ML11224A075
| ML11224A075 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar |
| Issue date: | 08/03/2011 |
| From: | - No Known Affiliation |
| To: | Division of Operating Reactor Licensing |
| References | |
| Download: ML11224A075 (22) | |
Text
1 WBN2Public Resource From:
Boyd, Desiree L [dlboyd@tva.gov]
Sent:
Wednesday, August 03, 2011 11:58 AM To:
Poole, Justin; Milano, Patrick; Campbell, Stephen; Epperson, Dan Cc:
Arent, Gordon; Smith, James D; Bryan, Robert H Jr; Smith, James D; Crouch, William D
Subject:
SSER 23 Open Item Status 8-03-11 R1.docx Attachments:
SSER 23 Open Item Status 8-03-11 R1.docx For todays 3pm telecom.
Thank You,
~*~*~*~*~*~*~*~*~*~*~*~
Désireé L. Boyd WBN 2 Licensing Support Sun Technical Services dlboyd@tva.gov 423-365-8764
Hearing Identifier:
Watts_Bar_2_Operating_LA_Public Email Number:
468 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF21864791)
Subject:
SSER 23 Open Item Status 8-03-11 R1.docx Sent Date:
8/3/2011 11:58:06 AM Received Date:
8/3/2011 11:58:56 AM From:
Boyd, Desiree L Created By:
dlboyd@tva.gov Recipients:
"Arent, Gordon" <garent@tva.gov>
Tracking Status: None "Smith, James D" <jdsmith@tva.gov>
Tracking Status: None "Bryan, Robert H Jr" <rhbryan@tva.gov>
Tracking Status: None "Smith, James D" <smith1jd@westinghouse.com>
Tracking Status: None "Crouch, William D" <wdcrouch@tva.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov>
Tracking Status: None "Campbell, Stephen" <Stephen.Campbell@nrc.gov>
Tracking Status: None "Epperson, Dan" <Dan.Epperson@nrc.gov>
Tracking Status: None Post Office:
TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 259 8/3/2011 11:58:56 AM SSER 23 Open Item Status 8-03-11 R1.docx 71542 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
SSER Status 8/3/2011 1
SSER Item No.
SSER Item Description Disposition TVA Status 1
Review evaluations and corrective actions associated with a power assisted cable pull. (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)
NRR Calculation Review Complete - Addressed by Maximo Commitment Closure package 10181059 2
Conduct appropriate inspection activities to verify cable lengths used in calculations and analysis match as-installed configuration. (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)
For NRC Inspection /
Review Provide NRC Residents access to as-constructed ICRDS database and associated calcs.
Due date:02/29/2012 (Khan)
Note: Pending completion of the cable pull effort and updating ICRDS for as-installed cable lengths by construction.
3 Confirm TVA submitted update to FSAR section 8.3.1.4.1. (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 4
Conduct appropriate inspection activities to verify that TVAs maximum SWBP criteria for signal level and coaxial cables do not exceed the cable manufacturers maximum SWBP criteria. (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)
Closed by IR 2010604 Complete 5
Verify timely submittal of pre-startup core map and perform technical review. (TVA letter dated September 7, 2007, ADAMS Accession No. ML072570676)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 6
Verify implementation of TSTF-449. (TVA letter dated September 7, 2007, ADAMS Accession No. ML072570676)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 7
Verify commitment completion and review electrical design calculations. (TVA letter dated October 9, 1990, ADAMS Accession No. ML073551056)
For NRC Inspection /
Review See commitments in TVA Letter. Provide NRC Residents a copy of related electrical calculation procedures and provide NRC access to calculations Due date: 8/1/11 (Khan) 8 Verify rod control system operability during power ascension. TVA should provide a pre-startup map to the NRC staff indicating the rodded fuel assemblies and a projected end of cycle burnup of each rodded assembly for the initial fuel cycle 6-months prior to fuel load.
(NRC safety evaluation dated May 3, 2010, ADAMS Accession No. ML101200035)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 9
Confirm that education and experience of management and principal supervisory positions down through the shift supervisory level conform to Regulatory Guide 1.8. (Section 13.1.3)
For NRC Inspection /
Review Obtain education and experience information from WBN Human Resources and provide info to NRC Residents.
Due date: 8/8/11 (Crouch)
SSER Status 8/3/2011 2
SSER Item No.
SSER Item Description Disposition TVA Status 10 Confirm that TVA has an adequate number of licensed and non-licensed operators in the training pipeline to support the preoperational test program, fuel loading, and dual unit operation.
(Section 13.1.3)
For NRC Inspection/
Review Provide submittal that confirms we have adequate personnel in the pipeline.
Complete (Wallace) 11 The plant administrative procedures should clearly state that, when the Assistant Shift Engineer assumes his duties as Fire Brigade Leader, his control room duties are temporarily assumed by the Shift Supervisor (Shift Engineer), or by another SRO, if one is available.
The plant administrative procedures should clearly describe this transfer of control room duties. (Section 13.1.3)
For NRC Inspection /
Review Provide NRC Residents copy of procedure that provides the controls of this function.
Due date: 1/26/12 (Wallace) 12 TVAs implementation of NGDC PP-20 and EDCR Appendix J is subject to future NRC audit and inspection. (Section 25.9)
For NRC Inspection /
Review Complete 13 TVA is expected to submit an IST program and specific relief requests for WBN Unit 2 nine months before the projected date of OL issuance. (Section 3.9.6)
To Licensing Provide submittal addressing IST program and relief requests.
Due date: 10/21/11 (Crouch) 14 TVA stated that the Unit 2 PTLR is included in the Unit 2 System Description for the Reactor Coolant System (WBN2-68-4001), which will be revised to reflect required revisions to the PTLR by September 17, 2010. (Section 5.3.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 15 TVA should confirm to the NRC staff the completion of Primary Stress Corrosion Cracking (PWSCC) mitigation activities on the Alloy 600 dissimilar metal butt welds (DMBWs) in the primary loop piping.
