ML11213A133
| ML11213A133 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 07/27/2011 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11213A133 (31) | |
Text
Enclosure 4 Generic Communications - Revision 6 Changes
GENERIC COMMUNICATIONS: REVISION 6 CHANGES ITEM TITLE REV ADDITIONAL INFORMATION B 74-003 Failure of Structural or Seismic Cl TVA: memo dated January 22, 1985 Support Bolts on Class I _ -.
Components 06 NRC: IR 390/391 85-08 Approach accepted in IR50-390/85-08 and 50-391/85-08 (March 29, 1985).
Unit 2 Action: Implement per NUREG-0577 as was done for Unit 1.
REVISION 06 UPDATE:
Corrective action for this item consisted of a bolting reheat treatment program for both units; it has been completed.
B 74-015 Misapplication of Cutler-Hammer C TVA: letter dated May 5, 1975 Three Position Maintained Switch _ -.
Model No. 10250T 06 NRC: IR 390/391 75-5 Unit 2 Action: Install modified A3 Cutler-Hammer 10250T switches.
REVISION 06 UPDATE:
It has been confirmed that WBN Unit 2 never had the faulty switches.
NRC Inspection Report 391/2010-605 closed B 74-015.
B 75-006 Defective Westinghouse Type OT- CI TVA: letter dated July 31, 1975 2 Control Switches 06 NRC: IR390/85-25 and 391/85-20 Unit 2 Action: Inspect Westinghouse Type OT-2 control switches.
[WAS "NOTE 3.1 REVISION 06 UPDATE:
All Unit 2 Type OT-2 switches procured or refurbished are inspected and tested.
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R REV ITEM TITLE ADDITIONAL INFORMATION B 79-009 Failure of GE Type AK-2 Circuit CI TVA: letter dated June 20, 1979 Breaker in Safety Related Systems 06 Unit 2 Action:
Complete preservice preventive maintenance on AK-2 Circuit Breakers.
[WAS "NOTE 3."]
REVISION 06 UPDATE:
It has been confirmed that AK-2 Circuit Breakers are not used on Unit 2.
B 79-021 Temperature Effects on Level C Reviewed in 7.2.5 of both the original 1982 SER and SSER14.
Measurements 06 Unit 2 Action: Update accident calculation.
CONFIRMATORY ISSUE - address IEB 79-21 to alleviate temperature dependence problem associated with measuring SG water level In SSER14, NRC concurred with TVA's assessment to not insulate the.
steam generator water level instrument reference leg.
Unit 2 Action: Update accident calculation.
REVISION 06 UPDATE:
The calculations were updated.
NRC Inspection Report 391/2010-605 closed B 79-021.
B 80-004 Analysis of a PWR Main Steam CI IR 50-390/85-60 and 50-391/85-49 (December 6, 1985) required Line Break with Continued completion of actions that included determination of temperature profiles Feedwater Addition 06 inside and outside of containment following a MSLB for Unit 1.
Unit 2 Action: Complete analysis for Unit 2.
REVISION 06 UPDATE:
The an alysis for Unit 2 was completed.
B 80-010 Contamination of Nonradioactive CI Unit 2 Actions: 1) Correct deficiencies involving monitoring of systems.
System and Resulting Potential for - -.
Unmonitored, Uncontrolled 06 Release of Radioactivity to ----------------------------------------------------------------------------------------------------
Environment REVISION 06 UPDATE:
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ITEM TITLE REV ADDITIONAL INFORMATION Chemistry procedure CM-3.01 (System Chemistry Specification) includes a radiation monitoring system for non-radioactive systems and provides appropriate surveillance limits. Additionally, it provides required actions if the surveillance limits are not met.
B 80-010 Contamination of Nonradioactive Cl. Unit 2 Actions:
System and Resulting Potential for Unmonitored, Uncontrolled 06 2) Include proper monitoring of non-radioactive systems in procedures.
Release of Radioactivity to Environment REVISION 06 UPDATE:*
Chemistry procedure CM-3.0! (System Chemistry Specification) includes a radiation monitoring system for non-radioactive systems and provides appropriate surveillance limits. Additionally, it provides required actions if the surveillance limits are not met.
B 80-018 Maintenance of Adequate CO IR 50-390/85-60 and 50-391/85-49 (Unit 1)
Minimum Flow Thru Centrifugal Charging Pumps Following 06 Unit 2 Action: Implement design and procedure changes.
Secondary Side High Energy Rupture REVISION 06 UPDATE:
NRC Inspection Report 391/2011-604 closed B 80-018.
B 80-020 Failure of Westinghouse Type CI Unit 2 Action: Modify switches.
W-2 Spring Return to Neutral Control Switches 06 -------------------------------------------------------------
REVISION 06 UPDATE:
The switches were modified.
NRC Inspection Report 391/2011-604 closed B 80-020.
B 80-024 Prevention of Damage Due to CI UnitS2IAction:
Water Leakage Inside Containment (10/17/80 Indian 06 Confirm that the reactor cavity can not be flooded, resulting in the partial or-Point 2 Event) total submergence of the reactor vessel unnoticed by the reactor - -- - -
- -operators..
rs. - -- - -
o pe rato REVISION 06 UPDATE:
It was confirmed that the reactor cavity can not be flooded,, resulting in the partialI or total submergence of the reactor vessel unnoticed by the reactor operators.
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ITEM TITLE REV ADDITIONAL IINFORMATION B 82-002 Degradation of Threaded CI TVA: memo dated February 6, 1985 Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants 06 NRC: IR390/391 85-08 Approach accepted in IR 50-390/85-08 and 50-391/85-08 (March 29, 1985).
