to all TVA to provide date covered in section 7.2.2.2. However, there is no reference to this section in 7.2.2.3.2 to direct Sub-Section paragraphs, including 7.2.2.3.2. An additional reference in this section is not when information the reader to 7.2.2.2. Please revise 7.2.2.2 accordingly. necessary and would be redundant to the Section 7.2.2.3 reference. will be docketed.

166 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System Changes to FSAR section 7.2.2.2(20) are justified based on the statement that the integrated EDCR 52322, Design, Procure And Construct An Intergrated Computer System (Ics) For computer system is implemented through EDCR 52322. Provide a copy of EDCR 52322 for Watts Bar Nuclear Plant Unit 2. Provide All Appropriate Documentation To Support Design TVA to provide date staff review. Input. Generate Or Revise All Official Drawings To Represent Final Constuction Configuration when information is contained in Attachment __ will be docketed.

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

168 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System FSAR table 7.2-4, item 9 deleted loss of offsite power to station auxiliaries (station blackout) This this change is in accordance with the Unit 1 UFSAR. The change was made by FSAR based on the fact that station blackout is not listed in AAPC events. Explain what are AAPC Change Package 1553 S00 (Attachment __). The justification for the change is: TVA to provide date events and how it justifies deleting this accident from the list. when information 38 (Table 7.2-4): This table lists the reactor trips and the various accident analyses for which will be docketed.

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

169 June 18, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Closed Describe the design changes which were made to Unit 1 by 10CFR50.59 process and which This is a duplicate of items 2, 10, 11 and 44 significantly affect the instrumentation and controls systems discussed in FSAR Chapter 7.

170 June 17, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Closed TVA needs to document that Arnold Magnetics power supplies have been used and This is a duplicate of item 113.

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 June 17, 2010 NRC POC: EICB (Garg) Date: Responder: Craig Date: Responsibility: Open An external unidirectional communications interface was installed between the Eagle 21 test This item requires further discussion. It has been deleted from the current letter.

subsystem and the plant process computer. TVA should confirm that testing has demonstrated TVA to provide date that two way communication is impossible with the described configuration. (Open Item # 3 of when information Eagle 21 audit) will be docketed.

172 June 17, 2010 NRC POC: EICB (Garg) Date: Responder: Craig Date: Responsibility: Closed During a FAT diagnostic test, the Loop Calculation Processor (LCP) failed while performing a This is a duplicate of the rack 5 update issue item 114.

parameter update. TVA should identify the cause and fix for the problem encountered. (Open Item # 1 of Eagle 21 audit) 173 June 17, 2010 NRC POC: EICB (Garg) Date: Responder: Craig/Webb/Powers Date: Responsibility: Open EEB-TI-28 discusses the correction for setpoints with a single side of interest. The staff finds this correction factor is not justified. TVA should justify this correction factor and demonstrate TVA to provide date that, with this correction, factor 95/95 criteria identified in RG 1.105 is met. when information will be docketed.

174 June 28, 2010 NRC POC: EICB (Garg) Date: Responder: Hilmes/Craig Date: Responsibility: Closed Placeholder: The staff has identifed questions regarding unidirectional communications Duplicate of 171 interface. The staff will keep this item open until TVA confirms testing has demonstrated that two way communication is impossible with the described configurations.

176 June 28, 2010 NRC POC: EICB (Garg) Date: Responder: Craig/Webb Date: Responsibility: Open Placeholder: The staff has identified questions regarding instrument setpoints. The staff will keep the instrument setpoint methodology issue open until TVA provides additional information TVA to provide date regarding RIS 2006-17 and single sided correction factor for uncertainty determination. when information will be docketed.

177 July 15, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open File: rad4AB2F.xlsx Page 19 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments FSAR Amendment 99 Section 7.5.1.2 states: "Type A Variables Those variables that provide The type A variables are the same in Unit 1 and Unit 2. See calculation WBNOSG4047 Rev. August 19, 2010 - TVA to submit calculation.

primary information to the MCR operators to allow them to take preplanned manually controlled 4 (Attachment ) TVA to docket actions for which no automatic action is provided and that are required for safety systems to calculation.

accomplish their safety functions for Chapter 15 design basis events. Primary information is information that is essential for the direct accomplishment of specified safety functions."

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

178 July 15, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open Please provide WBN-OSG4-047, "PAM Type A Variable Determination." See response to item 177 above. August 19, 2010 - TVA to submit calculation.

TVA to docket calculation.

179 July 15, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the Steve Clark to look at how to combine traceability items.

unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed TVA to provide date in Regulatory Guide 1.172, which breaks with typical NRC use of the word should regarding Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information backwards traceability to say Each identifiable requirement in an SRS must be traceable will be docketed.

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 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open The SRP, BTP 7-14, Section B.3.3.1 states that Regulatory Guide 1.172 endorses, with a few Steve Clark to look at how to combine traceability items.

noted exceptions, IEEE Std 830-1993. IEEE Recommended Practices for Software TVA to provide date Requirements Specifications. Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information will be docketed.

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

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

If no then please provide an evaluation that includes an identification and description of all differences proposed from the acceptance criteria given in SRP , BTP 7-14, Section B.3.3.1.

Please describe how the alternatives provide an acceptable method of complying with those regulations that underlie the corresponding SRP acceptance criteria.

181 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the Steve Clark to look at how to combine traceability items.

unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed TVA to provide date in Regulatory Guide 1.172, which breaks with typical NRC use of the word should to say Each Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information identifiable requirement in an SRS must be traceable backwards to the system requirements will be docketed.

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

182 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 20 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Characteristics that the SRP states that an Software Requirements Specifications should have Somewhat redundant with question on Shalls outside of the "requirements" sections.

include unambiguity, verifiability, and style, part of the latter is that Each requirement should be TVA to provide date uniquely and completely defined in a single location in the SRS. Shalls included in non-numbered sections and general discussions. when information will be docketed.

Clarify whether the unnumbered paragraphs in the Post Accident Monitoring Systems Software To be addressed at the 9/15 public meeting.

Requirements Specification, such as in the section headings, or are all such sections simply considered to be informative? WEC will probably remove or move to another document be in compliance with IEEE 830.

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

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

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

183 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open An emphasis is placed on traceability in System Requirements Specifications in the SRP, in the Steve Clark to look at how to combine traceability items.

unmodified IEEE std 830-1993, and even more so given the modifications to the standard listed TVA to provide date in Regulatory Guide 1.172, which breaks with typical NRC use of the word should to say Each Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information identifiable requirement in an SRS must be traceable backwards to the system requirements will be docketed.

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 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open The NRC considers that a System Requirements Specification is the complete set of Steve Clark to look at how to combine traceability items.

requirements used for the design of the software, whether it is contained within one document TVA to provide date or many. In order to evaluate an SRS against the guidance in the SRP the staff needs access Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information to all the requirements. will be docketed.

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 July 15, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 21 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments An emphasis is placed on the traceability of requirements in Software Requirements Steve Clark to look at how to combine traceability items.

Specifications in the SRP, in the unmodified IEEE std 830-1993, and even more so given the TVA to provide date modifications to the standard listed in Regulatory Guide 1.172, which breaks with typical NRC Will be addressed to during the 9/15 meeting and 9/20 - 9/21 audit. when information use of the word should to say Each identifiable requirement in an SRS must be traceable will be docketed.

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 July 15, 2010 NRC POC: EICB (Darbali) Date: Responder: Perkins/Clark Date: Responsibility: Once FSAR Along with Amendment 96, TVA submitted a list of Bechtel changes for each section. Change This change will be included in FSAR Amendment 101. Response is satisfactory. Issue date of Amendment 101 is not yet Amendmet 101 is number 45 addresses a change to section 7.7.1.12, AMSAC, however, the Justification column determined. received, the item will states This change is not included. EDCR 52408 installs the AMSAC in Unit 2. It does not EDCR 52408 Summary: be closed.

have a trouble alarms. The existing words better reflect the operation of the system. A Purchase Order was issued to Nutherm International to provide a Unit 2 cabinet with the Response is acceptable awaiting FSAR amendment submittal.

same functions as the current Unit 1 AMSAC. EDCR 52408 will install the cabinet and Even thought this change was not included in Amendment 96, will it be included in a future route/install cabling to provide the necessary inputs/outputs for/from the AMSAC cabinet. The amendment? EDCR will only route and install cables from the cabinet to the field side of a terminal block in the Main Control Room panel 2-M-3. These cables will provide the AMSAC NOT ARMED Also, please submit a summary of EDCR 52408. and AMSAC ACTUATED signals to annunciator windows.

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

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

187 July 20, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: Open By letter dated June 18, 2010, TVA docketed responses to NRC requests for information. 1) The original design was to allow printing from both the Operator Module (OM) and NNC 8/25/10: Why did TVA not catch this on the review of the PAMS Are these connections already Maintenance and Test Panel (MTP) via the plant computer. This required both to be SysRS or SRS? Does TVA check that the CQ PAMS system meets docketed?

1) Enclosure 1, Item No. 33 of the TVA letter dated June 18, 2010, did not identify any connected to the plant computer. Westinghouse did not perceive this as an issue, because the requirements in its purchase specifications?

connection from the PAMS Operator Modules (OMs) to the plant computer and printers; the standard Common Q PAMS design includes both the flat panel displays and individual however, Figure 2.1-1 of the PAMS System Requirements Specification (WNA-DS-01617-WBT control panel indicators. The Westinghouse Common Q team did not realize that WBN does Rev. 1 - ML101680578) shows a TCP connection from the OMs to the plant computer and not use the individual control panel indicators. As a result, the original design documents printer. Please explain. provided by Westinghouse included the connection from the OM to the plant computer.

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

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

File: rad4AB2F.xlsx Page 22 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 188 July 20, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: Open By letter dated June 30, 2010, TVA docketed, Tennessee Valley Authority (TVA) Watts Bar Unit 1) The original design was to allow printing from both the Operator Module (OM) and NNC 08/25/10: See Open Item No. 187. TVA to respond or 2 (WBN2) - Post-Accident Monitoring System (PAMS) Licensing Technical Report, (Document Maintenance and Test Panel (MTP) via the plant computer. This required both to be provide proposed Number WNA-LI-00058-WBT- P, Revision 0, June 2010) (Westinghouse Proprietary Class 2). connected to the plant computer. Westinghouse did not perceive this as an issue, because date of response.

the standard Common Q PAMS design includes both the flat panel displays and individual

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

TCP connection from the OMs to the plant computer and printer. Please explain.

The TVA team did not realize that the Westinghouse design relied on the OM and MTP to be

2) Section 5.3, Response to individual criteria in DI&C-ISG-04, of the PAMS Licensing Topical qualified isolation devices that protected the AC160 functions and individual control panel Report does not address the TCP connection between the OM and non-safety components indicators from interference from the plant computer. It was not until a meeting was held to depicted in Figure 2.1-1 of the PAMS System Requirements Specification (WNA-DS-01617- discuss the design of the OM that the issues came to light. That was when Westinghouse WBT Rev. 1 - ML101680578). Please explain. understood that the OM was the PAMS display and WBN did not use individual control panel indicators and TVA understood that the OM was being credited as the qualified isolation device. It became apparent at the meeting to both TVA and Westinghouse that the original design was not acceptable. The team then agreed deleting the OM connection to the plant computer was the best option to resolve the problem.

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

189 July 20, 2010 NRC POC: EICB (Singh) Date: Responder: Clark Date: Responsibility: Open FSAR Section 7.6.7States: Conformance with Regulatory Guide 1.133, Revision 1 is discussed This is a typographical error. The correct reference is Table 7.1-1. The reference will be NNC 8/25/10: Acceptable response. TVA to Docket FSAR in Table 7.1-7. FSAR Chapter 7 does not contain any such numbered table. Please explain. corrected in FSAR Amendment 100. Amendment 100.