(Section 3.6.3)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 16 Based on the uniqueness of EQ, the NRC staff must perform a detailed inspection and evaluation prior to fuel load to determine how the WBN Unit 2 EQ program complies with the requirements of 10 CFR 50.49. (Section 3.11.2)
For NRC Inspection /
Review Provide NRC Residents copies of EQ documents as requested for the onsite inspections.
Due date: Ongoing Inspection (Khan) 17 The NRC staff should verify the accuracy of the WBN Unit 2 EQ list prior to fuel load. (Section 3.11.2.1)
For NRC Inspection /
Review Provide NRC Residents copies of EQ documents as requested for the onsite inspections.
Due date: Ongoing Inspection (Khan) 18 Based on the extensive layup period of equipment within WBN Unit 2, the NRC staff must review, prior to fuel load, the assumptions used by TVA to re-establish a baseline for the qualified life of equipment.
The purpose of the staffs review is to ensure that TVA has addressed the effects of environmental conditions on equipment during the layup period. (Section 3.11.2.2)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete
SSER Status 8/3/2011 3
SSER Item No.
SSER Item Description Disposition TVA Status 19 The NRC staff should complete its review of TVAs EQ Program procedures for WBN Unit 2 prior to fuel load. (Section 3.11.2.2.1)
For NRC Inspection /
Review Provide NRC Residents copies of EQ documents as requested for the onsite inspection Complete - Expect NRC to close in next inspection report 20 Resolve whether or not routine maintenance activities should result in increasing the EQ of the 6.9 kV motors to Category I status in accordance with 10 CFR 50.49. (Section 3.11.2.2.1).
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 21 The NRC staff should confirm that the Electrical Penetration Assemblies (EPAs) are installed in the tested configuration, and that the feedthrough module is manufactured by the same company and is consistent with the EQ test report for the EPA. (Section 3.11.2.2.1)
For NRC Inspection /
Review Complete - Provided NRC Residents (Russ Lewis) copies of EQ documents as requested for the onsite inspection Complete (Khan) 22 TVA must clarify its use of the term equivalent (e.g., identical, similar) regarding the replacement terminal blocks to the NRC staff. If the blocks are similar, then a similarity analysis should be completed and presented to the NRC for review. (Section 3.11.2.2.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 23 Resolve whether or not TVAs reasoning for not upgrading the MSIV solenoid valves to Category I is a sound reason to the contrary, as specified in 10 CFR 50.49(l). (Section 3.11.2.2.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 24 The NRC staff requires supporting documentation from TVA to justify its establishment of a mild environment threshold for total integrated dose of less than 1x103 rads for electronic components such as semiconductors or electronic components containing organic material. (Section 3.11.2.2.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 25 Prior to the issuance of an operating license, TVA is required to provide satisfactory documentation that it has obtained the maximum secondary liability insurance coverage pursuant to 10 CFR 140.11(a)(4), and not less than the amount required by 10 CFR 50.54(w) with respect to property insurance, and the NRC staff has reviewed and approved the documentation. (Section 22.3)
TVA to answer later.
Provide Insurance coverage submittal.
Due date: 10/1/11 (Smith) 26 For the scenario with an accident in one unit and concurrent shutdown of the second unit without offsite power, TVA stated that Unit 2 pre-operational testing will validate the diesel response to sequencing of loads on the Unit 2 emergency diesel generators (EDGs). The NRC staff will evaluate the status of this issue and will update the status of the EDG load response in a future SSER.
(Section 8.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete
SSER Status 8/3/2011 4
SSER Item No.
SSER Item Description Disposition TVA Status 27 TVA should provide a summary of margin studies based on scenarios described in Section 8.1 for CSSTs A, B, C, and D.
(Section 8.2.2)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 28 TVA should provide to the NRC staff a detailed discussion showing that the load tap changer is able to maintain the 6.9 kV bus voltage control band given the normal and post-contingency transmission operating voltage band, bounding voltage drop on the grid, and plant conditions. (Section 8.2.2)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete 29 TVA should provide the transmission system specifics (grid stability analyses) to the NRC staff. In order to verify compliance with GDC 17, the results of the grid stability analyses must indicate that loss of the largest electric supply to the grid, loss of the largest load from the grid, loss of the most critical transmission line, or loss of both units themselves, will not cause grid instability. (Section 8.2.2)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete 30 TVA should confirm that all other safety-related equipment (in addition to the Class 1E motors) will have adequate starting and running voltage at the most limiting safety related components (such as motor operated valves, contactors, solenoid valves or relays) at the degraded voltage relay setpoint dropout setting. TVA should also confirm that the final Technical Specifications are properly derived from these analytical values for the degraded voltage settings.
(Section 8.3.1.2)
Corporate Licensing Provide response for submittal to NRR.
Due date: 8/15/11 (Hilmes)
Note: This issue is with Corporate Licensing to resolve on Unit 1. Unit 2 resolution will be the same as it is for Unit 1.
31 TVA should evaluate the re-sequencing of loads, with time delays involved, in the scenario of a LOCA followed by a delayed LOOP, and ensure that all loads will be sequenced within the time assumed in the accident analysis. (Section 8.3.1.11)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
32 TVA should provide to the NRC staff the details of the administrative limits of EDG voltage and speed range, and the basis for its conclusion that the impact is negligible, and describe how it accounts for the administrative limits in the Technical Specification surveillance requirements for EDG voltage and frequency. (Section 8.3.1.14)
Elec (Hilmes) can get done 7/29/11 Mech (Goines) end of Aug for NPSH eval.
Unit 1 and Unit 2 Tech Spec change needed Provide response for submittal to NRR.
Due date: 8/30/11 (Hilmes)
Note - NRC RII may have an issue with the actual DG loading -
33 TVA stated in Attachment 9 of its letter dated July 31, 2010, that certain design change notices (DCNs) are required or anticipated for completion of WBN Unit 2, and that these DCNs were unverified assumptions used in its analysis of the 125 V dc vital battery system.