Unit 2 Action: Implement same approach as Unit 1.
REVISION 06 UPDATE:
The boric acid corrosion program applies to both units.
B 83-004 Failure of the Undervoltage Trip C NRC: IR 390/391 85-08 Function of Reactor Trip Breakers - -.
06 Unit 2 Action:
Install new undervoltage attachment with wider grooves on the reactor trip breakers.
REVISION 06 UPDATE:
New breakers have been installed on Unit 2.
NRC Inspection Report 391/2011-602 closed B 83-004.
B 85-002 Undervoltage Trip Attachment of C Unit 2 Action:
Westinghouse DB-50 Type _ -.
Reactor Trip Breakers 06 Install automatic shunt trip on the Westinghouse DS-416 reactor trip breakers on Unit 2.
REVISION 06 UPDATE:
New breakers (including an automatic shunt trip) have been installed on Unit 2.
NRC Inspection Report 391/2011-602 closed B 85-002.
B 88-009 Thimble Tube Thinning in Cl Reviewed in Appendix EE of SSER16.
Westinghouse Reactors 06 Unit 2 Action:
TVA letter dated March 11, 1994, for both units committed to establish a program and inspect the thimble tubes during the first refueling outage.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 06 UPDATE:
Unit 2 is installing the Westinghouse In-core, Information, Surveillance, and Engineering (WINCISE) system. Westinghouse has analyzed WINCISE to exhibit essentially no wear due to vibrations, and should there be a breach of the thimble tube there would not be a loss of into the seal table room, Therefore, the thimble tubes for WINCISE do not need eddy current testing.
B 89-001 Failure of Westinghouse Steam C NRC acceptance letter dated September 26, 1991 for both units.
Generator Tube Mechanical Plugs _ -.
06 Unit 2 Action: Remove SG tube plugs.
REVISION 06 UPDATE:
The SG tube plugs were removed.
NRC Inspection Report 391/2011-602 closed B 89-001.
B 89-002 Stress Corrosion Cracking of Cl NRC reviewed in Appendix EE of SSER16.
High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in 06 Unit 2 Actions:
Anchor Darling Model S350W Swing Check Valves or Valves of " Replace the flapper assembly hold-down bolts fabricated on the 14 Similar Nature (12 valves are installed) Atwood and Morrell Mark No. 47W450-53 check valves.
" Replacement bolts are to be fabricated from ASTM F593 Alloy 630.
- A review of the remaining Unit 2 safety related swing check valves will be performed.
REVISION 06 UPDATE:
- Bolts fabricated from ASTM F593 Alloy 630 have been procured.
- The review of the remaining Unit 2 safety related swing check valves was completed. Needed corrective actions were initiated.
B 90-001 Loss of Fill-Oil in Transmitters CO Unit 2 Action:
Manufactured by Rosemount 06 Implement applicable recommendations from this Bulletin including identification of potentially defective transmitters and an enhanced surveillance program which monitors transmitters for loss of fill oil.
REVISION 06 UPDATE:
NRC Inspection Report 391/2011-603 closed B 90-001.
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ITEM TITLE REV ADDITIONAL INFORMATION B 96-001, Control Rod Insertion Problems CI NRC acceptance letter for Unit 1 dated July 22, 1996 - Initial response last part (PWR) _ -. for Unit 2 on September 7, 2007.
06 Unit 2 Action: and provide core map.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation (corrected) for Bulletin 1996-001 on May 3, 2010.
REVISION 04 UPDATE:
Corrected status from "OV" to "Cl" due to NRC issuance of Safety Evaluation as noted in Revision 03 update.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC letter dated May 3, 2010 (ADAMS Accession No. ML101200035) required Confirmatory Action (See Appendix HH)"
The applicable item from SER22, Appendix HH for this item is Open Item 5, "Verify timely submittal of pre-startup core map and perform technical review. (TVA letter dated September 7, 2007, ADAMS Accession No. ML072570676)."
TVA to NRC letter dated April 6, 2011 provided the following response to Open Item 5:
"Attachment 1 provides the requested core map."
B 96-002 Movement of Heavy Loads over CI NRC closure letter dated May 20, 1998.
Spent Fuel, Over Fuel in the Reactor, or Over Safety-Related 06 Unit 2 Action:
Equipment Unit 2 Heavy Loads Program will be in compliance with NUREG-0612.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Bulletin 1996-002 on March 4, 2010.
REVISION 06 UPDATE:
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ITEM TITLE REV ADDITIONAL INFORMATION SSER22 contained the following for NRC Action:
"Closed. NRC letter dated March 4, 2010 (ADAMS Accession No. ML100480062)"
B 01-001 Circumferential Cracking of C NRC acceptance letter dated November 20, 2001 (Unit 1) - Initial Reactor Pressure Vessel (RPV) - response for Unit 2 on September 7, 2007.
Head Penetration Nozzles 06 Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
Unit 2 Actions:
Perform baseline inspection.
- Evaluate or repair as necessary.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation for Bulletin 2001-001 on June 30, 2010.
REVISION 04 UPDATE:
Corrected status from "OV" to "Cl" due to NRC issuance of Safety Evaluation as noted in Revision 03 update.
REVISION 06 UPDATE:
The baseline inspection was performed with evaluations and repairs as necessary.
SSER22 contained the following for NRC Action:
"Closed. See NRC Letter dated June 30, 2010 (ADAMS Accession No. ML100539515)"
NRC Inspection Report 391/2011-602 closed B 01-001.
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ITEM TITLE REV ADDITIONAL INFORMATION B 02-001 RPV Head Degradation and C NRC review of Unit i's 15 day response in letter dated May 20, 2002 -
Reactor Coolant Pressure _-_. Initial response for Unit 2 on September 7, 2007.