190 July 20, 2010 NRC POC: EICB (Singh) Date: Responder: Clark Date: Responsibility: Open FSAR Table 7.1-1 states: Regulatory Guide 1.133, May 1981 Loose-Part Detection Program 1) TSR 3.3.6.3 specifies 18 months as the calibration frequency. TVA to revise for the Primary System of Light-Water Cooled Reactors, Revision 1 (See Note 12)Note 12 response.

Conforms except as noted belowPositi[o]ns C.3.a.(3) and C.5.c. recommend a channel 2) Per the Technical Requirements Manual (TRM) Bases 3.3.6 (Attachment __) the calibration be performed at least once pe[r] 18 months. In lieu of this recommendation, the surveillance requirements and frequency are provided in Regulatory Guide 1.133, "Loose-Part DMIMS will be calibrated at the frequency stated in subsection TSR 3.3.6.3 of TR 3.3.6 (Loose- Detection Program for the Primary System of Light-Water-Cooled Reactors."

Part Detection System).

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

1) Clarify what frequency is specified in TSR 3.3.6.3.

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 July 20, 2010 NRC POC: EICB (Carte) Date: Responder: Jimmie Perkins Date: Responsibility: Open NUREG-0800 Chapter 7, Section 7.9, "Data Communication Systems" contains review criteria WBN Unit 2 is in compliance with the regulatory requirements for data communications NNC 8/25/10: Information received, and read. NRC to review NNC 8/9/10: In response to TVA's for data communication systems. The WBN2 FSAR did not include any description of data systems as described in Attachment 33 (Data Communications Systems Description and information provided requet for clarification, a reference to communications systems. Regulatory Compliance Analysis). appropriate SRP section was added.

1) Please identify all data communications systems.

2) Please describe each data communications system identified above. See item 4

3) Please provide a regulatory evaluation of each data communications system against the applicable regulatory criteria.

192 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open File: rad4AB2F.xlsx Page 23 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments The NRC Staff is using SRP (NUREG-0800) Chapter 7 Section 7.5, Instrumentation Systems 11. At WBN Unit 1 and 2, there is a single computer system named the Integrated Computer August 19, 2010 - NRC to review TVA response. NRC to review Important to Safety, to review the WBU2 FSAR Section 7.5, Instrumentation Systems System or ICS. That system is sometimes described as the Plant Computer System, the Response.

Important to Safety. The following requests are for information that the SRP directs the Process Computer, the Technical Support Center Data System (TSCDS) or the Emergency reviewers to evaluate. Response Facility Data System (ERFDS). At one time, the TSCDS and ERFDS were separate computers on unit 1 but their functions were all incorporated into the ICS when it The role of the EICB Technical reviewer is to determine if there is reasonable assurance that the was installed.

equipment will perform the required functions. The WBU2 FSAR, Section 7.5.2, Plant Computer System, does not contain any description of the equipment that performs the 2. The Watts Nuclear Plant ICS is a non-safety related system, is designed as a single, large-functions described in the section. Enclosure 1 Item 3 of letter dated March 12, 2010, TVA scale nuclear plant computer system which integrates balance of plant (BOP) monitoring with stated that the platform of the Process Computer was, Hewlett Packard RX2660 and Dell extensive nuclear steam supply system (NSSS) application software into a comprehensive Poweredge R200 servers with RTP Corp 8707 I/O. In addition TVA provided (a) two pages of computer based tool for plant operations. The system is comprised of the following major marketing literature by DELL on the Poweredge R200 Server, (b) the HP Integrity rx2660 components:

Server Unser Service Guide, and (c) the Integrated Computer System Network Configuration

• Remote multiplexers in the Computer Room, Auxiliary Instrument Room and 480V Board Connection Diagram (2-45W2697-1-1 dated 8/27/09). This provided information is not sufficient rooms.

for evaluating whether the equipment will, with reasonable assurance, perform the functions

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

• Data Storage Devices

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

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

• Networking equipment including switches, firewalls and terminal servers

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

• Printers

• Data Links to other plant computer devices (serial and network)- These systems or devices

3) Please describe the relationship between the Plant Computer System and the Integrated include but are not limited to:

Computer System.

o System Foxboro I/A Systems (unit 2 only) o Arreva Beacon core monitoring systems o Multi-pen recorders o Landis & Gyr switchyard monitoring system o Computer Enhanced Rod Position Inidication (CERPI) o Eagle 21 o Ronan Annunicator o Leading Edge Flow Meter (LEFM) o Bently-Nevada vibration monitoring system o Inadequate Core Cooling Monitor (ICCM) (unit 1 only) o Common Q (unit 2 only) o WinCISE (unit 2) 193 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open The WBU2 FSAR, Section 7.5.2, Plant Computer System, contains three subsections, There is a single set of hardware that incorporates the functionality of Safety Parameter TVA to respond or 7.5.2.1, Safety Parameter Display System Display System (SPDS), Bypass and Inoperable Status Indication System (BISI) and the provide proposed 7.5.2.2, Bypassed and Inoperable Status Indication System (BISI) Technical Support Center (TSC). date of response.

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

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

194 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open The WBU2 FSAR Section 7.5.2.1, Safety Parameter Display System, contains a description of The principal purpose and function of the SPDS is to aid control room personnel during TVA to respond or the Safety Parameter Display System. abnormal and emergency conditions in determining the safety status of the plant and in provide proposed assessing if abnormal conditions require corrective action by the operators to avoid a degraded date of response.

SRP Section 7.5, Subsection II, Acceptance Criteria states: core. It also operates during normal operations, continuously displaying information from which Requirements applicable to the review of SPDS10 CFR 50.55a(a)(1), Quality Standards. 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:

• 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 File: rad4AB2F.xlsx Page 24 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 195 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open Bypassed and Inoperable Status Indication (BISI) The BISI system is a computer based system that provides automatic indication and TVA to respond or annunciation of the abnormal status of each ESFAS actuated component of each redundant provide proposed The WBU2 FSAR Section 7.5.2.2, Bypassed and Inoperable Status Indication System (BISI), portion of a system that performs a safety-related function. date of response.

contains a description of the Bypassed Inoperable Status Indication System (BISI).

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

196 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open Bypassed and Inoperable Status Indication (BISI) Section C of the Regulatory Guide lists the following six regulatory positions for guidance to TVA to respond or satisfy the NRC requirements with respect to the bypassed and inoperable status provide proposed The NRC staff is performing its review in accordance with LIC-110, Rev. 1, Watts Bar Unit 2 indication(BISI) for nuclear power plant safety systems: date of response.

License Application Review. LIC-110 directs the staff to review systems unique to Unit 2 in accordance with current staff guidance. Regulatory Guide (RG) 1.47 Revision 1, Bypassed and 1. Administrative procedures should be supplemented by an indication system that Inoperable Status indication for Nuclear Power Plant Safety Systems, is the current regulatory automatically indicates, for each affected safety system or subsystem, the bypass or guidance for BISI. Please provide a regulatory evaluation of BISI against the current RG. deliberately induced inoperability of a safety function and the systems actuated or controlled by the safety function. Provisions should also be made to allow the operations staff to confirm that a bypassed safety function has been properly returned to service.

Response: The BISI system provides indication(displays and annunciation) that a functional path for each train of a safety system or support system has been rendered in a state which could cause inoperability. The BISI system monitors and provides system level alarms for these plant safety-related systems:

• 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.

198 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open File: rad4AB2F.xlsx Page 25 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments SRP Section 7.5, Subsection III, Review Procedures states: Recommended review emphasis F. The scope of the WBN BISI indications are based on engineering calculation TVA to respond or for BISI WBPEVAR8807025 Rev. 7 (Attachment __). This calculation has not been updated for Unit provide proposed F. Scope of BISI indications - As a minimum, BISI should be provided for the following systems: 2. The calculation does include Common and Unit 2 equipment required to support Unit 1 date of response.

- Reactor trip system (RTS) and engineered safety features actuation system (ESFAS) - See operation.

SRP Appendix 7.1-B subsection 4.13, Indication of Bypasses, and SRP Appendix 7.1-C G. Compliance to Regulatory Guide 1.47 is described in design criteria document WB-DC subsection 5.8.3, Indication of Bypasses. 29 Rev. 8, Integrated Computer System (Attachment __) which is a design input to

- Interlocks for isolation of low-pressure systems from the reactor coolant system - See SRP calculation WBPEVAR8807025 Rev. 7 (Attachment __).

BTP 7-1. H. Design criteria document WB-DC-30-29 Rev. 8, Integrated Computer System (Attachment

- ECCS accumulator isolation valves - See SRP BTP 7-2. __), section 3.4.1, BISI Design and Operation states: The BISI shall not be designed to

- Controls for changeover of residual heat removal from injection to recirculation mode - See safety related system criteria and therefore is not to be used to perform functions essential to SRP BTP 7-6. the health and safety of the public. Class 1E isolation is required, however, to maintain the G. Conformance with Regulatory Guide 1.47, Bypassed and Inoperable Status Indication for independence of safety related equipment and systems.

Nuclear Power Plant Safety Systems. I. - Response in letter from Mike Norman H. Independence - See SRP Appendix 7.1-B subsection 4.7, Control and Protection System Interaction, and SRP Appendix 7.1-C subsections 5.6, Independence, and 6.3, Interaction Between the Sense and Command Features and Other Systems. The indication system should be designed and installed in a manner that precludes the possibility of adverse effects on plant safety systems. Failure or bypass of a protective function should not be a credible consequence of failures occurring in the indication equipment, and the bypass indication should not reduce the required independence between redundant safety systems.

I. Use of digital systems - See SRP Appendix 7.0-A and Appendix 7.1-D.

Please provide a description of how BISI meets each item above, or provide appropriate justification for not doing so.

199 July 20, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open The WBU2 FSAR Section 7.5.2.3, Technical Support Center and Nuclear Data Links, contains The Technical Support Center is intended to be an accident mitigation support center and TVA to respond or Related SE Section 7.5.5.3 a description of the Technical Support Center and Nuclear Data Links. provides Satellite Display Stations (SDS) capable of displaying information on plant systems provide proposed for Unit 1, Unit 2 or the Simulator. Stations in the TSC receive data from the plant Integrated date of response.

SRP Section 7.5, Subsection II, Acceptance Criteria states: Computer System (ICS) over the ICS network. Separate PCs receive data from the Requirements applicable to the review ofERF information systems, and ERDS information simulator computer over the WBN site network to support drills and training exercises. Those systems 10 CFR 50.55a(a)(1), Quality Standards. PCs can also access the Plant Engineering Data System (PEDS) as a backup to ICS. The TSC also has a separate computer that connects to the CECC to allow additional access to Please provide a description of how the nuclear data links meets this regulatory requirement. 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 July 21, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: NRC Review Amendment 99 of the Watts Bar Unit 2 FSAR Section 7.5, Instrumentation Systems Important The statement in SER Section 7.5.1 is supported by the following: Related to SE Section 7.5 to Safety, does not include any description of instrumentation for normal operation; therefore, Section 7.5 of the FSAR does not support statements made in the SER Section 7.5; compare I&C Systems for Normal Operation FSAR Section SER (ML072060490) Section 7.5.1 and FSAR Amendment 99 Section 7.5. Please identify Eagle 21 7.2 where, in the docketed material, information exists to support the statements in the SER Neutron Monitoring 7.2 Section 7.5.1. Foxboro Spec 200 7.3 (List of other sections in attachment 34)

Foxboro I/A 7.7.11 (new section will be added by amendment 101) (other sections have been previously provided)

Plant Computer 7.5.2 Rod Control 7.7.1.2 CERPI 7.7.1.2 Control Rod Drive 7.7.1.1 Incore Neutron Monitoring 7.7.1.9 Lose Part Detection/Monitoring 7.6.7 Vibration Monitoring RCP 5.5.1.2 Control Boards 7.1.1.10 RVLIS 7.5, 5.6 201 July 21, 2010 NRC POC: EICB (Carte) Date: Responder: Webb Date: Responsibility: Open Amendment 99, FSAR Section 7.7.1.1.1, "Reactor Control Input Signals (Unit 2 Only)," contains These functions are within the scope of the Foxboro I/A system. Section 7.7.11 will be added TVA to docket Related to SE Section 7.7.1.1.1 a description of functions performed uniquely for Unit 2. Please describe the equipment that to the FSAR in amendment 101 to provide a discussion of the DCS. amendment 101.

performs this function (in sufficient detail to support a regulatory evaluation), and evaluate this equipment against the appropriate regulatory criteria.