Verification of completion of these DCNs to the NRC staff is necessary prior to issuance of the operating license. (Section 8.3.2.3)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
SSER Status 8/3/2011 5
SSER Item No.
SSER Item Description Disposition TVA Status 34 TVA stated that the method of compliance with Phase I guidelines would be substantially similar to the current Unit 1 program and that a new Section 3.12 will be added to the Unit 2 FSAR that will be materially equivalent to Section 3.12 of the current Unit 1 FSAR.
(Section 9.1.4)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
35 TVA should provide information to the NRC staff that the CCS will produce feedwater purity in accordance with BTP MTEB 5-3 or, alternatively, provide justification for producing feedwater purity to another acceptable standard. (Section 10.4.6)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete.
36 TVA should provide information to the NRC staff to enable verification that the SGBS meets the requirements and guidance specified in the SER or provide justification that the SGBS meets other standards that demonstrate conformance to GDC 1 and GDC
- 14. (Section 10.4.8)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
37 The NRC staff will review the combined WBN Unit 1 and 2 Appendix C prior to issuance of the Unit 2 OL to confirm (1) that the proposed Unit 2 changes were incorporated into Appendix C, and (2) that changes made to Appendix C for Unit 1 since Revision 92 and the changes made to the NP-REP since Revision 92 do not affect the bases of the staffs findings in this SER supplement. (Section 13.3.2)
TVA to answer later.
Submit final Unit 1/2 REP to NRC Due date: October 1, 2011 Detchemendy
SSER Status 8/3/2011 6
SSER Item No.
SSER Item Description Disposition TVA Status 38 The NRC staff will confirm the availability and operability of the ERDS for Unit 2 prior to issuance of the Unit 2 OL. (Section 13.3.2.6)
For NRC Inspection /
Review The Emergency Response Data System software has previously been modified and tested for the Watts Bar Unit 2 addition. This unit can be selected from the ERDS menu to send data to the NRC at this time. In addition, the software has been developed and tested to send data from the WBN PEDS to the CECC.
However, the official list of points for Watts Bar Unit 2 has not been provided by Unit 2 Design Engineering and, until this has been completed and submitted to the Computer Engineering Group for addition to the ERDS software, official testing of the software for this unit cannot be completed with the NRC in order to declare the WBN ERDS Unit 2 operational. This list is derived from the official Data Point List. Once developed, Unit 2 Licensing submits the data to the NRC. Once this list has been received by the NRC, it would require one month to add the list to the NRC data systems, write the test, schedule the test with TVA/NRC, run the test, and TVA submit the results.
Due date: 10/1/11 Detchemendy 39 The NRC staff will confirm the adequacy of the communications capability to support dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.6)
For NRC Inspection /
Review Provide NRC Residents copies of related documents as requested for the onsite inspection. This item is covered by the response to Item 38 Due date: See Item 38 Detchemendy 40 The NRC staff will confirm the adequacy of the emergency facilities and equipment to support dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.8)
For NRC Inspection /
Review Perform self assessment to verify processes and materials in main control room, TSC, OSC, EOF and local recivery facility. Provide NRC Residents copies of self assessment documents for the onsite inspection.
Due date: 10/1/11 Detchemendy
SSER Status 8/3/2011 7
SSER Item No.
SSER Item Description Disposition TVA Status 41 TVA committed to (1) update plant data displays as necessary to include Unit 2, and (2) to update dose assessment models to provide capabilities for assessing releases from both WBN units. The NRC staff will confirm the adequacy of these items prior to issuance of the Unit 2 OL. (Section 13.3.2.9)
For NRC Inspection /
Review
Due date: 7/1/12 (Olson)
- 2) Submit EPIP-13. Describe RED, FRED and BRED data systems..
Due date: 10/1/11 Detchemendy 42 The NRC staff will confirm the adequacy of the accident assessment capabilities to support dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.9)
For NRC Inspection /
Review Covered by Item 41 (1)
Due date: 7/12/12 (Olson) 43 Section V of Appendix E to 10 CFR Part 50 requires TVA to submit its detailed implementing procedures for its emergency plan no less than 180 days before the scheduled issuance of an operating license.
Completion of this requirement will be confirmed by the NRC staff prior to the issuance of an operating license. (Section 13.3.2.18)
TVA to answer later.
Submit Unit 1/2 REP implementing procedures (EPIP-1 thru EPIP-17) to NRC Due date: October 1, 2011 (Detchemendy) 44 TVA should provide additional information to clarify how the initial and irradiated RTNDT was determined. (Section 5.3.1)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
45 TVA stated in its response to RAI 5.3.2-2, dated July 31, 2010, that the PTLR would be revised to incorporate the COMS arming temperature. (Section 5.3.2)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
46 The LTOP lift settings were not included in the PTLR, but were provided in TVAs response to RAI 5.3.2-2 in its letter dated July 31, 2010. TVA stated in its RAI response that the PTLR would be revised to incorporate the LTOP lift settings into the PTLR. (Section 5.3.2)
Response provided in TVA to NRC letter dated April 6, 2011.
Complete.
47 The NRC staff noted that TVAs changes to Section 6.2.6 in FSAR Amendment 97, regarding the implementation of Option B of Appendix J, were incomplete, because several statements remained regarding performing water-sealed valve leakage tests as specified in 10 CFR [Part] 50, Appendix J. With the adoption of Option B, the specified testing requirements are no longer applicable; Option A to Appendix J retains these requirements. The NRC discussed this discrepancy with TVA in a telephone conference on September 28, 2010. TVA stated that it would remove the inaccurate reference to Appendix J for specific water testing requirements in a future FSAR amendment. (Section 6.2.6)
Response provided in TVA to NRC letter dated June 7, 2011. However, one FSAR Note was missed.
A105 to correct oversight. FSAR change package prepared
SSER Status 8/3/2011 8
SSER Item No.
SSER Item Description Disposition TVA Status 48 The NRC staff should verify that its conclusions in the review of FSAR Section 15.4.1 do not affect the conclusions of the staff regarding the acceptability of Section 6.5.3. (Section 6.5.3)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete.