Boundary Integrity 06 Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
Unit 2 Actions:
- Perform baseline inspection.
- Evaluate or repair as necessary.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation for Bulletin 2002-001 on June 30, 2010.
REVISION 04 UPDATE:
Corrected status from "OV" to "CI" due to NRC issuance of Safety Evaluation as noted in Revision 03 update.
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REVISION 06 UPDATE:
The baseline inspection was performed with evaluations and repairs as necessary.
SSSER22 contained the following for NRC Action:
"Closed. See NRC Letter dated June 30, 2010 (ADAMS Accession No. ML100539515)"
NRC Inspection Report 391/2011-602 closed B 02-001.
B 02-002 RPV Head and Vessel Head C NRC acceptance letter dated December 20, 2002 (Unit 1) - Initial Penetration Nozzle Inspection - -. response for Unit 2 on September 7, 2007.
Programs 06 Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
Unit 2 Actions:
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ITEM TITLE REV ADDITIONAL INFORMATION
- Perform baseline inspection.
- Evaluate or repair as necessary.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation for Bulletin 2002-002 on June 30, 2010.
REVISION 04 UPDATE:
Corrected status from "OV" to "Cl" due to NRC issuance of Safety Evaluation as noted in Revision 03 update.
REVISION 06 UPDATE:
The baseline inspection was performed with evaluations and repairs as necessary.
SSSER22 contained the following for NRC Action:
"Closed. See NRC Letter dated June 30, 2010 (ADAMS Accession No. ML100539515)"
NRC Inspection Report 391/2011-602 closed B 02-002.
B 03-002 Leakage from RPV Lower Head CI NRC acceptance letter dated October 6, 2004 (Unit 1) - Initial response Penetrations and Reactor Coolant --. for Unit 2 on September 7, 2007.
Pressure Boundary Integrity 06 (PWRs) Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Bulletin 2003-002 on January 21, 2010.
Unit 2 Actions:
- Perform baseline inspection.
- Evaluate or repair as necessary.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061)"
B 04-001 Inspection of Alloy 82/182/600 CI Initial response for Unit 2 on September 7, 2007.
Materials Used in the Fabrication of Pressurizer Penetrations and 06 Unit 2 Actions:
Steam Space Piping Connections at PWRs
- Provide details of pressurizer and penetrations, and
. apply Material Stress Improvement Process.
REVISION 02 UPDATE:
TVA provided details of the pressurizer and penetrations on September 29, 2008. This letter committed to:
Prior to placing the pressurizer in service, TVA will apply the Material Stress Improvement Process (MSIP) to the Pressurizer Power Operated Relief Valve connections, the safety relief valve connections, the spray line nozzle and surge line nozzle connections.
TVA will perform a bare metal visual (BMV) inspection of the upper pressurizer Alloy 600 locations at the first refueling outage.
REVISION 03 UPDATE:
April 1, 2010, letter committed to:
TVA will perform NDE prior to and after performance of the MSIP. If circumferential cracking is observed in either pressure boundary or non-pressure boundary portions of any locations covered under the scope of the bulletin, TVA will develop plans to perform an adequate extent-of-condition evaluation, and TVA will discuss those plans with cognizant NRC technical staff prior to starting Unit 2.
After performing the BMV inspection during the first refueling outage,. ifany evidence of apparent reactor coolant pressure boundary leakage is discovered, then NDE capable of determining crack orientation will be performed in order to accurately characterize the flaw, the orientation, and extent. TVA will develop plans to perform an adequate extent of condition evaluation, and plans to possibly expand the scope of NDE to other components in the pressurizer will be discussed with NRC technical staff prior to restarting of Unit 2.
REVISION 04 UPDATE:
NRC issued the Safety Evaluation for Bulletin 2004-001 on August 4, 2010.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated August 4, 2010 (ADAMS Accession No. ML102080017)"
B 07-001 Security Officer Attentiveness C Item concerns a multi-unit issue that was completed for both units.
REVISION 05 UPDATE:
The NRC closed this bulletin via letter dated March 25, 2010 (ADAMS Accession No. ML100770549).
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated March 25, 2010 (ADAMS Accession No. ML100770549)"
GL 82-028 Inadequate Core Cooling CO LICENSE CONDITION - Detectors for Inadequate core cooling (II.F.2)
Instrumentation System - -.
06 In the original SER, the review of the ICC instrumentation was incomplete.
The January 24, 1992, letter superseded the previous responses on this issue. TVA letter for Units 1 and 2 dated January 24, 1992, committed to install Westinghouse ICCM-86 and associated hardware. NRC completed the review for Units 1 and 2 in SSER10. For Unit 2 due to obsolescence of the ICCM-86 system, TVA intends to install the Westinghouse Common Q Post-Accident Monitoring System.
Unit 2 Action: Install Westinghouse Common Q PAM system.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. Subsumed as part of NRC staff review of Instrumentation and Controls submitted April 8, 2010."
GL 83-028 "Required Actions Based on Cl TVA: letters dated November 7, 1983 and August 24, 1990 Generic Implications of Salem - -.
ATWS Events: 06 NRC: letters dated October 20, 1986 and June 18, 1990 2.1 - Equipment Classification and Vendor Interface (Reactor Trip Unit 2 Action:
System Components)
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REV ITEM TITLE ADDITIONAL INFORMATION Ensure that required information on Critical Structures and Components is properly incorporated into procedures.
[WAS "NOTE 3."]
REVISION 06 UPDATE:
Confirmed that required information on Critical Structures and Components is properly incorporated into procedures.