202 July 22, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 26 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments The letter (ML0003740165) which transmitted the Safety Evaluation for the Common Q topical Revision 1 of the Licensing Technical Report will provide more detailed information on TVA to respond or Relates to SE Section 7.5.2, PAMS report to Westinghouse stated: "Should our criteria or regulations change so that our conclusions the changes to the platform. provide proposed as to the acceptability of the report are invalidated, CE Nuclear Power and/or the applicant date of response.

referencing the topical report will be expected to revise and resubmit their respective Rev. 2 of the Licensing Technical Report wil include the applicability of guidance.

documentation, or submit justification for continued applicability of the topical report without revision of the respective documentation." Question No 81 identified many criteria changes; please revise the respective documentation or submit justification for continued applicability of the topical report.

203 July 26, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open By letter datedApril 27, 2010 (ML101230248), TVA stated (Enclosure Item No.19): "The WBN The plant computer system is one set of hardware. The Safety Parameter Display System, TVA to respond or Unit 2 Itegrated Computer System(ICS) modification merges the ERFDS and plant computer Bypassed and Inoperable Status Indication System (BISI), Technical Support Center and provide proposed into a single computer network." Nuclear Data Links are all functions of the Plant Computer System. Historically the date of response.

Westinghouse P2500 Plant Process Computer and Emergency Response Facilities Data FSAR Section 7.5.2, "Plant Computer System," has three subsections: System (ERFDS) were individual systems but were merged together with the implementation 7.5.2.1, "Safety Parameter Dispaly System" of DCN 39911-A, implemented for WBN Unit 1 in December 1998, to become the Plant 7.5.2.2, "Bypassed and Inoperable Status Indication System (BISI)" Integrated Computer System (ICS). A similar system is being installed for WBN Unit 2 based 7.5.2.3, "Technical Cupport Center and Nuclar Data Links" on the same software with more modern hardware.

This arrangement implies that the each of these function are part of the plant computer, and not a separate sets of equipment. Please describe the equipment for each function and identify any The ICS is composed of a number of pieces of hardware, all utilized as a system, to provide equipment common to more than one function. the functions listed in the FSAR sections 7.5.2.1, 7.5.2.2 and 7.5.2.3. This hardware includes but is not limited to Hewlett Packard (HP) servers (CPU), DELL servers (CPU), Fiber Optic Panels, Fiber Optic Converters, Switches, Firewalls, Network Taps, Multiplexors (RTP), LCD displays and fiber optic and copper Ethernet cables. As all the applicable hardware make up the system it is all common to more than one function and there is no separate set of equipment for any of the functions referenced in FSAR Section 7.5.2.1 and 7.5.2.2.

The Nuclear Data Link and EOF functions described in 7.5.2.3 are provided by the CECC in Chattanooga. In order for the CECC to have access to ICS data, both the PEDS and the data diode isolating the PEDS from the ICS must be operational.

Meteorological data from the Environmental Data Station (EDS) is gathered by the Unit 1 204 July 26, 2010 NRC POC: EICB (Marcus) Date: Responder: Costley/Norman Date: Responsibility: Open By letter dated March 12, 2010 (ML101680577) TVA provided drawing No. 2-45W2697-1-1, 1. Three data diodes. TVA to respond or Relates to SE Section 7.5.2, PAMS "Integrated Computer System Network Configuration Connection Diagram," that depics three 2. Two provide an interface between train A and B of Common Q. provide proposed "Data Diode"s. Please provide a detailed description of the equipment, software, and a. These are identical systems consisting of the following: date of response.

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:

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 July 26, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open Regarding the Foxboro Spec 200 system installed at Unit 2: As discussed at the August 3 and 4 meeting in Knoxville between TVA and the NRC, the TVA to respond or Question B related to prior NRC Foxboro Spec 200 is not a system. The Foxboro Spec 200 analog hardware is used to provide proposed approval of this system or 50.59 a- Is it similar to Unit 1? If not, identify the differences and evaluation of the acceptability of replace the existing obsolete hardware with the same functions. There are no date of response. information. This question will be these differences. interconnections between the analog loops unless such interconnections existed prior to the addressed in the August plant visit.

replacement. This is strictly an analog to analog upgrade due to equipment obsolescence.

b- deleted The Foxboro hardware is installed in existing cabinets which require modifications to accept the Foxboro hardware racks.

c- For each system which is discussed in the FSAR and utilizes the Spec 200 system, please provide the instrument logic diagram, loop/block diagram with reference to where the system is a- A listing of the replacements and differences was previously provided as Attachment 1 to discussed in the FSAR. 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 206 July 27, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open File: rad4AB2F.xlsx Page 27 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments The NRC Requested a description of the plant computer and TVA provided: (1) The Plant Computer is not just a computer but is a system and is designated the TVA to respond or Relates to SE Section: 7.5.5, Plant (1) Dell marketing literature for Dell Poweredge R200 Server, which can be found on the internet Integrated Computer System or ICS. The ICS is composed of multiple computer CPUs, LCD provide proposed Computer (http://www.dell.com/downloads/global/products/pedge/en/pe_R200_spec_sheet_new.pdf), and displays, RTP Multiplexer Assemblies, network fiber optic panels, fiber optic converters, date of response.

(2) HP Integrity rx2660 Server User Service guide (edition 6), which has not yet been found on Ethernet switches and network taps previously described in items 71, 81 and 82 above. For a the internet, but many other editions have been found. detailed discussion of the ICS functions refer to design criteria document WB-DC-30-29 Rev.

This information is not adequate for answering the question. (Note: TVA also provided a network 8, Integrated Computer System submitted under TVA letter dated August __, 2010.

configuration connection diagram, which is necessary but not sufficient.)

(2) As previously discussed in item 82, there is no unique set of hardware for any specific Please provide a description of the plant computer: function.

(1) Please include sufficinet detail so that an evaluation can be mde against the SRP acceptance criteria in SRP Section 7.7.

(2) Please identify the equipment (hardware and software) that performes each function described in the FSAR.

208 July 27, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional The notes provided with the table include the change to the variable under 10 CFR 50.59. For TVA to respond or Relates to SE Section: 7.5.2, PAMS information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the ease of review, the other note references have been deleted for these variables and only the provide proposed variable was: (1) implemented identically to Unit 1 and reviewed by the NRC, (2) implemented note dealing with the Unit 1 change has been retained in the Notes column of the table date of response.

identically to Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) excerpt. The applicable notes are highlighted in the notes list.

implemented in a manner that is unique to Unit 2. There were sixteen variables modified under 10 CFR 50.59; please describe the changes that were performed under 50.59.

209 July 27, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional The first eight variables in question are primary chemistry parameter. The parameters are the TVA to respond or Relates to SE Section: 7.5.2, PAMS information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the same for both units, but in Unit 1, the sample is obtained via the post accident sampling provide proposed variable was: (1) implemented identically to Unit 1 and reviewed by the NRC, (2) implemented system, while in Unit 2 the sample is obtained using a grab sample via the normal sample date of response.

identically to Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) system.

implemented in a manner that is unique to Unit 2. There were nine variables that were identified as both Unique to Unit 2 and identical to what was reviewed and approved on Unit 1. The last variable was somewhat difficult to characterize. The method of detection and the Please explain. hardware manufacturer is the same in both units. However, due to obsolescence some of the parts are different than what is installed in Unit 1. The differences are described in Note 21 of the original response.

210 July 27, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open By letter dated June 18, 2010 (ML101940236), TVA responded to an NRC request for additional The design basis for Unit 2 is to match Unit 1 as closely as possible. This includes TVA to respond or Relates to SE Section: 7.5.2, PAMS information. Enclosure 1 Item No. 6 of this letter identified, for each PAM variable whether the incorporating changes made to Unit 1 after licensing under 10 CFR 50.59. The changes in provide proposed variable was: (1) implemented identically to Unit 1 and reviewed by the NRC, (2) implemented question fall into this category and are described in the Notes for each variable in the original date of response.

identically to Unit 1 but modified under 10 CFR 50.59 after it was reviewed by the NRC, and (3) submittal.

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 July 27, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: Open FSA Table 7.1-1 shows: "The extent to which the recommendations of the applicable NRC The WBN 2 FSAR Section 7.5 defines the following systems as important to safety TVA to respond or Relates to SE Sections:

regulatory guides and IEEE standards are followed for the Class 1E instrumentation and control provide proposed 7.5.5, Plant Computer systems is shown below. The symbol (F) indicates full compliance. Those which are not fully 1. Post Accident Monitoring including: date of response. 7.6.10, Loose Part Monitoring implemented are discussed in the referenced sections of the FSAR and in the footnotes as a. Common Q Post Accident Monitoring System (Safety-Related) 7.7.1, Control System Description indicated." i. Reactor Vessel Level 7.7.2, Safety System Status Monitoring ii. Core Exit Thermocouples System Please describe how systems that are important to safety, but not 1E, comply with 10 CFR iii. Subcooling Margin Monitor 7.7.4, Pzr & SG Overfill 50.55a(a)1: "Structures, systems, and components must be designed, fabricated, erected, b. Eagle 21 indications (Safety-Related) 7.9, Data Communications constructed, tested, and inspected to quality standards commensurate with the importance of c. Foxboro Spec 200 indications (Safety-Related) the safety function to be performed." d. Neutron Monitoring (Source and Intermediate Range) (Safety-Related)

e. Radiation Monitors (Safety-Related)

f. Unit 1 and Common shared indications (Safety-Related)

g. Foxboro I/A indications (Non-Safety-Related)

h. Radiation Monitors (Non-Safety-Related)

i. CERPI (Non-Safety-Related)

j. Integrated Computer System (Non-Safety-Related)

k. Unit 1 and Common shared indications (Non-Safety-Related)

Post Accident Monitoring Instrumentation Design Criteria, WB-DC-30-7, Rev. 22, Appendix A provides the minimum quality requirements for each Category (1, 2 or 3) of variable. By definition, no Category 1 variable can be non-safety-related. Therefore, non-safety-related variables and the source equipment are limited to category 2 or 3. Since some variables are designated as having more than 1 category, the requirements of the highest category apply.

Additional design criteria information for specific systems is contained in:

g. Foxboro I/A - Site-Specific Engineering Specification WBN Unit 2 NSSS and BOP Controls Upgrade Specification Rev. 1 (Attachment 23)

h. CERPI - Rod Control System Description, N3-85-4003, Rev. 12 Section 2.2, Design Requirements 212 July 27, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 28 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. Application specific requirements for testing. This cannot be addressed in a topical TVA to respond or Relates to SE Section 7.5.2

3) that the PAMS system design specification and software requirements specification contain report. Evaluation of how the hardware meets the regulatory requirements. provide proposed information to address the "Design Report on Computer Integrity, Test and Calibration..." The date of response.

staff has reviewed these documents, and it is not claer how this is the case. WEC to provide the information and determine where the information will be located.

(1) Please describe how the infomation provided demonstrates compliance with IEEE 603-1991 Clauses 5.5, 5.7, 5.10, & 6.5.

(2) Please describe how the infomation provided demonstrates conformance with IEEE 7-4.3.2-2003 Clauses 5.5 & 57.