49 The NRC staff was unable to determine how TVA linked the training qualification requirements of ANSI N45.2-1971 to TVA Procedure TI-119. Therefore, the implementation of training and qualification for inspectors will be the subject of future NRC staff inspections. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050)
For NRC Inspection /
Review Provided NRC Residents how the refurb training requirements are linked to the ANSI standard.
Provided the training records for refurb inspectors.
Due date: Complete 50 TVA stated that about 5 percent of the anchor bolts for safety-related pipe supports do not have quality control documentation, because the pull tests have not yet been performed. Since the documentation is still under development, the NRC staff will conduct inspections to follow-up on the adequate implementation of this construction refurbishment program requirement. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050)
For NRC Inspection /
Review Notify NRC Residents of anchor bolt pull tests.
Inspection of pull tests ongoing (Gilley) 51 The implementation of TVA Procedure TI-119 will be the subject of NRC follow-up inspection to determine if the construction refurbishment program requirements are being adequately implemented. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050)
For NRC Inspection /
Review Provide NRC Residents the results of the refurb program.
Due date: Ongoing Inspection (Moll) 52[A]
TVA should provide an update to the FSAR replacing Table 12.2-3 with the expected source strength values of the freshly irradiated IITAs. (Section 12.3)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete.
53 TVA should provide an update to the FSAR reflecting the information provided in its letter dated October 4, 2010, regarding the WBN radiation protection design features, including controlled access areas, decontamination areas, and onsite laboratories and counting rooms. (Section 12.4) 54 TVA should provide adequate technical justification to the staff to relax the frequency of the radiation monitor channel quarterly operability tests. TVA should provide sufficient information to the staff to determine that the portable airborne radiation monitors comply with the requirements of 10 CFR 20.1501. TVA should provide sufficient information to the staff to determine that the licensing or TVA program requirements for the calibration and operability testing of area radiation monitors are sufficient to meet the regulatory requirements of 10 CFR 20.1501. (Section 12.4)
On bucket list.
Calculation has been issued and is ready to submit.
Meeting with NRC next week
SSER Status 8/3/2011 9
SSER Item No.
SSER Item Description Disposition TVA Status 55 TVA should provide sufficient information to the staff to demonstrate that the two area radiation monitors for the Spent Fuel Pit comply with the requirements of 10 CFR 70.24 and 10 CFR 50.68 for radiation monitoring in areas where fuel is handled or stored.
(Section 12.4)
TVA to NRC letter submitted July 14, 2011.
A 105 Change package prepared 56 TVA should update the FSAR to reflect the information regarding the dose assessment program provided in its letter the NRC dated June 3, 2010. (Section 12.5) 57 TVA should update the FSAR to reflect the qualification standards of the RPM as provided in its letter to the NRC dated October 4, 2010.
(Section 12.6) 58 The staff has insufficient information to conclude that TVA has taken appropriate actions to reduce radiation levels and increase the capability of operators to control and mitigate the consequences of an accident at WBN Unit 2, in accordance with the guidance of NUREG-0737, Item II.B.2, or can maintain occupational doses to plant operators within the requirements of GDC 19. Therefore, the staff cannot conclude that the plant shielding for WBN Unit 2 is acceptable. (Section 12.7.1)
(I&C Matrix Item 349)
WBNAPS3-126, EQ Dose in the U1/U2 Auxiliary Instrument Rooms and the Computer Room in the Control Building WBNAPS3-127 EQ Dose in the Control Building TVA to review 59[B]
The staff's evaluation of the compatibility of the ESF system materials with containment sprays and core cooling water in the event of a LOCA is incomplete pending resolution of GSI-191 for WBN Unit 2.
(Section 6.1.1.4)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete 60[C]
TVA should amend the FSAR description of the design and operation of the spent fuel pool cooling and cleanup system in FSAR Section 9.1.3 as proposed in its December 21, 2010, letter to the NRC.
(Section 9.1.3)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete 61[D]
TVA should provide information to the NRC staff to demonstrate that PAD 4.0 can conservatively calculate the fuel temperature and other impacted variables, such as stored energy, given the lack of a fuel thermal conductivity degradation model. (Section 4.2.2.1)
Will result in a License Condition.
62[E]
Confirm TVA's change to FSAR Section 10.4.9 to reflect its intention to operate with each CST isolated from the other. (Section 10.4.9)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete 63[F]
TVA should confirm to the NRC staff that testing prior to Unit 2 fuel load has demonstrated that two-way communications is impossible with the Eagle 21 communications interface. (Section 7.2.1.1)
Hot functional testing.
I&C Matrix Item None Complete - This will be addressed by a License Condition (Duplicate of SSER 23 Item 93) 7/1/12
SSER Status 8/3/2011 10 SSER Item No.
SSER Item Description Disposition TVA Status 64[G]
TVA stated that, "Post modification testing will be performed to verify that the design change corrects the Eagle 21, Rack 2 RTD accuracy issue prior to WBN Unit 2 fuel load. This issue is open pending NRC review of the testing results.
For NRC Inspection /
Review I&C Matrix Item None Provide requested info Due Date: FCN date from WEC is 9/16/11 65[H]
TVA should provide justification to the staff regarding why different revisions of WCAP-13869 are referenced in WBN Unit 1 and Unit 2.
(Section 7.2.1.1)
Response provided in TVA to NRC letter dated June 7, 2011.
I&C Matrix Item 323 Complete: Changes are reflected in FSAR Amendment 104.
66[I]
TVA should clarify FSAR Section 9.2.5 to add the capability of the UHS to bring the non accident unit to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
(SRP Section 9.2.5)
TVA to answer later.
A102 provided update to FSAR Section 9.2.2.4 to cover this question for both ERCW and CCS.
Additional Info from 4/13 submittal required Due Date: 8/12/11 (Koontz) 67[J]
TVA should confirm, and the NRC staff should verify, that the component cooling booster pumps for Unit 2 are above PMF level.