GL 83-028 "Required Actions Based on S TVA: letters dated November 7, 1983, January 17, 1986 and Generic Implications of Salem November 1, 1993 ATWS Events: 06 NRC: letters dated December 10, 1985, October 27, 1986, and 3.2 - Post-Maintenance Testing July 2, 1990; IR 390, 391/86-04 (All SR Components)
Unit 2 Action:
Test and maintenance procedures and Technical Specifications will include post-maintenance operability testing of other (than reactor trip system) safety-related components.
REVISION 02 UPDATE:
Developmental Revision A of the Unit 2 TS (including the TS Bases) was submitted on March 4, 2009.
The Bases for TS Surveillance Requirement 3.0.1 states, in part, "Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2."
REVISION 06 UPDATE:
Watts Bar's Preventative Maintenance Program is not unit specific; no further action is required for Unit 2.
GL 83-028 "Required Actions Based on CO TVA: letter dated May 19, 1986 Generic Implications of Salem ATWS Events: 06 4.1 - Reactor Trip System Unit 2 Action:
Reliability (Vendor Related Confirm vendor-recommended DS416 breaker modifications are Modifications) implemented.
REVISION 06 UPDATE:
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ITEM TITLE REV ADDITIONAL INFORMATION NRC Inspection Report 391/2011-602 closed GL 83-028, Item 4.1.
GL 88-005 Boric Acid Corrosion of Carbon CI NRC acceptance letter dated August 8, 1990 for both units.
Steel Reactor Pressure Boundary Components in PWR plants 06 Unit 2 Action: Implement program.
REVISION 06 UPDATE:
The program has been implemented on Unit 2.
GL 88-020 Individual Plant Examination for S Unit 2 Action: Complete evaluation for Unit 2.
Severe Accident Vulnerabilities 06-----------------------------
REVISION 02 UPDATE:
The Probabilistic Risk Assessment Individual Plant Examination Summary Report was submitted on February 9, 2010..
REVISION 04 UPDATE:
The Individual Plant Examination of External Events Design Report was submitted on April 30, 2010.
REVISION 06 UPDATE:
The NRC issued Requests for Additional Information (RAIs) on November 12, 2010.
TVA responded to the RAIs on December 17, 2010, and April 1, 2011.
GL 89-013 Service Water System Problems CI NRC letters dated July 9, 1990 and June 13, 1997, accepting approach.
Affecting Safety-Related Equipment - _.
06 Unit 2 Actions:
- 1) Implement initial performance testing of the heat exchangers; and
- 2) Establish eddy current baseline data for the Containment Spray heat exchangers.
REVISION 06 UPDATE:
NRC Inspection Report 391/2011-602 closed GL 89-013.
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ITEM TITLE REV ADDITIONAL INFORMATION GL 89-021 Request for Information S TVA responded to GL 89-21 with the status of USIs for both units on Concerning Status of November 29, 1989. NRC provided an assessment of WBN USI status on Implementation of Unresolved 06 May 1, 1990. The NRC assessment included a list of incomplete USIs for Safety Issue (USI) Requirements WBN. USIs were initially reviewed for WBN in the SER Appendix C. USIs were subsequently reviewed in SSER 15 Appendix C (June 1995) and SSER 16 (September 1995).
Unit 2 actions:
- Complete implementation of USIs.
REVISION 02 UPDATE:
Status of USIs was provided by Enclosure 2 of TVA letter dated September 26, 2008.
The applicable USIs are either closed, deleted, or captured in either the SER Framework or the Generic Communications Framework, or they are part of the CAPs and SPs.
REVISION 06 UPDATE:
Updated status of USIs was provided on January 25, 2011.
GL 93-004 Rod Control System Failure and CO NRC letter dated December 9, 1994, accepted TVA commitments for both Withdrawal of Rod Control Cluster - . units.
Assemblies, 10 CFR 50.54(f) 06 Unit 2 Action: Implement modifications and testing.
REVISION 06 UPDATE:
NRC Inspection Report 391/2011-604 closed GIL 93-004.
GL 95-003 Circumferential Cracking of Steam CI NRC acceptance letter dated May 16, 1997 (Unit 1) - Initial response for Generator Tubes Unit 2 on September 7, 2007. TVA responded to a request for additional 06 information on December 17, 2007.
Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
Unit 2 Action:
- Perform baseline inspection.
- Evaluate or repair as necessary.
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ITEM TITLE REV ADDITIONAL INFORMATION On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-01.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061)."
100% of the steam generator tubes have been inspected.
GL 95-005 Voltage-Based Repair Criteria for C No specific action or response required by the GL; TVA responded on Westinghouse Steam Generator September 7, 2007.
Tubes Affected by Outside 06 Diameter Stress Corrosion Cracking REVISION 02 UPDATE:
On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-01.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061 )."
GL 95-007 Pressure Locking and Thermal C1 Unit 1 SER for GL 95-07 dated Sept 15, 1999 Binding of Safety-Related Power-Operated Gate Valves 06 Unit 2 Actions:
- Perform evaluation for pressure locking and thermal binding of safety related power-operated gate valves, and
- take corrective actions for those valves identified as being susceptible.
REVISION 03 UPDATE:
April 1, 2010, letter committed to evaluate missing GL 89-10 motor-operated valves for susceptibility to pressure locking and thermal binding.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 04 UPDATE:
NRC letter dated July 29, 2010, provided RAIs on the GL.
TVA letter dated July 30, 2010, answered the RAIs and provided the following commitments:
" EDCRs 53292 and 53287 shall be implemented to eliminate the potential for pressure locking prior to startup.