213 July 27, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. Carte to review and revise this question. TVA to respond or Relates to SE Section 7.5.2

3) that the PAMS system design specification and software requirements specification contain provide proposed information to address the "Theory of Operation Description." The staff has reviewed these date of response.

documents, and it is not claer how this is the case. The docketed material does not appear to contain the design basis information that is required to evaluaate compliance with the Clause of IEEE 603.

(1) Please provide the design basis (as described in IEEE 604 Calsue 4) of the Common Q PAMS.

(2) Please provide a regulatory evaluation of how the PAMs complies with the applicable regulatory requirements for the theory of opration.

For example: Regarding IEEE 603 Clause 5.8.4 (1) What are the manually controled protective actions? (2) How do the documents identified demonstrate compliance with this clause?

214 July 27, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By leter dated June 18, 2010 (ML101940236) TVA stated (Enclosure 1, Attachment 3, Item No. According to "The Software Program Manual for Common Q Systems," WCAP-16096-NP- WEC References Common Q PAMS preliminary hazards analysis TVA to respond or

10) that the approved Common Q Topical Report contains information to address the "Safety 1A, the Software Safety Plan only applies to Protection class software and PAMS is classified is referenced in the SRS. WEC to delete. provide proposed Analysis." The Common Q SPM however states that a Preliminary Hazards Analysiss Report as Important-to-safety. Exhibit 4-1 of the SPM shows that PAMS is classified as Important-to- date of response.

and the V&V reports document the software hazards analysis. Please Provide these Safety documents.

215 July 29, 2010 NRC POC: DORV (Bailey) Date: Responder: WEC Date: Responsibility: Open By letter dated June 18, 2010, TVA provided a talbe showing the documents that had been Close this item TVA to respond or completed and were available for staff review. In a conference call on July 27, 2010, TVA provide proposed agreed to submit the requested documents on the docket. Please provide the schedule for date of response.

submitting the documents.

216 July 29, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open By letter dated March 12, 2010 (ML101680577), TVA stated that it would provide five 1) EDCR 52322 is contained in Attachment 7. TVA to respond or documents to describe the Process computer: (1) EDCR 52322 Rev. A excerpts, (2) HP 5) The design change referred to is the addition of a data diode. This has not been provide proposed RX2660 Users Guide AB419-9002C-ed6, (3) Dell Poweredge R200 Server sheet November incorporated into the drawing. Please see the response to letter item 88 (RAI Matrix Item date of response.

2007, (4) RTP Corp 8707 I/O Brochure RTP 8707-02, 2004, and (5) Integrated Computer 224).

System Drawing.

By letter dated April 27, 2010 (ML101230248), TVA stated (Enclosure Item No. 20) stated that design changes are planned, therefore a revision to the drawing (5) and EDCR (1) are required.

Please privide updated version of (1) and (5).

217 NRC Garg 7/6/2010 Date: Responder: Clark Date: Responsibility: NRC Review NRC POC: EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that provide the block and logic diagrams for Attachment 7 contains excerpts of the following change documents:

the Foxboro 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 ansd as such are implemented under 10CFR50.59.

EDCR 52343 EDCR 52427 218 NRC Garg 7/6/2010 Date: Responder: Clark Date: Responsibility: NRC Review NRC POC: EICB (Garg)

Provide copies excerpts of the EDCRs and DCNs that provide the block and logic diagrams for The excerpt of work order WO 08-813412-000 provided with the June 18 letter did not contain Attachment 8 contains the required correct work order excerpt.

the Foxboro Spec 200 implementation. the information showing that the new type (Arnold) power supplies had been installed in the Unit 1 Eagle 21 system. Please provide the necessary pages of the work order to verify the installation of Arnold power supplies in the Unit 1 Eagle 21 System.

219 NRC Garg/Kemper 4-Aug-10 Date: Responder: TVA Licensing Date: Responsibility: Open Transmit copy of February 8, 2008 FSAR Red-Line for Unit 2 letter with attachments [CD]. A copy was hand carried by Mr. W. Crouch and delivered to Stewart Bailey at the August 17 Check what sent by Terry missing attachments.

meeting at NRC headquarters.

220 NRC Garg/Kemper 8/4/2010 Date: Responder: Ayala Date: Responsibility: Open NRC POC: EICB (Garg)

File: rad4AB2F.xlsx Page 29 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments For Safety Related SSPS, submit letter justifying delta between U1 [utilizing ARs] & U2 [utilizing The Westinghouse ARLA latch attachment is obsolete. In order to provide a latching relay for Are there any open issues? Docket plant specific responses to TVA to respond or ARs and MDRs]. [Requires TS change ???] Unit 2 Solid State Protection System (SSPS), a MDR latching relay must be used. MDR the individual. provide proposed relays are currently in use and shown to be reliable as SSPS Slave Relays in other date of response.

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 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 NRC Marcus 8/4/2010 Date: Responder: Trelease Date: Responsibility: Open NRC POC: EICB (Marcus)

Submit EDCR Technical Evaluation for the source and intermediate range updated electronics The EDCR _____ Source and Intermediate Range, Scope and Intent, Unit Difference and TVA to respond or for Unit 2 Technical Evaluations are contained in Attachment __. provide proposed date of response.

222 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Garg)

Submit updated list for Foxboro Spec 200 [replacement of Bailey and Robert-Shaw electronics The updated listing of Foxboro Spec 200 loop functions is contained in Attachment 34.

223 NRC Garg/Kemper 4-Aug-10 Date: Responder: Clark Date: Responsibility: Closed Submit EDCR Technical Evaluationn for Foxboro I/A replacing obsolete non-safety related Duplicate of item 233.

Foxboro H-Line analog electronics with a digital CDS. [selected single point failures being addressed in design]

224 August 4, 2010 NRC POC: EICB (Marcus) Date: Responder: Norman (TVA CEG) Date: Responsibility: Open Mike Norman [TVA Computer Eng. Group] will check status of DCN/50.59 for Integrated The Data diode to isolate the WBN Unit 1 and Unit 2 ICS computers from the WBN PEDS TVA to respond or Computer System upgrade that will install the data diode between the WBN PEDS and the Unit computers will be installed in PIC 56278 as part of DCN 54971. This DCN is scheduled for provide proposed 1 and Unit 2 ICS. implementation in Spring 2011. This date was included in the Cyber Security Plan date of response.

Implementation Schedules submitted to the NRC on July 23.

225 NRC Garg/Kemper 8/4/2010 Date: Responder: Scansen Date: Responsibility: Open NRC POC: EICB (Garg)

Provide EDCR Technical Evaluation Justify/explain updated hardware [functionally equivalent to The requested information is contained in the Scope and Intent, Unit Difference and Technical TVA to respond or Unit 1] for the RCP and Turbine Generator vibration monitoring equipment. Evaluations for EDCRs 52420 (Attachment __) and 53559 (Attachment __) provide proposed date of response.

226 NRC Garg/Kemper 8/4/2010 Date: Responder: TVA Licensing Date: Responsibility: Closed NRC POC: EICB (Marcus/Carte)

Submit the Foxboro I/A segmentation analysis and ICS Design Criteria documents on an These documents were submitted under TVA letter dated August 11, 2010. NNC 8/25/10: Segmentation analysis has been received and read. See also Open Item Nos. 41 & 270.

expedited separate letter. Provide a date when the Segmentation analysis will be revised based Please describe why a failure or error will not propagate over the -peer-on discussions at the meeting. to-peer network, and cause more than one segment to fail.

227 NRC Garg/Kemper 4-Aug-10 Date: Responder: Clark Date: Responsibility: Open Provide copies of 50.59s for the following Unit 1 changes A. CERPI, initial installation DCN 51072 and 2009 upgrade DCN 52957 (Attachment __) TVA to respond or B. Upgrade of RCP, TG and FW pumps vibration monitoring to Bentley-Nevada 3300, DCN provide proposed

a. CERPI (initial installation and 2009 upgrade) 39242, DCN 39506, DCN 39548, and DCN 50750 (Attachment __) date of response.

b. Vibration monitoring (RCP, TG and FW pumps to Bentley-Nevada 3300) C. Containment Sump Level Transmitter replacement, DCN 39608, (Attachment __)

c. Containment Sump Level Transmitter replacement D. Turbine Servo Control Valve Card replacement, DCN 38993, (Attachment 1)

d. Turbine Servo Control Valve Card replacement E. Pressurizer Heater deletion of Backup Heaters on for PZR High Level, DCN 51102

e. Pressurizer Heater deletion of Backup Heaters on for PZR High Level (Attachment __)

f. AMSAC F. AMSAC DCN 50475 (Attachment __)

g. Significant ESFAS changes G. Significant ESFAS changes

i. Relocate containment isolation valve functions on relays K002 and K626 to prevent plant shutdown during routine surveillance testing. DCN 38238, (Attachment __)

ii. Revise OTT and OPT turbine runback setpoints, DCN 38842 (Attachment __)

iii. Install Integrated Computer System (ICS), DCN 50301 (Attachment __)

228 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Carte/Singh)

Submit rod control system description N3-85-4003 The Rod Control Systemt Desciption N3-85-4003 is contained in Attachment 21. TVA to respond or provide proposed 229 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Carte)

Submit Annunciator system description/design criteria Condition Status/Alarm Design Criteria Document WB-DC-30-21 is contained in Attachment NNC 8/25/10: Document not yet received. TVA to respond or

22. provide proposed date of response.

File: rad4AB2F.xlsx Page 30 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 230 NRC Garg/Kemper 8/4/2010 Date: Responder: Webb Date: Responsibility: Open NRC POC: EICB (Carte)

Submit Foxboro I/A Procurement Specification excerpts that provide system description The requested Foxboro I/A Procurement Specificaition is contained in Attachment 23. NNC 8/25/10: Document not yet received. TVA to respond or information Discuss with Steve Hilmes 1 page description provide proposed date of response.

231 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: FSAR Amd 100 NRC POC: EICB (Garg)

Update FSAR Amendment 100 Section 7.1.1.2 markup based on discussion with Hukam Garg. FSAR section 7.1.1.2 is revised in FSAR Amendment 100 submitted to the NRC on TVA letter to the NRC dated August __, 2010 includes the requested clarifications.

232 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Singh)

Submit EDCR Technical Evaluation for LPMS EDCR The EDCR 52418 Lose Part Monitoring Scope and Intent, Unit Difference and Technical TVA to respond or Evaluations are contained in Attachment 24. provide proposed date of response.

233 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Carte)

Submit EDCR Technical Evaluation for Foxboro I/A EDCR Foxboro I/A EDCRs 52378 and 52671 Scope and Intent, Unit Difference and Technical NNC 8/25/10: Documents received. NRC to review Evaluations are contained in Attachment 25. documents.

234 NRC Garg/Kemper 8/4/2010 Date: Responder: Date: Responsibility: Closed NRC POC: EICB (Carte)

Bechtel to perform D3 analysis for Common Q PAMS which will be incorporated into Duplicate of Item 64 Westinghouse Licensing Technical Report.

235 NRC Garg/Kemper 4-Aug-10 Date: Responder: TVA Licensing Date: Responsibility: Closed TVA to ensure Stewart Bailey is on cc: for all Chapter 7 RAI response letters. Stewart Bailey has been added to the standard response letter template used for Chapter 7 responses.

236 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Garg)

Submit EDCR Technical Evaluation for Foxboro Spec 200 EDCRs Foxboro Spec 200 EDCRs 52343, 52427 and 52641, Scope and Intent, Unit Difference and TVA to respond or Technical Evaluations are contained in Attachment 26. provide proposed date of response.

237 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Carte)

Submit EDCR Technical Evaluation for Annunciator EDCR The Annunciator EDCR 52315 Scope and Intent, Unit Difference and Technical Evaluations NNC 8/25/10: Documents not yet received. TVA to respond or are contained in Attachment 27. provide proposed date of response.