(Section 9.2.2)
For NRC Inspection /
Review Provide EDCR closure documentation for installation of CCS thermal barrier booster pump dike. AA FCR issued. Inspect after field complete Due Date:
68[K]
Not Used 69[L]
The WBN Unit 2 RCS vent system is acceptable, pending verification that the RCS vent system is installed. (Section 5.4.5)
For NRC Inspection /
Review Provide EDCR closure documentation for installation of ECCS vents. EDCR numbers 52637 (RHR) [P3 Completion Date 6/7/11], 53311 (SI) [P3 Completion Date 8/25/11] RCS vents not ECCS - need correct DCR #
Due Date: See above 70[M]
TVA should provide the revised WBN Unit 2 PSI program ASME Class 1, 2, and 3 Supports "Summary Tables," to include numbers of components so that the NRC staff can verify that the numbers meet the reference ASME Code. (Section 3.2.3 of Appendix Z of this SSER)
TVA to answer later.
Provide requested info Due Date: 11/1/11 (Tinley) 71[N]
TVA should confirm to the staff the replacement of the current Unit 2 clevis insert bolts to the latest design, which uses an X-750 alloy with an HTH process, rolled threads, and a larger radius on the undercut of the cap screw head. (Section 3.9.5)
Response provided in TVA to NRC letter dated June 7, 2011.
Complete - Did not replace because industry data does not show a need. Need TVA/NRC conference call 72[O]
Based on its review, the staff asked TVA several questions regarding the ICC instrumentation. TVA responded to the staff questions by letter dated October 26, 2010 (ADAMS Accession No. ML103020322). The NRC staff has not completed the review of the additional information provided by TVA. The staff will provide its evaluation after completion of that review. (Section 4.4.8)
Responses provided in multiple TVA to NRC letters.
I&C Matrix Item 041,, 244, 245, 246, 250, 251, 252, 367, 368, 372, 373, and 374 Open pending NRC review
SSER Status 8/3/2011 11 SSER Item No.
SSER Item Description Disposition TVA Status 73[P]
The NRC staff will inspect to confirm that TVA has completed the WBN Unit 2 EOPs prior to fuel load. (Section 7.5.3)
For NRC Inspection /
Review Provide copies of EOPs for inspection.
Due Date: 2/1/12 (Wallace) Check date 74[Q]
The NRC staff will verify installation of the acoustic-monitoring system for the power-operated relief valve (PORV) position indication in WBN Unit 2 before fuel load. (Section 7.8.1)
For NRC Inspection /
Review Provide EDCR closure documentation for installation of acoustic monitors.
Panels installed 5/18/11 Probes not installed Due Date: Need field complete dates 75[R]
The NRC staff will verify that the test procedures and qualification testing for auxiliary feedwater initiation and control and flow indication are completed in WBN Unit 2 before fuel load. (Section 7.8.2)
For NRC Inspection /
Review Provide copies of test procedures for inspection.
Due Date: 7/1/12 (Olson) 76[S]
The NRC staff will verify that the derivative time constant is set to zero in WBN Unit 2 before fuel load. (Section 7.8.3)
For NRC Inspection /
Review I&C Matrix Item None Provide EDCR closure documentation for setting of time constant.
Due Date: 7/1/12 77 It is unclear to the NRC staff which software V&V documents are applicable to the HRCAR monitors. TVA should clarify which software V&V documents are applicable, in order for the staff to complete its evaluation. (Section 7.5.2.3)
Provide requested information I&C Matrix Item None Request sent to GA on 7/18/11 8/30/11 (Hilmes) 78 TVA intends to issue a revised calculation reflecting that the TID in the control room is less than 103 rads, which will be evaluated by the NRC staff. (Section 7.5.2.3)
Provide requested calculation I&C Matrix Item 349 -
Calculation WBNAPS3-127 EQ Dose in the Control Building is ready to submit Complete (Hilmes) 79 TVA should perform a radiated susceptibility survey, after the installation of the hardware but prior to the RM-1000 being placed in service, to establish the need for exclusion distance for the HRCAR monitors while using handheld portable devices (e.g., walkie-talkie) in the control room, as documented in Attachment 23 to TVAs letter dated February 25, 2011, and item number 355 of TVAs letter dated April 15, 2011. (Section 7.5.2.3)
For NRC Inspection /
Review I&C Matrix Item 355 (closed to commitment)
TVA made a commitment to perform the survey and provide results to NRC Owner: R. Brehm 7/1/12 80 TVA should provide clarification to the staff on how TVA Standard Specification SS-E18-14.1 meets the guidance of RG 1.180, and should address any deviations from the guidance of the RG.
(Section 7.5.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 340 - submitted NRC review pending
SSER Status 8/3/2011 12 SSER Item No.
SSER Item Description Disposition TVA Status 81 The extent to which TVAs supplier, General Atomics (GA), complies with EPRI TR-106439 and the methods that GA used for its commercial dedication process should be provided by TVA to the NRC staff for review. (Section 7.5.2.3)
Provide revised Procedure to NRC for review.
I&C Matrix Item 353 NRC comments on GA procedure received 7/11/11 sent to GA for resolution.
Due Date: 9/16/11 82 The staff concluded that the information provided by TVA pertaining to the in-containment LPMS equipment qualification for vibration was incomplete. TVA should provide (item number 362 of ADAMS Accession No. ML111050009), documentation that demonstrates the LPMS in-containment equipment has been qualified to remain functional in its normal operating vibration environment, per RG 1.133, Revision 1. (Section 7.6.1)
Response provided in TVA to NRC letter dated June 10, 2011 I&C Matrix Item 362 Complete - Staff accepted the response and closed the I&C Matrix Item as of 7/11/11.