" Valves 2-FCV-63-25 and -26 will be evaluated for impact due to new parameters from the JOG Topical Report MPR 2524A prior to startup.
NRC issued the Safety Evaluation for GL 1995-007 on August 12, 2010.
REVISION 06 UPDATE:
TVA letter to NRC dated July 30, 2010, documented that none of the missing Watts Bar Unit 2 GL 89-10 valves are GL 95-07 valves.
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated August 12, 2010 (ADAMS Accession No. ML100190443)"
GL 96-003 Relocation of the Pressure CI No response required Temperature Limit Curves and - -.
Low Temperature Overpressure 06 Unit 2 Actions:
Protection System Limits
- Submit Pressure Temperature limits, and
- similar to Unit 1, upon approval, incorporate into licensee-controlled document.
REVISION 06 UPDATE:
The Pressure and Temperature Limits Report (PTLR) was submitted via TVA to NRC letter dated February 2, 2010.
The PTLR was incorporated inthe system description for the Reactor Coolant System (WBN2-68-4001).
GL 96-006 Assurance of Equipment C NRC letter dated April 6, 1999, accepting TVA response for Operability and Containment __. Unit 1.
Integrity During Design-Basis 06 Accident Conditions Unit 2 Action:
Implement modification to provide containment penetration relief.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 1996-006 on January 21, 2010.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML100130227)."
Modification to provide containment penetration relief was implemented.
NRC Inspection Report 391/2011-603 closed GL 96-006.
GL 97-001 Degradation of Control Rod Drive C1 NRC acceptance letter dated November 4, 1999 (Unit 1).
Mechanism Nozzle and Other - -.
Vessel Closure Head Penetrations 06 Unit 2 Action: Provide a report to address the inspection program.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 97-001 on June 30, 2010.
REVISION 04 UPDATE:
Corrected status from "OV" to "Cl" due to NRC issuance of Safety Evaluation as noted in Revision 03 update.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated June 30, 2010 (ADAMS Accession No. ML100539515)"
GL 97-004 Assurance of Sufficient Net Cl NRC acceptance letter dated June 17, 1998 (Unit 1) - Initial response for Positive Suction Head for _-. Unit 2 on September 7, 2007.
Emergency Core Cooling and 06 Containment Heat Removal Pumps Unit 2 Actions:
- Install new sump strainers, and
- perform other modification-related activities identical to Unit 1.
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 1997-004 on February 18, 2010.
REVISION 06 UPDATE:
See the REVISION 06 UPDATE for GL 04-002 for new commitments.
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated February 18, 2010 (ADAMS Accession No. ML100200375)"
GL 97-005 Steam Generator Tube Inspection CI NRC acceptance letter dated September 22, 1998 (Unit 1) - Initial Techniques - response for Unit 2 on September 7, 2007.
06 Unit 2 Action:
Employ the same approach used on the original Unit 1 SGs. TVA responded to a request for additional information on December 17, 2007.
REVISION 02 UPDATE:
On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-01.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061)"
GL 97-006 Degradation of Steam Generator CI NRC acceptance letter dated October 19, 1999 (Unit 1) - Initial response Internals - -. for Unit 2 on September 7, 2007. TVA responded to a request for 06 additional information on December 17, 2007.
Unit 2 Action: Perform SG inspections during each refueling outage.
REVISION 02 UPDATE:
On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-Page 18 of 30 * = See last page for status code definition.
R ITEM REV TITLE ADDITIONAL INFORMATION 01.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061)"
GL 98-002 Loss of Reactor Coolant Inventory Cl Initial response for Unit 2 on September 7, 2007.
and Associated Potential for Loss of Emergency Mitigation Functions 06 Unit 2 Actions:
While in a Shutdown Condition
- 1) Review the ECCS designs to ensure they do not contain design features which can render them susceptible to common-cause failures; and
- 2) document the results.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 1998-002 on March 3, 2010.
REVISION 03 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 98-002 on May 11, 2010. This letter noted that it superseded the SE issued by NRC on March 3, 2010.
April 1, 2010, letter committed to ensure that the guidance added to the Unit 1 procedure as a result of the review of NRC GL 98-02 is incorporated into the Unit 2 procedures. Specifically, when decreasing power, valve HCV-74-34, Refueling Water Return (normally locked closed valve) has a hold order placed with specific release criteria before entry into Mode 4 and to remove the hold order before entry into Mode 3 when returning to power.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated May 11,2010 (ADAMS Accession No. ML101200155)"
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ITEM TITLE REV ADDITIONAL INFORMATION GL 98-004 Potential for Degradation of the Cl NRC closure letter dated November 24, 1999 (Unit 1). - Initial response ECCS and the Containment Spray for Unit 2 on September 7, 2007.
System After a LOCA Because of 06 Construction and Protective Unit 2 Actions:
Coating Deficiencies and Foreign Material in Containment " Install new sump strainers, and
" perform other modification-related activities identical to Unit 1.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 1998-004 on February 1, 2010.
REVISION 06 UPDATE:
See the REVISION 06 UPDATE for GL 04-002 for new commitments.
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated February 1, 2010 (ADAMS Accession No. ML100260594)"
GL 03-001 Control Room Habitability S Initial response for Unit 2 on September 7, 2007 06 Unit 2 Action: Incorporate TSTF-448 into Technical Specifications.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 2003-01 on February 1, 2010.
Developmental Revision B of the Unit 2 Technical Specifications (TS) was submitted on February 2, 2010.
TS Surveillance Requirement 3.7.10.4 requires performance of a Control Room Envelope (CRE) unfiltered air inleakage test in accordance with the CRE Habitability Program.