238 NRC Garg/Kemper 8/4/2010 Date: Responder: Webb/Hilmes Date: Responsibility: Closed NRC POC: EICB (Carte)

Discuss with TVA adding a description of the Foxboro I/A system to chapter 7 of the FSAR. Duplicate of item 201 239 NRC Garg/Kemper 8/4/2010 Date: Responder: Hilmes Date: Responsibility: Closed NRC POC: EICB (Carte)

Plan a meeting with TVA the NRC and Westinghouse to review Common Q PAMS meeting held 8/17/10 documentation.

240 NRC Garg/Kemper 8/4/2010 Date: Responder: Clark Date: Responsibility: Open NRC POC: EICB (Garg)

Submit EDCR Technical Evaluation for Vibration Monitoring EDCR(s) The Scope and Intent, Unit Difference and Technical Evaluations for EDCRs 53559 and TVA to respond or 52420 are contained in Attachment 28. provide proposed date of response.

241 NRC Garg/Kemper 8/4/2010 Date: Responder: Davies Date: Responsibility: Open NRC POC: EICB (Sinh)

Review CERPI WCAPs for system description information to be submitted to the NRC. CERPI was designed after Westinghouse stopped using WCAPs. The documents that TVA to respond or provides the most detailed information are the CERPI System Requirements Specification provide proposed WN-DS-00001-WBT Rev. 2. This document is containted in Attachment __. date of response.

242 NRC Garg/Kemper 8/4/2010 Garg Date: Responder: Hilmes Date: Responsibility: Open TVA to make firm decision on date of transfer (before or after initial startup) of Unit 2 loops in The Unit 2 loops in service for Unit that are scheduled to be transferred to the Foxboro Spec TVA to respond or service for Unit 1 to new Foxboro Spec 200 hardware 200 hardware will be transferred prior to Unit 2 fuel load. provide proposed date of response.

243 August 3, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open Section 8.2.1 of the Common Q SPM (ML050350234) states that the System Requirements WEC to address at the 9/15 meeting TVA to respond or Specification (SysRS) includes the system design basis. Section 1.2, "System Scope," of the provide proposed WBN2 PAM SysRS (ML101680578) includes a description of the PAMS design bases that does date of response.

not meet the requirments of IEEE 603-199 Clause 4. Please provide a description of the PAMs design bases that conforms to the requirements of IEEE 603-1991 Clause 4.

244 August 3, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 31 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Section 8.2.2 of the Common Q SPM (ML050350234) states that the Software Requirements WEC agreed to remove process related items from all docs. Close to previous item and TVA to respond or LIC-101 Rev. 3 Appendix B Section 4, Specification (SRS) shall be develped using IEEE 830 and RE 1.172. Clause 4.8, "Embedding revise previous item to include all documents. provide proposed "Safety Evaluation" states: "the project requirements in the SRS," of the IEEE 830 states that an SRS should address the date of response. information relied upon in the SE must software product, not the process of producing the software. In addition Section 4.3.2.1 of the be docketed correspondence."

SPM states "Any alternatives to the SPM processes or additional project specific information for the ...SCMP...shall be specified in the PQP. LIC-101 Rev. 3 states: "The safety analysis that supports the change Contrary to these two statements in the SPM, the WBN2 PAMS SRS (ML101050202) contains requested should include technical many process related requirments, for example all seventeen requirements in Section 2.3.2, information in sufficient detail to enable "Configuration Control," address process requirements for configuration control. the NRC staff to make an independent assessment regarding the acceptability Please explain how the above meets the intent of the approved SPM. of the proposal in terms of regulatory requirements and the protection of public health and safety."

245 August 3, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, Section 5.8 of the Common Q SPM (ML050350234) identifies the required test documentation Relates to the commitment to provide the test plan and the SPM compliance matrix TVA to respond or "Safety Evaluation" states: "the for systems developed using the Common Q SPM. Please provide sufficient information for the provide proposed information relied upon in the SE must NRC staff to independently asssess whether the test plan for WBN2 PAMS, is as described in date of response. be docketed correspondence."

the SPM (e.g., Section 5.8.1).

LIC-101 Rev. 3 states: "The safety 246 August 3, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, Section 4.3.2.1, "Initiation Phase" of the Common Q SPM (ML050350234) requires that a There is a PQP and SPM compliance matrix will be referenced in the Licensing Technical TVA to respond or "Safety Evaluation" states: "the Project Quality Plan (PQP) be developed. Many other section of the SPM identify that this PQP Report. provide proposed information relied upon in the SE must should contain information reuired by ISG6. Please provide the PQP. If "PQP" is not the name date of response. be docketed correspondence."

of the documentation produced, please describe the documentation producted and provide the WEC to identify the elements of the SPM in the compliance matrix information that the SPM states should be in the PQP. LIC-101 Rev. 3 states: "The safety analysis that supports the change requested should include technical 247 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, As part of the Common Q topical report development effort, Westinghouse developed the The documents will be identified in Rev. 1 of the Licensing Technical Report in the TVA to respond or "Safety Evaluation" states: "the Software Program Manual for Common Q Systems (ML050350234) to address software compliance matrix. WEC to make the documents available ASAP in Rockville. May provide proposed information relied upon in the SE must planning documentation. The NRC reviewed the SPM and concluded: the SPM specifies plans require later submittal. date of response. be docketed correspondence."

that will provide a quality software life cycle process, and that these plans commit to documentation of life cycle activities that will permit the staff or others to evaluate the quality of LIC-101 Rev. 3 states: "The safety the design features upon which the safety determination will be based. The staff will review the analysis that supports the change Implementation of the life cycle process and the software life cycle process design outputs for requested should include technical specific applications on a plant-specific basis. Please identify the implementation information in sufficient detail to enable documentation produced as a result of following the SPM, and state what information will be the NRC staff to make an independent docketed. assessment regarding the acceptability of the proposal in terms of regulatory 248 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, As part of the Common Q topical report development effort, Westinghouse developed the The documents will be identified in Rev. 1 of the Licensing Technical Report in the TVA to respond or "Safety Evaluation" states: "the Software Program Manual for Common Q Systems (ML050350234) to address software compliance matrix. WEC to make the documents available ASAP in Rockville. May provide proposed information relied upon in the SE must planning documentation. The NRC reviewed the SPM and concluded: the SPM specifies plans require later submittal. date of response. be docketed correspondence."

that will provide a quality software life cycle process, and that these plans commit to documentation of life cycle activities that will permit the staff or others to evaluate the quality of LIC-101 Rev. 3 states: "The safety the design features upon which the safety determination will be based. The staff will review the analysis that supports the change Implementation of the life cycle process and the software life cycle process design outputs for requested should include technical specific applications on a plant-specific basis. Please identify the design outputs produced as information in sufficient detail to enable a result of following the SPM, and state when what information will be docketed. the NRC staff to make an independent assessment regarding the acceptability of the proposal in terms of regulatory 249 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, The SVVP in the SPM describes the V&V implementation tasks that are to be carried out. The Close to previous items to provide the V&V Reports. TVA to respond or "Safety Evaluation" states: "the acceptance criterion for software V&V implementation is that the tasks in the SVVP have been provide proposed information relied upon in the SE must carried out in their entirety. Documentation should exist that shows that the V&V tasks have date of response. be docketed correspondence."

been successfully accomplished for each life cycle activity group. Please provide information that shows that the V&V tasks havebeen successfully acomplished for each life cycle actifity LIC-101 Rev. 3 states: "The safety group. analysis that supports the change requested should include technical 250 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, The SPM describes the software and documents that will be created and placed under Westinghouse develops Software Release Reports/Records and a Configuration TVA to respond or "Safety Evaluation" states: "the configuration control. The SCMP (e.g., SPM Section 6, Software Configuration Management Management Release Report. Describe the documents and when they will be produced. provide proposed information relied upon in the SE must Plan) describes the implementation tasks that are to be carried out. The acceptance criterion for Sumarize guidance on how to produce these records, focus on project specific date of response. be docketed correspondence."

software CM implementation is that the tasks in the SCMP have been carried out in their requirements in SPM etc.

entirety. Documentation should exist that shows that the configuration management tasks for LIC-101 Rev. 3 states: "The safety that activity group have been successfully accomplished. Please provide information that analysis that supports the change shows that the CM tasks have been successfully accomplished for each life cycle activity group. requested should include technical information in sufficient detail to enable the NRC staff to make an independent 251 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open LIC-101 Rev. 3 Appendix B Section 4, The SPM describes the software testing and documents that will be created. The SPM also Addressed by SPM Compliance matrix in Rev. 1 of the Licensing Technical Report. TVA to respond or "Safety Evaluation" states: "the describes the testing tasks that are to be carried out. The acceptance criterion for software test Norbert is looking for guidance on how to ask for less. provide proposed information relied upon in the SE must implementation is that the tasks in the SPM have been carried out in their entirety. Please date of response. be docketed correspondence."

provide information that shows that testing been successfully accomplished.

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

accomplished.

LIC-101 Rev. 3 states: "The safety File: rad4AB2F.xlsx Page 32 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 253 August 8, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: Open Related to Open Item no. 83.

TVA provided information by letter dated July 30, 2010 (ML102160349) - See Enclosure 1 Item Identify only FPGAs in new or revised modules. If none, provide a revised response. TVA to respond or No. 8 - that some AC160 module contain FPGAs. For those modules that have not been Steve Clark to revise response. provide proposed LIC-110 Rev. 1 Section 6.2.2 states:

previously approved, please provide information to address regulatory criteria for FPGAs. date of response. "Design features and administrative programs that are unique to Unit 2 254 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed WNA-PD-00056-WBT, Rev 1 Watts Bar Unit 2 NSSS Completion I&C Projects date of response.

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 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or The Reusable Software Elements Documents. These contain requirements for the software. provide proposed WNA-DS-01564-GEN, Rev 1. ; WNA-DS-00315-GEN, Rev. 2 ; WNA-DS-01715-GEN, Rev 2 ; date of response.

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 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed The following are documents that contain requirements used in the SRS which we incorporated date of response.

by reference within that document.

Coding Standards and Guidelines for Common Q Systems, 00000-ICE-3889, Rev. 10, Westinghouse Electric Company LLC.

Application Restrictions for Generic Common Q Qualification, WNA-DS-01070-GEN, Rev. 3, Westinghouse Electric Company LLC.

System Requirements Specification for the Common Q Generic Flat Panel Display 00000-ICE-30155, Rev. 9, Westinghouse Electric Company LLC.

Software Requirements Specification for the Common Q Generic Flat Panel Display Software, 00000-ICE-3239, Rev. 12, Westinghouse Electric Company LLC.

Common Q Software Configuration Management Guidelines, NABU-DP-00015-GEN, Rev. 2, Westinghouse Electric Company LLC, Standard General Requirements for Cyber security, WNA-DS-01150-GEN, Rev. 0, Westinghouse Electric Company LLC, 257 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open File: rad4AB2F.xlsx Page 33 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed The following are documents that contain requirements used in the SRS which we incorporated date of response.

by reference within that document.

AC160 CPU Loading Restrictions, AN03007Sp, ABB Memo, ABB Process Automation Corporation, Software Design Description for the Common Q Generic Flat-Panel Display Software, 00000-ICE-30157, Rev. 16, Westinghouse Electric Company LLC.

System Requirements Specification for the Common Q Post Accident Monitoring System, 0000-ICE-30156, Rev. 06, Westinghouse Electric Company LLC.

Software Requirements Specification for the Common Q Post Accident Monitoring System 00000-ICE-3238, Rev. 5, Westinghouse Electric Company LLC.

Commercial Dedication Report for QNX 4.25G for Common Q Applications, WNA-CD-00018-GEN, Rev. 3, Westinghouse Electric Company LLC, Generic Common Q Software Installation Procedure, WNA-IP-00152-GEN, Rev. 7, Westinghouse Electric Company LLC.