83 TVA should confirm to the NRC staff the completion of the data storm test on the DCS. (Section 7.7.1.4)
For NRC Inspection /
Review I&C Matrix Item None Provide requested info Owner: Olson 7/1/12 84 TVA should provide additional information for the NRC staff to complete its review of post-LOCA long term cooling boric acid precipitation. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete 85 The 95/95 peak local oxidation was calculated to be 1.04 percent, while core-wide oxidation was calculated to be much less than 0.1 percent. TVA should provide to the NRC staff the value of the decay heat multiplier used for this limiting large break, in order for the staff to complete its evaluation. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete 86 TVA should demonstrate to the staff, in the WCOBRA/TRAC analysis of the limiting break, that the core remains covered with a two-phase mixture and can be cooled for an indefinite period of time. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete 87 In order for the staff to complete its evaluation, TVA should provide (1) a time step sensitivity study for the limiting break displaying downcomer boiling, (2) a list of ten key parameter plots for the worst case downcomer boiling transient, (3) values for the lateral k-factors used in the evaluation, and (4) the manner in which condensation was modeled in the downcomer. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete
SSER Status 8/3/2011 13 SSER Item No.
SSER Item Description Disposition TVA Status 88 It is also unclear to the staff that the entrainment correlation information has been incorporated into the EOP, to ensure that operators do not initiate hot and cold side injection during the period of time that entrainment could preclude injection into the hot legs.
TVA should provide the EOP guidance/instructions for the operators to the staff for review. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete 89 TVA should demonstrate, quantitatively, the applicability of the generic analysis to WBN Unit 2, to demonstrate that the EOP instructions to the operators can effectively deal with the failure of a bottom mounted instrument tube in the lower head. (Section 15.3.1)
Response provided in TVA to NRC Letter dated July 18, 2011.
complete 90 Verify that the ERCW pumps meet GDC 5 requirements for two unit operation. (Section 9.2.1)
No response necessary.
Region II to inspect.
91 TVA should update the FSAR with information describing how WBN Unit 2 meets GDC 5, assuming the worst case single failure and a LOOP, as provided in TVAs letter dated April 13, 2011. (Section 9.2.1)
Mechanical (Koontz)
In A105 Due Date: 8/15/11 92 The NRC staff should perform an inspection in accordance with NRC Temporary Instruction 2515/087, Inspection of Licensees Implementation of Multi-Plant Action A-17: Instrumentation for Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident (Regulatory Guide 1.97). (Section 7.5.2.1.4)
No response necessary.
NRC to determine if open item needed.
93 TVA should confirm to the staff that testing of the Eagle 21 system has sufficiently demonstrated that two-way communication to the ICS is precluded with the described configurations. (Section 7.9.3.2)
TVA to answer later.
I&C Matrix Item None Complete - This will be addressed by a License Condition (Duplicate of SSER 23 Item 63(F)) 7/1/12 94 TVA should provide to the staff either information that demonstrates that the WBN Unit 2 Common Q PAMS meets the applicable requirements in IEEE Std. 603-1991, or justification for why the Common Q PAMS should not meet those requirements. (Section 7.5.2.2.3)
Prepare evaluation to show how Common Q PAMS meets these requirements.
Response provided in TVA to NRC Letter 5/6/11 I&C Matrix Item 364 item 1, 367, 372 Submitted 95 TVA should update FSAR Table 7.1-1, Watts Bar Nuclear Plant NRC Regulatory Guide Conformance, to reference IEEE Std. 603-1991 for the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item: 364 Item 2 Preparing FSAR A105 change package to close.
Complete 96 TVA should (1) update FSAR Table 7.1-1 to include RG 1.100, Revision 3, for the Common Q PAMS, or (2) demonstrate that the Common Q PAMS is in conformance with RG 1.100, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 366 Preparing FSAR A105 change package to close.
Complete
SSER Status 8/3/2011 14 SSER Item No.
SSER Item Description Disposition TVA Status 97 TVA should demonstrate that the WBN Unit 2 Common Q PAMS is in conformance with RG 1.153, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 367 Needs to be in Table 7.1-1 Complete 98 TVA should demonstrate that the WBN Unit 2 Common Q PAMS is in conformance with RG 1.152, Revision 2, or provide justification for not conforming. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 368 Needs to be in Table 7.1-1 Complete 99 TVA should update FSAR Table 7.1-1 to reference IEEE 7-4.3.2-2003 as being applicable to the WBN Unit 2 Common Q PAMS.
(Section 7.5.2.2.3)
Provide response that Common Q PAMS meets these requirements and update FSAR in A105 I&C Matrix Item 369 Preparing FSAR A105 change package to close.
Complete 100 TVA should update FSAR Table 7.1-1 to reference RG 1.168, Revision 1; IEEE 1012-1998; and IEEE 1028-1997 as being applicable to the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 370 Preparing FSAR A105 change package to close.
Complete 101 TVA should demonstrate that the WBN Unit 2 Common Q PAMS application software is in conformance with RG 1.168, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3)
Response provided in TVA to NRC letter dated February 25, 2011 I&C Matrix Item 081 For NRC Inspection / Review 102 TVA should update FSAR Table 7.1-1 to reference RG 1.209 and IEEE Std. 323-2003 as being applicable to the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3)
Provide response that Common Q PAMS meets these requirements and update FSAR in A105 I&C Matrix Item 371 Item 1 Preparing FSAR A105 change package to close.
Complete 103 TVA should demonstrate that the WBN Unit 2 Common Q PAMS conforms to RG 1.209 and IEEE Std. 323-2003, or provide justification for not conforming. (Section 7.5.2.2.3)
Prepare evaluation to show how Common Q PAMS meets these requirements.
I&C Matrix Item 371 Item 2 8/3/11 104 The NRC staff will review the WEC self assessment to verify that it the WBN Unit 2 PAMS is compliant to the V&V requirements in the SPM or that deviations from the requirements are adequately justified. (Section 7.5.2.2.3.4.2)
Response provided in TVA to NRC letter dated June 10, 2011 I&C Matrix Item 041 Self Assessment is available for NRC review at the WEC Rockville Office For NRC Inspection / Review 105 TVA should produce an acceptable description of how the WBN Unit 2 Common Q PAMS SysRS and SRS implement the design basis requirements of IEEE Std. 603-1991 Clause 4. (Section 7.5.2.2.3.4.3.1)
Prepare Response I&C Matrix Item 213 & 372 8/22/11
SSER Status 8/3/2011 15 SSER Item No.