TS 5.7.2.20 provides for the CRE Habitability Program.
These portions of the Unit 2 TS were based on the Unit 1 TS which incorporated TSTF-448 per Amendment 70 (NRC approved A70 on 10/08/2008).
REVISION 06 UPDATE:
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ITEM TITLE REV ADDITIONAL INFORMATION SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated February 1, 2010 (ADAMS Accession No. ML100270076)"
GL 04-001 Requirements for Steam Cl NRC acceptance letter dated April 8, 2005 (Unit 1) - Initial response for Generator Tube Inspection _ Unit 2 on September 7, 2007.
06 Unit 2 Action: Perform baseline inspection.
REVISION 02 UPDATE:
On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-01.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061)"
100% of the steam generator tubes have been inspected.
NRC Audit Report dated February 7, 2007 (Unit 1) - Initial response for GL 04-002 Potential Impact of Debris OV Blockage on Emergency - -. Unit 2 on September 7, 2007.
Recirculation During Design Basis 06 Accidents at PWRs Unit 2 Actions:
- Install new sump strainers, and
- perform other modification-related activities identical to Unit 1.
REVISION 06 UPDATE:
Additional TVA letters concerning GL 2004-02 were sent to the NRC on the following dates:
- January 29, 2008,
- May 19, 2008,
- September 10, 2010,
- March 4, 2011, and
- April 29, 2011.
The March 4, 2011, letter provided a response that superseded previous responses and commitments. It provided the following new commitments:
- Unit 2 will install sump modifications per the requirements of Generic Letter (GL) 2004-02 prior to Unit 2 fuel load.
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ITEM TITLE REV ADDITIONAL INFORMATION A confirmatory walkdown for loose debris will be performed on Unit 2 after containment work is completed and the containment has been cleaned. This walkdown will be completed prior to startup.
New throttle valves will be installed in the CVCS and SI injection lines to the RCS. The new valves will be opened sufficiently to preclude downstream blockage.
The current Unit 1 TVA protective coating program contains requirements for conducting periodic visual examinations of Coating Service Level I and Level II protective coatings. The Unit 2 program will be the same.
Procedural controls will be put in place at WBN Unit 2 to ensure that potential quantities of post-accident debris are maintained within the bounds of the analyses and design bases that support ECCS and CSS recirculation functions.
V-WAwill complete the WBN in-vessel downstream effects evaluation discussed inthe supplemental response to Generic Letter 2004-02 following issuance of the final NRC Safety Evaluation Report (SER) for Topical Report No. WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid."
The design basis of the modified emergency sump strainer has been incorporated into the plant's current licensing basis. The WBN Unit 2 FSAR will be amended to include this information.
- Unit 1 and Unit 2 share a common protective coatings program.
- Amendment 103 to the Unit 2 FSAR was submitted to the NRC on March 15, 2010. This amendment included the design basis of the modified emergency sump strainer.
GL 06-001 Steam Generator Tube Integrity S Initial response for Unit 2 on September 7, 2007.
and Associated Technical Specifications 06 Unit 2 Action: Incorporate TSTF-449 into Technical Specifications.
REVISION 02 UPDATE:
On January 21, 2010, NRC issued the Safety Evaluation for the following Generic Letters: 1995-03, 1995-05, 1997-05, 1997-06, 2004-01, and 2006-01.
Developmental Revision B of the Unit 2 Technical Specifications (TS) was submitted on February 2, 2010.
TS 5.7.2.12 is the Steam Generator (SG) Program. This program is implemented to ensure that SG tube integrity is maintained.
Unit 2 TS 5.7.2.12 was based on Unit 1 TS 5.7.2.12. Unit 1 TS 5.7.2.1.12 was based on TSTF-449 (NRC approved Unit 1 TS A65 on 1/03/2006).
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ITEM TITLE REV ADDITIONAL INFORMATION REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061) (See Appendix HH)"
The applicable item from SER22, Appendix HH for this item is Open item 6, "Verify implementation of TSTF-449. (TVA letter dated September 7, 2007, ADAMS Accession No. ML072570676)."
TVA to NRC letter dated April 6, 2011 provided the following response to Open Item 6:
"Amendment 65 to the Unit 1 TS revised the existing steam generator tube surveillance program and was modeled after TSTF-449, Rev. 4. The NRC approved Amendment 65 via letter dated November 3, 2006, 'Watts Bar Nuclear Plant, Unit 1 - Issuance of Amendment Regarding Steam Generator Tube Integrity (TS-05-10) (TAC No. MC9271).' Revision 82 made the associated changes to the Unit 1 TS Bases.
Developmental Revision A to the Unit 2 TS and TS Bases made the equivalent changes to the Unit 2 TS / TS Bases. Affected TS sections include the following: LEAKAGE definition in 1.1, LCO 3.4.13 (RCS Operational LEAKAGE), LCO 3.4.17 (SG Tube Integrity), 5.7.2.12 (Steam Generator (SG) Program), and 5.9.9 (Steam Generator Tube Inspection Report).
Developmental Revision A of the Unit 2 TS was submitted to the NRC via letter dated March 4, 2009, 'Watts Bar Nuclear Plant (WBN) Unit 2 -
Operating License Application Update,' (ADAMS Accession number ML090700378)."
GL 06-002 Grid Reliability and the Impact on CI Initial response for Unit 2 on September 7, 2007.
Plant Risk and the Operability of - -.
Offsite Power 06 Unit 2 Action:
Complete the two unit baseline electrical calculations and implementing procedures.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 2006-002 on January 20, 2010.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated January 21, 2010 (ADAMS Accession No. ML093631061) (See Appendix HH)"
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ITEM TITLE REV ADDITIONAL INFORMATION Note that the correct date and ADAMS Accession No. are January 20, 2010, and ML100080768, respectively.