258 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed The IV&V Phase Summary Report, (WNA-VR-00283-WBT Rev . 0 ) indicated that the IV&V date of response.

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 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed As they may demonstrate that a number of issues raised by, or that will be raised by, the NRC date of response.

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 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open Please make the following available in Westinghouse's Rockville office. WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or provide proposed The Source level documents for the requirements date of response.

WBT-TVA-0070 Safety Related Digital Logic Cards Circuitry and Related Instrument Racks Restrictions WBT-D-0088 Transmittal Westinghouse comments on TVA specification EDSR 52451 Contract Number 65717 Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2 NSSS Completion Project WEST-WBT-2008-25 TVA Contract Word Authorization 261 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open LIC-110 Rev. 1 Section 6.2.2 states:

Please provide the Requirements Traceability Matrix for generic PAMS and/or any other RTMs WEC to make available in Rockville ASAP. May require later submittal per 9/15 meeting. TVA to respond or "Design features and administrative applicable to WBN2 PAMS. Some requirements in the Software Requirements Specification provide proposed programs that are unique to Unit 2 are simply not present in the Watts Bar 2 PAMS specific RTM (WNA-VR-00279-WBT). date of response. should then be reviewed in accordance with current staff positions" If some requirements in the SRS are not present in any traceability matrix, please indicate how traceability and verifiability are achieved. LIC-101 Rev. 3 Appendix B Section 4, "Safety Evaluation" states: "the 262 August 10, 2010 NRC POC: EICB (Halverson) Date: Responder: WEC Date: Responsibility: Open In order to facilitate visits to the Rockville office, please make the following documents available WEC Reviewing to ensure all documents are available in Rockville office. TVA to respond or at the Rockville office. provide proposed date of response.

Watts Bar 2 PAMS licensing technical report 00000-ICE-37722 Rev. 0 (ML003733136)

Common Q Software Programming manual (ML050350234)

Common Q topical report. (ML031830959)

File: rad4AB2F.xlsx Page 34 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 263 August 11, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open Based on an examination of document available at the Westinghouse Rockville offices (i.e., NA Addressed in 9/20 - 9/21 audit. TVA to respond or 7.4, WEC 7.2, WEC 7.3, CDI-3803, & CDI-3722) a CDI appears to identify the verification provide proposed activities for each critical characteristic. These activities appear to be documented on the date of response.

associated dedication data sheets; therefore, it appears that the Westignhouse Commercial Grade Dedication Plan is called a CDI and the completed CDI data sheets are the commercial grade desication Report. If so, please provide the CDI for each new (not previously approved) component and the associated completed dedication data sheets.

264 August 11, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open Please provide a copy of the commercial grade survey(s) applicable to each new (not previously After the 9/20 - 9/21 audit. TVA to respond or approved) Common Q component. provide proposed date of response.

265 August 11, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open Please provide: After the 9/20 - 9/21 audit. TVA to respond or WNA-CD-00018-GEN Rev. 3 provide proposed 00000-ICE-35444 Rev. 1 date of response.

266 August 11, 2010 NRC POC: EICB (Carte) Date: Responder: Webb/Webber Date: Responsibility: Open Please provide a high level description of the Foxboro IA equipment used at WBN2. This SER Level writeup. Steve Hilmes TVA to respond or description should be more detailed than a brochure on the product line (or available on the provide proposed web), and less detailed than a technical manual on each field replaceable unit. It is expected date of response.

that such literature already exists.

267 August 11, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By letter dated June 18, 2010 (ML101940236) TVA stated that the software safety plan (SSP) References will be removed as appropriate. TVA to respond or was not applicable to PAMS applications (see Watts Bar 2 - Common Q PAMS ISG-6 provide proposed Compliance matrix Item No. 10); however, reference No. 30 of the SRS (ML101050202) is: date of response.

00000-ICE-37727, Rev. 0, "Post Accident Monitoring System Softwarre Preliminary Hazard Analysis for the Common Q PAMS Project." A Preliminary Hazard Analysis is required by the SSP. Please explain.

268 August 19, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By letter dated March 12, 2010 (ML101680577), TVA stated that the application specific Andy to see what can be done. TVA to respond or hardware and software architecture descriptions are addressed in the WBN2 PAMS System provide proposed Design Specification (ML101680579, ML102040481, & ML102040482) and Software date of response.

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 August 20, 2010 NRC POC: DORL (Bailey) Date: Responder: NRC Date: Responsibility: Open DORL to send the Eagle-21 Audit Report to TVA.

270 August 23, 2010 NRC POC: EICB (Carte) Date: Responder: Clark Date: Responsibility: Open See also Open Item Nos. 41 & 226.

By letter dated June 18, 2009 (ML091560352) the NRC informed Westinghouse that WNA-PT- Close to items 41 and 226 Steve Clark to confirm item references and close.

00058-GEN (see pdf page 7 of 25) did not adequately address the test plan criteria of the Software Program Manual (ML050350234); however, by letter dated June 18, 2010 (ML101940236) TVA/Westinghouse stated that WNA-PT-00058-GEN addressed the test plan criteria of the SPM (pdf page 59 of 194, Item No. 12). Please explain.

271 August 23, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Open By letter dated August 20, 2010 TVA dockated a Requirements Traceability Matrix for the 9/15 meeting and 9/20 audit Common Q PAMS (Requirements Phase).This document does not identify the source of each requirement. The Comon Q PAMS System Requirements Specification (SysRS -

ML101680578, ML102040483, & ML102040484) does not explicitly identify the origin of each requirement. The SRP acceptance criteria for requirements specifications is that the origin of the requirements is know. Please explain how to trace each requirement in the SysRS to its origin.

272 August 26, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for Deviations)," (WBNP-96) for Variable 19, "Containment Hydrogem Concentration," Deviation 2 (page 19 of 41), the variable number is listed as 15. The variable number should be listed as 19.

273 August 26, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open In WBN2 FSAR Table 7.5-2, "Regulatory Guide 1.97 Variable List (Deviation and Justification for State samples are taken via the 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.

File: rad4AB2F.xlsx Page 35 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 274 August 26, 2010 NRC POC: EICB (Marcus) Date: Responder: Clark Date: Responsibility: Open 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 August 26, 2010 NRC POC: EICB (Singh) Date: Responder: Clark Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Singh) Date: Responder: Clark Date: Responsibility: Closed 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 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Tindell Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open For FSAR Section 7.6.6, provide the justification for adding valves FCV 63-8 and FCV 63-11, which require that power to be removed and will be administratively controlled prior to use of RHR system for plant cooldown. Provide the P & ID and block diagram showing the operation of these valves.

279 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open For FSAR Section 7.6.6, provide the justification for the addition of protective covers which operator has to remove before he can have access to control switch to operate two additional valves FCV62-98 and FCV62-99.

280 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Open 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 August 27, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: Open File: rad4AB2F.xlsx Page 36 of 45 Tab: Open Items

Prop Open Items No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Follow-up to item 96 This item is a followup question to item On Open Item 96, regarding the implementation of IEN 79-22, part of TVAs response was: 96.

The non-safety-related device/systems within the scope of IEN 79-22 are:

1. Steam generator power operated relief valve control system

2. Pressurizer power operated relief valve control system

3. Main feedwater control system

4. Automatic rod control system.

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

Please identify the sections of FSAR Chapter 15 that address the failures of these systems.

284 August 27, 2010 NRC POC: EICB (Darbali) Date: Responder: Troutman Date: Responsibility: Open Follow-up to item 123 This item is a followup question to item 123 Please provide a readable electrical logic diagram of the Volume Control Tank Level Control System.

285 August 27, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: Open Follow-up to item 22 This item is a followup question 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 August 27, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: Open SE 7.7.3, Volume Control Tank Level Control System In FSAR section 9.3.4.2.4 a change was made to the last paragraph of the Volume Control Tank description (page 9.3-31 of the Amendment 97 redline), where the "low-low level alarm" was changed to "low level alarm".

Please explain if this deletion was an editorial change to correct a typo.

287 August 27, 2010 NRC POC: EICB (Darbali) Date: Responder: Clark Date: Responsibility: Open AMSAC start of AFW pumps in Table 7.3-1??

September 2, 2010 NRC POC: EICB (Garg) Date: Responder: McNeil Date: Responsibility: Open Can we add a section to chapter 7 giving a brief overview of the Foxboro Spec 200 in Section 7.3?

September 2, 2010 NRC POC: EICB (Singh) Date: Responder: Mather Date: Responsibility: Open Provide an ISG4 diversity analysis for the containment high range accident monitors RM-1000.

File: rad4AB2F.xlsx Page 37 of 45 Tab: Open Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 1 19-Nov-09 NRC POC: EICB (Carte) 12/15/2009 Presentation Slides: This item was partially addressed during the December 15, Date: 3/15/2010 Responsibility: NRC Closed November 19, 2010 March 12, 2010 NNC 11/19/09: The FSAR contains The Watts Bar Nuclear Plant FSAR red-line for Unit 2 (Agency wide Documents Access and 2009 meeting. RAI response received. ML093230343 RAI 1 mostly description of the function that Management System Accession Number ML080770366) lists changes to the Unit 1 FSAR and TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 1 on Page 1 of 15): TVA the various TVA systems must perform.

depicts how Chapter 7 of the Unit 2 FSAR will appear at fuel load. Have additional changes been responded to this request for additional Information. Therefore this question was asked to made to Chapter 7 of the Unit 2 FSAR beyond those indicated in ML080770366? Which of the determine how the systems have been changes identified correspond to digital instrumentation and controls (I&C) components and changed.

systems that have not been previously reviewed and approved by the NRC? NNC 4/15/10: The response addresses many systems and should be read by all EICB reviewers.

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

components and systems that have been changed or replaced by digital base technology since responded to this request for additional Information. Therefore this question was asked to Unit 1 was approved? determine how the systems have been changed.

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

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

For planning and scheduling reasons, it is important to know beforehand which platform has been responded to this request for additional Information. Therefore this question was asked to used in each digital component and system. What is the base platform of each unreviewed digital determine how the systems have been I&C component and system (e.g., Common Q)? changed.

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

5 December 11, 2009 (ML093431118, RAI 5) NRC POC: EICB (Garg) Responder: Craig/Webb Date: 3/15/2010 Responsibility: NRC FSAR Amd 100 NNC 4/15/10: Related to (Garg) and TVA setpoints and SE Section 7.1.3.1.

By letter date February 28, 2008 (Agencywide Documents Access and Management System TVA Letter Dated February 5, 2010: TVA provided the Unit 2 setpoint methodology (WCAP- RAI response received. This item is closed (Hilmes and Crouch) as this is covered under (ADAMS) Accession Number ML080770366) TVA provided a "red-lined" version of the FSAR for 177044-P Revision 0 - dated December). item 154 later on.

WBN Unit 2. The purpose of this FSAR "red-line" version was to depict how the Unit 2 FSAR will TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 5 on Page 5 of 15): TVA appear at fuel load. This letter identified significant FSAR changes and provided a X-REF responded to this request for additional Information This item requires futher discussion between TVA and the staff number for each. concening the setpoint methodology employed for WBN2.

This item is addressed as follows:

Change 7.3-1 refers to the following two Summary Reports: See Item 8.

1. FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August TVA Letter, P. L. Pace to NRC, dated February.9, 1998, "Watts Bar Nuclear Plant (WBN) Unit 1 - __, 2010 incorporates as-found and as-left setpoint tolerance discussion into section 10 CFR 50.59(b)(2), Changes, Tests and Experiments Summary Report 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.

TVA Letter, P. L. Pace to NRC, dated September 30, 2005, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59, Changes, Tests and Experiments Summary Report" TSTF-493, Rev. 4 Option A has been incorporated into the Unit 2 Tech Spec submittal 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.