SSER Item Description Disposition TVA Status 106 TVA should produce a final WBN Unit 2 Common Q PAMS SRS that is independently reviewed. (Section 7.5.2.2.3.4.3.1)
Response provided in TVA to NRC letter dated June 10, 2011 I&C Matrix Item 372 item 2 NRC review pending 107 TVA should provide to the NRC staff documentation to confirm that the final WBN Unit 2 Common Q PAMS SDDs that are independently reviewed. (Section 7.5.2.2.3.4.3.2)
Response provided in TVA to NRC letter dated June 10, 2011 I&C Matrix Item 373 NRC review pending 108 TVA should demonstrate to the NRC staff that there are no synergistic effects between temperature and humidity for the Common Q PAMS equipment. (Section 7.5.2.2.3.5.2)
Prepare Response I&C Matrix Item None 8/8/11 109 TVA should demonstrate to the NRC staff acceptable data storm testing of the Common Q PAMS. (Section 7.5.2.2.3.7.1.8)
Response provided in TVA to NRC letter dated June 10, 2011 I&C Matrix Item None NRC review pending 110 TVA should provide information to the NRC staff describing how the WBN Unit 2 Common Q PAMS design supports periodic testing of the RVLIS function. (Section 7.5.2.2.3.9.2.6)
Prepare Response I&C Matrix Item None 8/8/11 111 TVA should provide the technical specifications for the Common Q PAMS to the NRC staff for review. (Section 7.5.2.2.3.11)
Response provided in TVA to NRC letter dated May 6, 2011 I&C Matrix Item 374 TVA1 The audit mentioned on 2/2/22 above, was performed 2/28-3/4/2011 (ML110980761). This audit report documents WBN2 specific and generic actions required to address the conditions identified during the audit.
I&C Matrix Item 043 TVA2 TVA to respond to open items in CQ PAMS SE.
See ML111150287 Section 7.5.2.2.3.4.2.5 on page 24 and Section 7.5.2.2.3.4.3.1 on page 26.
I&C Matrix Item 142, 143, 144, 145, 183, 185 TVA3 NRC to confirm receipt of the following:
The non-proprietary versions of the following RM-1000, Containment High Range Post Accident Radiation Monitor documents will be provided by June 30, 2010.
- 1. V&V Report 04508006A
- 2. System Description 04508100-1TM
- 3. Qualification Reports 04508905-QR, 04508905-1 SP, 04508905-2SP, 04508905-3SP
- 4. Functional Testing Report 04507007-1TR Documents submitted on TVA letter to NRC dated July 15, 2010.
I&C Matrix Item 101 NRC action pending TVA4 6 contains Foxboro proprietary drawings 08F802403-SC-2001 sheets 1 through 6. An affidavit for withholding and non-proprietary versions of the drawings will be submitted by January 31, 2011.
Response in letter dated 11/24/10 I&C Matrix Item 327 NRC Review Pending
SSER Status 8/3/2011 16 SSER Item No.
SSER Item Description Disposition TVA Status TVA5 All safety related work must be quality controlled per 10CFR50, App.
B. TVA to confirm that the procedure used for the RM-1000 system verification tests (04507007) was actually a procedure that was prepared per 10CFR50, App. B. 7.5.2.3 Provide requested response from GA I&C Matrix Item 346 Due Date: TBD TVA6 Was the CERPI system developed under a 10 CFR 50 Appendix B compliant program?
Response in letter dated 4/15/11 I&C Matrix Item 359 NRC Review Pending TVA7 Was the Foxboro IA system developed under a 10 CFR 50 Appendix B compliant program?
Response in letter dated 4/15/11 I&C Matrix Item 361 NRC Review Pending TVA8 OI#199 requested TVA to provide information concerning how TVA plans to meet regulatory criteria for Quality (10 CFR 50.55a(a)(1))
associated with the Technical Support Center and Nuclear Data Link.
TVA responded in Letter Dated October 5, 2010, Item 63; however, TVAs response does not address the quality aspects of these system features. A similar question had been asked for Quality Criteria adherence for the SPDS and the BISI functions of the Integrated Computer System. In response to that request (same letter) TVA provided a description of TVA procedures, BISI software development procedures, and various management measures that will be taken to assure high quality in the design, operation, and maintenance of the SPDS and BISI functions of the ICS. Since the TSC and Nuclear Data Link information originates in the SPDS function of the ICS, are there any aspects of the quality measures that apply to the TSC and NDL features developed as part of quality processes for the ICS that are applicable to the data communications features?
Specifically, what is the scope of TVA Procedure SPP-2.6 Computer Software Control? How does it apply to the ICS functions of a)
SPDS, b) BISI, and c) TSC and NDL functions? Wouldnt there be aspects of the quality procedures that apply to the development, maintenance, and operations of the software needed to support the data communications features. Also, what quality measures will be applied to develop, maintain, and operate the hardware that accomplishes the TSC and NDL functions to ensure that these features will be reliable and available when needed?
Response in letter dated 5/6/11 I&C Matrix Item 363 NRC Review pending
SSER Status 8/3/2011 17 SSER Item No.
SSER Item Description Disposition TVA Status TVA9 On 5/6/2010 (See Open Item No. 81) the NRC Staff requested an evaluation of the Common Q PAMS against the current staff position.
By letter dated 2/25/11 (ML110620219), TVA docketed a response:
that WBN2 is not committed in complying with Reg. Guide 1.75Since WBN2 is not committed to RG 1.75 or IEEE-384, no comparison is required However, WBN2 is committed to RG 1.75 Rev. 2, Physical Independence of Electric Systems. RG 1.75 Rev. 3 and IEEE Std. 384-1992 are used, in part, to address IEEE Std 603-1991 Clause 5.6.1. The current NRC staff position for RG 1.75 is documented in Rev. 3. Based upon the review of this item, the staff finds the following open item:
1 TVA to updated FSAR (Amendment 103) Table 7.1-1 to include RG 1.75 Rev. 3 for WBN2 Common Q PAMS and the Sorrento Containment High Radiation monitor.