GL 06-003 Potentially Nonconforming Hemyc CI TVA does not rely on Hemyc or MT materials to protect electrical and and MT Fire Barrier Configurations _-_. instrumentation cables or equipment that provide safe shutdown capability 06 during a postulated fire.
Unit 2 Action:
Addressed in CAP/SP.
The Fire Protection Corrective Action Program will ensure Unit 2 conforms with NRC requirements and applicable guidelines.
REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 2006-003 on February 25, 2010.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed. NRC Letter dated February 25, 2010 (ADAMS Accession No. ML100470398)"
GL 07-001 Inaccessible or Underground CI Initial response for Unit 2 on September 7, 2007.
Power Cable Failures That Disable - -.
Accident Mitigation Systems or 06 Unit 2 Action: Complete testing of four additional cables.
Cause Plant Transients REVISION 02 UPDATE:
NRC issued the Safety Evaluation for Generic Letter 2007-001 on January 26, 2010.
REVISION 04 UPDATE:
NRC Inspection Report 391/2010-603 closed GL 2007-001.
REVISION 06 UPDATE:
The four additional cables passed the testing.
SSER22 contained the following for NRC Action:
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ITEM TITLE REV ADDITIONAL INFORMATION "Closed. NRC Letter dated January 26, 2010 (ADAMS Accession No. ML100120052)"
GL 08-001 Managing Gas Accumulation in 0 Initial response for Unit 2 on October 1, 2008.
Emergency Core Cooling, Decay - -.
Heat Removal, and Containment 06 Spray Systems REVISION 02 UPDATE:
Unit 2 Actions:
- TVA will provide a submittal within 45 days of completion of the engineering for the ECCS, RHR, and CSS systems.
- WBN Unit 2 will complete the required modifications and provide a submittal consistent with the information requested in the GL 90 days prior to fuel load.
REVISION 06 UPDATE:
The submittal was provided inTVA to NRC letter dated March 11, 2011.
This submittal satisfied the above Unit 2 actions and generated the following new commitments:
- TVA will evaluate adopting the revised ISTS SR 3.5.2.3 (NUREG 1431) at WBN within 6 months of NRC approval of the Traveler.
- Complete evaluation of CS pump 2A-A pipe chase horizontal suction piping for venting. Add a vent valve to this location or conduct periodic UT examinations if necessary. (90 days prior to fuel load.)
- Add vent valves to selected locations in the ECCS and RHRS piping to enhance filling and venting. (90 days prior to fuel load.)
- Complete walk down survey of ECCS and RHRS piping and evaluate the piping for latent voids that could exceed 5% of the pipe cross sectional area. (90 days prior to fuel load.)
- Operating procedures are being revised to improve instructions for filling and venting portions of the ECCS discharge pipe. (90 days prior to fuel load.)
- Complete Preoperational tests on ECCS and RHRS systems to confirm Unit 1 operating experience showing no gas intrusion/accumulation issues. (90 days prior to fuel load.)
- Periodic venting procedures used to meet SR 3.5.2.3 are being revised to require that, for an extended gas release, a report is entered into the Corrective Action Program. (90 days prior to fuel load.)
NUREG- Independent Safety Engineering OV LICENSE CONDITION - Independent Safety Engineering Group (ISEG) 0737, Group - (NUREG-0737, I.B.1.2)
I.B.1.2 06 Resolved for Unit 1 only in SSER8.
Unit 2 action:
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ITEM TITLE REV ADDITIONAL INFORMATION Implement the alternate ISEG that was approved for the rest of the TVA units including WBN Unit 1 by NRC on August 26, 1999. The function will be performed by the site engineering organizations.
REVISION 06 UPDATE:
By letter of March 2, 1999, TVA proposed to eliminate the ISEG function from the fleet-wide nuclear organization.
NRC safety evaluation of August 26,1999 shows that the NRC accepted the elimination of the ISEG with alternate organizational responsibilities provided in TVA-NQA-PLN89A and TVA-NPOD89-A.
By letter of August 26, 1999, TVA revised Topical Report TVA-NPOD89-A, Rev 8 to describe the alternate organizations responsible for the management and operation of TVA's nuclear projects that replaced the ISEG function.
The developmental Unit 2 TS were modeled after the Unit 1 TS. There is no reference to the ISEG.
The current revision of TVA-NQA-PLN89-A (24A1) was written to include Unit 2.
The current revision of TVA-NPOD89-A (18) was written to include Unit 2.
NUREG- Control Room Design Review Cl NRC reviewed in SSER5, SSER6, SSER15, and Appendix EE of 0737, _. SSER16.
I.D.1 06 Unit 2 Actions:
- Complete the CRDR process.
- Perform rewiring in accordance with ECN 5982.
- Take advantage of the completed Human Engineering reviews to ensure appropriate configuration for Unit 2 control panels.
See CRDR Special Program.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed in SSER22, Section 18.2" NUREG- Accident-Monitoring CO Reviewed in SSER9.
0737, Instrumentation - Containment II.F.1.2.d. Pressure 06 Unit 2 Action: Verify installation of containment pressure indication.
REVISION 06 UPDATE:
NRC Inspection Report 391/2011-604 closed NUREG-0737, lI.F.1 .2.d.
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ITEM TITLE REV ADDITIONAL INFORMATION NUREG- Accident-Monitoring CO Reviewed in SSER9.
0737, Instrumentation - Containment _ -.
II.F.1.2.f. Hydrogen 06 Unit 2 Action: Verify installation of containment hydrogen accident monitoring instrumentation.