8 December 11, 2009 (ML093431118, RAI 8) NRC POC: EICB (Garg) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 8 on Page 7 of Date: 5/24/10 Responsibility: NRC FSAR Amd 100. TVA stated that they will follow TSTF-15): TVA responded to this request for additional Information (Garg) and TVA Closed as it will be 493 Rev. 4 as approved by the NRC.

(Hilmes/Crouch) covered under item This item is addressed as follows: 154 The TS have already been provided to There are several staff positions that provide guidance on setpoint methodology (e.g., Reg Guide RAI response received. NRC to review response.

the NRC.

1.105, BTP 7-12, RIS-2006-17 and TSTF-493 Rev. 4). Please identify how the Unit 2 setpoint

1. FSAR Amendment 100 which was submitted on TVA letter to the NRC methodology addresses staff guidance. This item requires further discussion between TVA and the staff NNC 4/15/10: Related to setpoints and dated August __, 2010 incorporates as-found and as-left setpoint concerning the applicability of the staff positions to WBN2.

tolerance discussion into section 7.1.2.1.9, adds EEB-TI-28, Setpoint SE Section 7.1.3.1.

Methodology to the section 7.1 references and adds a reference to See Item 5 7.1.2.1.9 to section 7.2.1.1.10. NNC 4/15/10: Hukam, please update this open item as appropriate.

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

9 December 11, 2009 (ML093431118, RAI 9) NRC POC: EICB (Darbali) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 9 on Page 8 of Date: 3/15/2010 Responsibility: NRC Closed NNC 4/15/10: Related SE 15): TVA responded to this request for additional Information (Darbali) Section 7.3.

File: rad4AB2F.xlsx Page 38 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Change 7.3-2, identified in Watts Bar Nuclear Plant FSAR red-line for Unit 2 (ADAMS Accession 50.59 evaluation was submitted in the RAI response. NRC to review.

Number ML080770366), refers to the following Summary Report: TVA Letter, P. L. Pace to NRC, dated September 20, 2002, "Watts Bar Nuclear Plant (WBN) Unit 1 - 10 CFR 50.59, Changes, Tests and Experiments Summary Report" Please provide the 50.59 Evaluation summarized in this Summary Report.

11 December 11, 2009 (ML093431118, RAI 11) NRC POC: EICB (Darbali) TVA Letter Dated March 12, 2010 (Enclosure 1, Item No. 11 on Page 13 Date: 3/15/2010 Responsibility: NRC Closed NNC 4/15/10: Related SE of 15): TVA responded to this request for additional Information (Darbali) Section 7.3.

NUREG-0847 Supplement No. 2 Section 7.3.2 includes an evaluation of a change in containment Requested information was submitted in the RAI response.

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

14 December 22, 2009 (ML093560019, item 1) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed NNC 4/30/10: Related to Eagle (Carte) 21; therefore Garg is responsible.

Provide the justification for any hardware and software changes that have been made since the By letter dated April 27, 2010: TVA responded to this request for information (Enclosure, Item NNC: I do not recall saying that the NRC is not interested in changes previous U.S. Nuclear Regulatory Commission (NRC) staff review for Eagle 21 and other No. 1) stated: "In discussion with the staff, TVA's understanding is that the focus of this in other platforms. Please provide a description of changes to other platforms. question is the Eagle 21 system. Please refer to Reference 2 [TVA Letter Dated March 12, platforms (e.g., SSPS).

2010], Question 10, and TVA letter to NRC dated August 25, 2008, 'Watts Bar Nuclear Plant (WBN) - Unit 2 - Westinghouse Eagle 21 Process Protection System, Response to NRC I&C For Eagle 21, this response points to Open Item No. 10.

Branch request for additional information' (Reference 3 [TVA letter dated August 25, 2008]) for the discussion of changes to the Eagle 21 system." Response understood. Additioanl material will be requested separately to understand the systems described.

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

15 December 22, 2009 (ML093560019, item 2) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Garg)

Verify that the refurbishment of the power range nuclear instrumentation drawers resulted in only By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Response acceptable. Close like-for-like replacements. No. 2).

16 December 22, 2009 (ML093560019, item 3) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Garg)

Identify the precedents in license amendment requests (LARs), if any, for source range monitors or By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Acceptable. Close intermediate range monitors. No. 3).

18 December 22, 2009 (ML093560019, item 5) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Garg)

Identify any changes made to any instrumentation and control (I&C) system based on prior By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Acceptable. Close knowledge of failures. No. 5).

20 December 22, 2009 (ML093560019, item 7) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed NNC 4/30/10: SRP Section 7.0 (EEEB) states: "The organization Provide environmental qualification information pursuant to Section 50.49 of Title 10 of the Code of By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Garg to coordinate with Weibi to ensure EEEB takes responsibility for responsible for the review of Federal Regulations (10 CFR) for safety-related actuation transmitters. No. 7). this one. environmental qualification reviews the environmental qualification of I&C equipment.

The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment."

23 December 22, 2009 (ML093560019, item 10) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 12/22/09 Responsibility: NRC Closed NNC 4/30/10: SRP Section 7.0 (EEEB) states: "The organization File: rad4AB2F.xlsx Page 39 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Provide environmental qualification (10 CFR 50.49) information for safety-related control By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Garg to coordinate with Weibi to ensure EEEB takes responsibility for responsible for the review of transmitters and complete the deviation section of the table. No. 10). this one. environmental qualification reviews the environmental qualification of I&C equipment.

The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment."

26 December 22, 2009 (ML093560019, item 13) NRC POC: EICB (Garg) Date: 4/27/10 Responder: TVA Date: 12/22/09 Responsibility: NRC Closed NNC 4/30/10: SRP Section 7.0 (EEEB) states: "The organization Provide environmental qualification (10 CFR 50.49) information for safety-related monitoring By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Garg to coordinate with Weibi to ensure EEEB takes responsibility for responsible for the review of transmitters. No. 13). this one. environmental qualification reviews the environmental qualification of I&C equipment.

The scope of this review includes the design criteria and qualification testing methods and procedures for I&C equipment."

27 December 22, 2009 (ML093560019, item 14) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Carte)

For Foxboro I/A provide information regarding safety/non-safety-related interaction, common cause By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item failures, and communication with safety related equipment in accordance with ISG 4. No. 14): "There is no digital communications or interactions between Foxboro Intelligent Automation (IA) and any Safety-related system."

29 December 22, 2009 (ML093560019, item 16) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Carte)

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

31 December 22, 2009 (ML093560019, item 18) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed CERPI is non-safety related.

(Carte)

For the rod position indication system (CERPI), provide information in accordance with ISG 4. By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item Response acceptable.

Need to consider cyber-security issues. No. 18).

32 December 22, 2009 (ML093560019, item 19) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed (Carte)

For the process computer, need to consider cyber security issues and emergency response data By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item EICB will no longer consider cyber issues.

system needs. No. 19).

33 December 22, 2009 (ML093560019, item 20) NRC POC: EICB (Carte) Date: 4/27/10 Responder: TVA Date: 4/27/10 Responsibility: NRC Closed The loose parts monitoring system is not (Carte) connected to any other system.

For the loose parts monitoring system, provide information regarding interactions with safety By letter dated April 27, 2010 TVA responded to this request for information (Enclosure, Item TVA stated that there are no interactions.

related equipment. No. 20): Loose parts is not connected to any other system.

36 February 18, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 2/18/2010 Responsibility: TVA Closed FSAR Section 7.5.1, SE Section 7.5.2 Please provide a system description of the Post Accident Monitoring System that contains In previous letters TVA has provided the Common Q documents that address this item:

sufficient detail to support a review of this system using current staff positions. NNC: Unit 2 FSAR Section 7.5.1, Post Accident Monitoring Instrumentation, describes a system design that is unique to Unit 2. LIC-110, "Watts Bar Unit 2 License Application Review," states:

"Design features and administrative programs that are unique to Unit 2 should then be reviewed in accordance with the current staff positions."

39 January 13, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Clark Date: 1/13/2010 Responsibility: TVA The equation for the calculation of the estimated average hot leg temperature File: rad4AB2F.xlsx Page 40 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Please describe the change to the calculation of the estimated average hot leg temperature (see Refer to revised equations in FSAR amendment 98. NRC staff will review. estimated average hot leg temperature FSAR Section 7.2.1.1.4, page 7.2-14 Version WBNP-96) in sufficient detail to support a review of on page 7.2-13 of Revision WBNP-96 of this system using current staff positions. the Unit 2 FSAR is different than the calculation of the average hot leg temperature shown at the top of page 7.2-14 of version WBNP-1 of the UNIT 1 FSAR.

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

42 February 25, 2010: Telecom NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 2/25/2010 Responsibility: TVA Closed The drawing provided did not have the On December 16, 2009: EICB stated to DORL: "I am having trouble reading the drawings in the Attachment 2 provides a drawing cross reference list for FSAR Chapter 7 and electronic TVA provided readable drawings. identification numbers as in the FSAR.

binder that was given to me. Is it possible to produce a set of full size drawing that are in the copies of the fully legible current drawings previously submitted in full size hard copies.

FSAR?"

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

44 February 25, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 2/25/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident The PAMS system described in Section 7.5 of the FSAR is implemented in various manners. TVA By letter Dated June 18, 2010 (see Enclosure 1 Item 6) TVA provided Monitoring Instrumentation - SE Section should identify: information requested. 7.5.2 (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.

45 February 25, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 2/25/2010 Responsibility: TVA Closed For each system implemented using a digital technology, please identify any communications There are no communications betweeen divisions. The response includes the description of TVA provided information by letter dated July 30, 2010 between divisions, or between safety-related equipment and non-safety-related equipment. Please communications and isolation between the Common Q PAMS, Eagle 21 and RM-1000 rad (ML102160349) - See Enclosure 1 Item No. 4.

describe the implementation of the associated communications isolation. monitors and non safety systems.

46 February 25, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 2/25/2010 Responsibility: TVA Closed The Watts Bar Unit 1 Ser (Section 7.2.1, page 7-3) identifies that the RTS includes a trip from the FSAR amendment 98, Section 7.2.2.2, page 7.2-29 second paragraph states:

"general warning alarm". Please identify where this trip is 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."

48 April 8, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: WEC Date: 4/8/10 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Reference 16 of the PAMS System Requirements Specification (SysRS) is the Unit 1 precautions To ensure technical fidelity with the Unit 1 ICCM-86 system, the Unit 1 PLS was used as an Requested information was provided. Monitoring Instrumentation - SE Section Limitations and Setpoints document. When and how will the transition to the unit 2 document be input to the Common Q PAMS System Requirements Specification. This was done to 7.5.2 made. ensure the Unit 2 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.

File: rad4AB2F.xlsx Page 41 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 51 April 15, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Craig/Webb Date: 4/15/10 Responsibility: TVA This item is closed NRC staff has issued RIS 2006-17, to provide guidance to the industry regarding the instrument This item is addressed as follows: This item is to be worked with item 108. as it will be reviewed setpoint methodology which complies with 10CFR50.36 requirements. The staff has requested all under item 154.

the licensees for the existing license to demonstrate how they meet the guidance provided in this 1. FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August __, FSAR Amd 100 RIS. The staff consider WBN 2 as a license amendment for all the setpoints in the TS. Provide 2010 incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9, the information on how WBN 2's setpoint methodology meets the guidance of RIS 2006 -17. You adds EEB-TI-28, Setpoint Methodology to the section 7.1 references and adds a reference to may also consider the guidance provided in TSTF - 493, rev.4 as a basis for meeting the RIS 2006 - 7.1.2.1.9 to section 7.2.1.1.10.

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.