The Common Q PAMS was designed to meet the requirements of RG 1.75 Rev. 2. WBN2 did not perform an analysis to RG 1.75 Rev.
- 3. Based upon the review of this item, the staff finds the following open item:
2 TVA to evaluate Common Q PAMS and the Sorrento Containment High Radiation monitor for conformance with RG 1.75 Rev. 3.
Submit FSAR amendment to reflect changes Response submitted in letter dated 5/16/11 I&C Matrix Item 365 Pending A105 submittal.
SSER Status 8/3/2011 18 SSER Item No.
SSER Item Description Disposition TVA Status TVA10 ReferenceEDCR # 52321, Revision AEDCR Unit Difference Form --- Bechtel Document Page 2 -Maintenance Difference The proposed In-Core Instrument Thimble Assemblies (IITAs) which will replace Movable In-Core Detectable Systems (MIDs) have the following features:
(1) IITAs are not fully extracted and they are held in a movable frame assembly.
(2) IITAs exert lower vibration amplitude and therefore, aging degradation due to wear does not occur.
(3) Loss of reactor coolant system pressure boundary due to breach of IITA outer sheath does not occur.
Question:
The staff believes that the licensee should provide an inspection program to confirm that the aforementioned attributes associated with IITAs are valid and this inspection program can be a part of a routine maintenance program.
Replacement of 58 CETs for the current 65 CETs -to be addressed by the fuels division.
Response submitted 6/13/11 I&C Matrix Item 376 NRC Review pending TVA11 Non-Proprietary description of the qualification of the MI cable assemblies with references to any EQ report (if applicable) - June 10th Response submitted 6/13/11 I&C Matrix Item 381 NRC Review pending TVA12 Non-Proprietary description of the qualification of the IITA with references to EQ report(s)
NRC Update (Alvarado) - need the proprietary versions of reports, such as EQ tests, EMI/RFI tests, calculations, and other documents to make a safety determination, not non-proprietary reports that reference these reports and calculations.
NRC update (RA) 6/16: The report will be available after June 30.
This is still an open item I&C Matrix Item 383
SSER Status 8/3/2011 19 SSER Item No.
SSER Item Description Disposition TVA Status TVA13 Provide the following documents, which describe operation of the WINCISE Application Server.
Sections 1 and 2 of the WNA-GO-00075-WBT, WINCISE Signal Processing System Cabinet Operation & Maintenance Manual. Revision 0.
WNA-DS-01811-WBT, WINCISE Signal Processing System Design Requirements. Revision 0, May 2010 420A90, WINCISE Functional Specification for Watts Bar Unit 2. Revision 2.
I&C Matrix Item 388 TVA14 Provide the proprietary version of the calculation described in WNA-CN-00157-WBT, Watts Bar 2 IIS Signal Processing System Isolation Requirements. Revision 0.
I&C Matrix Item 389 TVA15 Westinghouse has indicated that the WINCISE Application Servers, as well as the BEACON are redundant. However, the WINCISE Application Server communicates only with Beacon A. Westinghouse also explained that to switch from Beacon A to Beacon B, the operator must perform this manually. After reviewing Westinghouse documents, we couldnt find explanation that automatic switchover to the other server is not permitted.
I&C Matrix Item 390 TVA16 Clarify the type of connector used with the MI cable in Unit 2. During this review, we identified the following connectors, but we could not establish which one will be used in unit 2. Also explain if the qualification performed is still valid or if it is going to be revised.
o Whittaker connectors o
Litton connectors o
Electronic Resources Division (ERD) connectors I&C Matrix Item 391 TVA17 Clarify the logic to subtract failed detectors from the algorithm used to calculate core power. During the May 12 meeting with Westinghouse and TVA, Westinghouse explained that the WINCISE Application Server includes an algorithm to subtract failed detectors. However, during our review in Westinghouse office, we could not find description on how this algorithm is accomplished. Furthermore, the document BEACON Data Processing Application Program Software Requirements Specification includes the following assumption: BEACON will perform the subtraction between various length elements for the vanadium detector design. This is appropriate, as BEACON is more equipped to support the replacement value algorithm should an element fail. BEACON has knowledge of the flux shape which is critical to this process.
I&C Matrix Item 392
SSER Status 8/3/2011 20 SSER Item No.
SSER Item Description Disposition TVA Status TVA18 Clarify if the IITA assembly and the 6-to-1 transition cable have been subjected to the 600VDC dielectric strength test. Document Watts Bar 2 IIS Signal Processing System Isolation Requirements states that the MI and IITA assemblies need to be subjected to a 600VDC dielectric strength test. Letter LTR-ME-10-3 summarizes the result for the MI cable. However, similar documentation was not available for the IITA assembly.
I&C Matrix Item 393 TVA19 Confirm that power supply cables to the WINCISE SPS cabinet are not routed with cables that are greater than 264V.
I&C Matrix Item 394 TVA20 Confirm that power supply to the WINCISE SPS cabinet are from isolated 1E sources, such that power supply routed to PAMS train A is the same routed to SPS cabinet 1, and power supply routed to PAMS train B is the same routed to SPS cabinet 2.
I&C Matrix Item 395 TVA21 Provide proprietary, non-proprietary versions and affidavits for withholding for the following documents:
General Atomics Electronic Systems 04038903-1SP, Qualification Basis for 04031101-001 (2-RE-90-130 &131).
General Atomics Electron Systems 04038903-2SP, Qualification Basis for 04031301-001 (2_RE-90-106).
General Atomics Electronic Systems 04038903-4SP, Qualification Basis for 04031501-001 (2-RE-90-112).
I&C Matrix Item 396