REVISION 06 UPDATE:
NRC Inspection Report 391/2011-604 closed NUREG-0737, II.F.1.2.F.
NUREG- Power Supplies For Pressurizer CI Reviewed in original 1982 SER and 8.3.3 of SSER7.
0737, Relief Valves, Block Valves and _ -.
II.G.1 Level Indicators 06 Unit 2 Action:
Implement modifications such that PORVS and associated Block Valves are powered from same train but different buses.
REVISION 06 UPDATE:
Modifications were implemented such that PORVS and associated Block Valves are powered from same train but different buses.
NUREG- Reporting SV/RV C (Action from GL 82-16) - NRC reviewed inAppendix EE of SSER16.
0737, Failures/Challenges _ -.
11.K.3.3 06 Unit 2 Action: Include, as necessary, inTechnical Specifications submittal.
REVISION 02 UPDATE:
Developmental Revision A of the Unit 2 Technical Specifications (TS) was submitted on March 04, 2009.
Rev. 0 of the Unit 1 TS contained 5.9.4 (Monthly Operating Reports) which implemented the above commitment for Unit 1.
Amendment 57 to the Unit 1 TS (approved by the NRC on March 21, 2005) deleted this section of the TS.
The markup for Unit 2 Developmental Revision A noted that Unit 2 will apply this change, and the Unit 2 TS will contain no requirement for Monthly Operating Reports.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed in SSER22, Section 13.5.3."
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R ITEM TITLE REV ADDITIONAL INFORMATION NUREG- PID Controller Cl Reviewed in original 1982 SER.
- 0737, 11.K.3.9 06 Unit 2 Action: Set the derivative time constant to zero.
REVISION 06 UPDATE:
The derivative time constant was set to zero.
NUREG- Power On Pump Seals C NRC reviewed and closed in IR 390/84-35 based on Diesel Generator 0737, _-. (DG) power to pump sealing cooling system.
II.K.3.25 06 Unit 2 Action:
Ensure DG power is provided to pump sealing cooling system.
REVISION 06 UPDATE:
It was confirmed that DG power is provided to pump sealing cooling system.
NRC Inspection Report 391/2010-605 closed NUREG-0737, II.K.3.25.
NUREG- Small Break LOCA Methods C TVA: letter dated October 29, 1981
- 0737, I1.K.3.30 06 NRC: letters dated March 29, 1985, and July 24, 1986; SSER 16 The staff determined in SSER4 that their review of Items I1.K.3.30 and I1.K.3.31 did not have to be completed to support the full-power license and considered this LICENSE CONDITION resolved in SSER4. In SSER5, the staff further reviewed responses to these items, and concluded that the Units 1 and 2 FSAR methods and analysis met the requirements of I1.K.3.30 and II.K.3.31. This item was further reviewed in Appendix EE of SSER1 6.
Unit 2 Action: Complete analysis for Unit 2.
REVISION 06 UPDATE:
The analysis has been completed for Unit 2.
NRC Inspection Report 391/2011-603 closed NUREG-0737, II.K.3.30.
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ITEM REV ADDITIONAL INFORMATION TITLE NUREG- Plant Specific Analysis C The staff determined in SSER4 that their review of Items II.K.3.30 and 0737, - -. II.K.3.31 did not have to be completed to support the full-power license and I1.K.3.31 06 considered this LICENSE CONDITION resolved in SSER4. In SSER5, the staff further reviewed responses to these items, and concluded that the Units 1 and 2 FSAR methods and analysis met the requirements of I1.K.3.30 and I1.K.3.31. This item was further reviewed in Appendix EE of SSER16.
Unit 2 Action: Complete analysis for Unit 2.
REVISION 06 UPDATE:
The analysis has been completed for Unit 2.
NRC Inspection Report 391/2011-603 closed NUREG-0737, ll.K.3.31.
NUREG- Control-Room Habitability Cl TVA: letter dated October 29, 1981
- 0737, II1.D.3.4 06 NRC: SSER16 NRC reviewed in SER and in Appendix EE of SSER16.
Unit 2 Action: Complete with CRDR completion.
REVISION 06 UPDATE:
SSER22 contained the following for NRC Action:
"Closed in 55ER22, Section 6.4'
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ITEM TITLE REV ADDITIONAL INFORMATION STATUS CODE DEFINITIONS C: CLOSED: Previous staff review of NUREG-0847 and/or supplements has closed the item either for both units at WBN or explicitly for WBN Unit 2.
CI: CLOSED/IMPLEMENTATION: Staff has approved either for both units at WBN or explicitly for WBN Unit 2; there is no change to the approved design; and implementation is recommended through Regional Inspection.
CO: CLOSED - OPEN: Staff has approved closure of the item; however, TVA actions remain to be completed.
CT: CLOSED/TECHNICAL SPECIFICATIONS: Item has been approved either for both units at WBN or explicitly for WBN Unit 2; however, a change to the original approval requires submittal of the Technical Specifications and staff review.
NA: NOT APPLICABLE: Justification as to why a section / subsection is not applicable is provided in the ADDITIONAL INFORMATION column.
0: OPEN: No action or documentation is provided that shows the staff has reviewed the item for WBN Unit 2.
OT: OPEN/TECHNICAL SPECIFICATIONS: No action or documentation is provided that shows the staff has reviewed the item for WBN Unit 2, and the resolution is through submittal of a Technical Specification.
OV: OPENNALIDATION: The proposed approach has been approved for Watts Bar Unit 1; the same approach is proposed for use on WBN Unit 2 without change.
S: SUBMITTED: Information has been submitted, and is under review by NRC staff.
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