52 April 19, 2010 NRC POC: EICB (Darbali) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Please identify the systems that will use the RM-1000 radiation monitors. As identified in TVA letter dated March 12, 2010, Enclosure 1, item 3 the RM-1000 radiation Monitoring Instrumentation - SE Section monitors are used for the Containment High Range Post Accident Monitors. 7.5.2 53 April 19, 2010 NRC POC: EICB (Darbali) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Please identify all FSAR sections that apply to the RM-1000. The containment high range post accident radiation monitors are discussed in FSAR Monitoring Instrumentation - SE Section amendment 98 sections 7.5 and 12.3. 7.5.2 56 April 19, 2010 NRC POC: EICB (Darbali) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC Closed. Sorrento Radiation Monitoring The "RM-1000 Version 1.2 Software Verification and Validation Report," Document No. 04508006 The initial draft Software Verification and Validation (V&V) report document, version 1.0, was TVA provided the requested Software V&V Report.

Rev. A, is an incremental report. That is to say it addresses the verification an validation for never issued.

changes that resulted in Version 1.2; therefore, the NRC has not received a software verification and validation report for all other aspects of the software. Please provide the last complete Attachment 4 contains the latest complete proprietary version 1.1 Software V&V report verification and validation report, and all incremental reports after the complete report. (04508005). The non-proprietary version and withholding affidavit will be submitted by July 14, 2010. Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 119.

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

58 April 19, 2010 NRC POC: EICB (Darbali) Date: 5/25/10 Responder: Slifer Date: 4/19/10 Responsibility: NRC Closed See FSAR Section 7.5 Instrumentation Please describe all digital communications used in the installed configuration. There are no digital communications between the RM-1000 and any other plant system or Requested information provided. NRC to review. ML101940236, Encl Systems Important To Safety - SE component. 1, Item 13 Section 7.5.0 59 April 19, 2010 NRC POC: EICB (Darbali) Date: Responder: Slifer Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Previously TVA provided the "RM-1000 Digital Radiation Processor Technical Manual," Document (a) The technical manual is applicable to versions 1.1 and 1.2 of the software. Requested information provided. NRC to review. Monitoring Instrumentation - SE Section No. 04508100-1TM Revision C dated October 2003. The "RM-1000 Version 1.2 Software 7.5.2 Verification and Validation Report," Document No. 04508006 Rev. A is dated April 2008. (a) What (b) Version 1.2 was implemented April 1, 2008 software version does the technical manual address? (b) When was Version 1.2 implemented?

60 April 19, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident The PAMS System Requirements Specification (SysRS) references RG 1.97 Rev. 3 where the Duplicate of Item 47 Monitoring Instrumentation - SE Section FSAR References Rev. 2. Please explain. 7.5.2 61 April 19, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section File: rad4AB2F.xlsx Page 42 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments Reference 16 of the PAMS System Requirements Specification (SysRS) is the Unit 1 precautions Duplicate of Item 48. Monitoring Instrumentation - SE Section Limitations and Setpoints document. When and how will the transition to the unit 2 document be 7.5.2 made.

62 April 19, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident Please provide 00000-ICE-30156 Rev. 6. The PAMS SysRS incorporates sections of this Duplicate of Item 49 Monitoring Instrumentation - SE Section document by reference. 7.5.2 63 April 19, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Clark Date: 4/19/10 Responsibility: NRC Closed FSAR Section 7.5.1 Post Accident How should the "shall" statements outside of the bracketed requirements be interpreted? Duplicate of Item 50 Monitoring Instrumentation - SE Section 7.5.2 83 May 6, 2010 NRC POC: EICB (Carte) Date: 6/18/10 Responder: WEC Date: 5/6/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Please identify all FPGAs in the new or changed PAMS hardware. The FPGAs used in the Common Q PAMS AC160 module are listed in Westinghouse letter Monitoring Instrumentation - SE Section WBT-D-2166, (Attachment 5), which provides both the proprietary and non-proprietary 7.5.2 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.

84 May 6, 2010 NRC POC: EICB (Carte) Date: 6/18/10 Responder: Clark Date: 5/6/2010 Responsibility: TVA Closed FSAR Section 7.5.1 Post Accident Monitoring Instrumentation - SE Section Please provide: TVA Design Criteria WB-DC-30-7 Rev. 22, Post Accident Monitoring Attachment 5 contains Design Criteria WB-DC-30-7 Rev. 22, Post Accident Monitoring Document received. 7.5.2 Instrumentation. Instrumentation.

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

88 May 6, 2010 NRC POC: EICB (Darbali) Date: 5/24/10 Responder: Slifer Date: 5/6/2010 Responsibility: TVA Closed. FSAR Section 7.5.1 Post Accident Regarding the Sorrento RM-1000 Digital Radiation Processor: Please provide prior software V&V See response to item 56 Monitoring Instrumentation - SE Section reports. The latest report only addresses Version 1.2. 7.5.2.

91 May 20, 2010 NRC POC: EICB (Darbali) Date: 5/25/10 Responder: Clark Date: Responsibility: Item is Closed and TVA to submit excerpts of EDCRs 52421, 52987, 52321, 52351 and 52601 1. Attachment 6 contains the EDCR 52421 excerpt Two EDCRs have been submitted. TVA has agreed to submit the replaced by items remaining EDCRs. 103, 104 and 118.

2. Attachment 7 contains the EDCR 52987 excerpt

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

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

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

93 May 20, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Knuettel Date: Responsibility: Closed TVA to submit a letter committing to include setpoint methodology discussion in the FSAR no later Letter Sent 5/25/10 than amendment 100.

95 May 20, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: NRC Review TVA to review SER supplements 5 and 14 item 7.8.1 and supplement 4 item 7.8.4 and confirm if Q1: Monitoring of the reactor coolant system relief valve position is the Response is satisfactory. Item closed.

they are identical to Unit 1. If not provide differences. same as Unit 1.

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

97 May 20, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: Closed.

File: rad4AB2F.xlsx Page 43 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments TVA to review SER Supplement 7 item 7.4.25 deviation on Aux Control Room display of RCS cold The deviation to not have RCS cold leg temperature displayed in the Response is satisfactory. Item closed.

leg temperature for applicability to Unit 2. Auxiliary Control Room was approved as part of the WBN Unit 1 initial license. WBN Unit 2 complies with the WBN Unit 1 Llicensing basese and this deviaition is applicable to Unit 2.

98 May 25, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: Closed.

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

this change?

99 April 12, 2010 NRC POC: DORL (Bailey) Date: Responder: WEC Date: Responsibility: Closed Closed to Item 129 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. 1 102 May 24, 2010 NRC POC: EICB (Carte) Date: 5/24/10 Responder: WEC Date: Responsibility: Closed Provide a schedule for resolution of items 80, 82 and 83 Item 80 - no later than July 23, 2010 Item 82 - no later than July 23, 2010 Item 83 - no later than July 23, 2010 105 April 29, 2010 NRC POC: EICB (Garg) Date: Responder: Langley Date: 5/27/10 Responsibility: NRC Closed Provide As-Found/As-Left methodology procedure Submitted copy of TI-28 May 14/2010. Replaced with new open item 176.

106 May 6, 2010 NRC POC: EICB (Carte) Date: 5/25/10 Responder: Davies Date: Responsibility: Closed Confirm that the Unit 1 and Unit 2 CERPI systems utilize the same processor (AC110 or AC160). Westinghouse Unit 2 Drawing 6D31420, Watts Bar 2- CERPI AC160 Chassis Configuration, Rev. 2, shows the processors are model AC160, which are the same that are utilized for Unit 1, as shown on Westinghouse drawing 2D82995 Rev. 0, Watts Bar CERPI AC 160 Chassis Configuration.

107 May 6, 2010 NRC POC: EICB (Darbali) Date: 5/28/10 Responder: Clark Date: Responsibility: NRC Closed See Describe any control functions associated with the RM-1000 radiation monitors. The RM-1000 radiation monitors do not provide any control functions. Requested information provided. NRC to review. ML101940236, Encl 1, Item 29.

108 May 6, 2010 NRC POC: EICB (Garg) Date: 5/25/10 Responder: Webb/Hilmes Date: Responsibility: This item is closed We are requested to docket the fact that the appropriate sections of chapter 7 of the FSAR will be This item is addressed as follows: This item is to be worked with item 51. as it will be reviewed updated to include references to: under item 154.

1. FSAR Amendment 100 which was submitted on TVA letter to the NRC dated August __, FSAR Amd 100

a. TI-28 to address as-found/as-left issues 2010 incorporates as-found and as-left setpoint tolerance discussion into section 7.1.2.1.9,

b. RISC 2006-17 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.

110 May 6, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: TVA Responsibility: Clark Closed The reviewer was unable to locate the Eagle 21 WCAPs 12374 and 12375 for review within the These items were docketed under ML073550386 NRC records. We agreed to provide the ADAMS numbers for the submittal.

111 May 6, 2010 NRC POC: EICB (Carte) Date: 5/28/10 Responder: Clark Date: Responsibility: Closed The reviewer was unable to locate information (SER) on the plant computer or annunciator The annunciator system is not described in the WBN Unit 1 UFSAR. As such it is not included systems and asked us to provide the location within the FSAR where these systems are described. in the WBN Unit 2 FSAR.

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

112 June 1, 2010 NRC POC: EICB (Garg) Date: Responder: Clark Date: Responsibility: Closed File: rad4AB2F.xlsx Page 44 of 45 Tab: Closed Items

Closed Items Agenda for Weekly Telecom with TVA (I&C Chapter 7 only)

Closed Items Resolved for SER Approval Prop No Issue TVA Response(s) Y/N Status/Current Action Resolution Path RAI No. & Date RAI Response Date Comments 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.

119 June 10, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: 7/29/10 Responsibility: NRC Closed Submit the non-proprietary version of Sorrento/GA software V&V report version 1.1 04508005 and Provided 7/15/2010 TVA provided the non-proprietary version of V&V report version 1.1 withholding affidavit 04508005 and the withholding affidavit via TVA letter dated July 15, 2010.

122 June 14, 2010 NRC POC: EICB (Carte) Date: Responder: WEC Date: Responsibility: Closed 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 is considered closed.

Specification.

126 June 14, 2010 NRC POC: EICB (Darbali) Date: Responder: Date: Responsibility: NRC Review SE Section 7.8 NUREG-0737 Items No I&C components or systems are affected by this change. Item closed.

1. In the SER Cross Reference To FSAR table (06-25-09), section 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12) has the following scope of change:

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

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

141 June 17, 2010 NRC POC: EICB (Carte) Date: Responder: Date: Responsibility: Closed WBN2 PAMS System Requirements deleted Specification 155 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Stockton Date: Responsibility: Open FSAR Section 7.2, Reactor Trip System Summary of FSAR change document section 7.2 states that sections 7.2.1.1.9 and 7.2.2.2(4) are The change package summary were the changes recommended by Engineering. TVA Close changed to show that these activities will occur in future. However, no changes were made to the Licensing is responsible for the actual submittal and elected not to incorporate these TVA to provide date FSAR sections. Please explain. recommendations. The activities are complete and the text in Amendment 99 of the FSAR is when information correct. will be docketed.

163 June 25, 2010 NRC POC: EICB (Garg) Date: Responder: Date: Responsibility: Closed FSAR Section 7.2, Reactor Trip System deleted 175 June 28, 2010 NRC POC: EICB (Garg) Date: Responder: Date: Responsibility: Close. This item is Placeholder: The staff has identified questions regarding diversity. The staff will keep this item WCAP-13869 rev.2. is submitted in response to item In FSAR amendment 98, reference 6 added a new WCAP-13869 covered under item open until TVA provides the related WCAP to the staff for its review and approval. rev.2. Has this WCAP been reviewed by the staff. If not then 78.

provide the copy of WCAP for staff review.

TVA to provide date when information will be docketed.

197 Date: Responder: Date: Responsibility: Closed Open Item 197 was never issued.

207 July 27, 2010 NRC POC: EICB (Carte) Date: Responder: Date: Responsibility: Closed deleted File: rad4AB2F.xlsx Page 45 of 45 Tab: Closed Items