Weak link
Weak link# QUERYf92cb9314c604bb02ad6453632b9166d
Weak link# QUERYaac4e349182cf420afc75232a1d27efb
Weak link# QUERY4489402bd7490697cbca18aef77550bc
Weak link Beaver Valley
Weak link# QUERYd20a68b475af85b06f2ec958c7afeca1
Weak link# QUERYd584b5bf026eca80dc576111eb0d3a1e
Weak link Calvert Cliffs
Weak link# QUERY26d4b7915ce6aed4e912bd5b04c8615d
Weak link FitzPatrick
Weak link# QUERYb67628ac8afa027776e32e813acdcdc4
Weak link# QUERYada8610ff92575562b4db6186d0d0d5c
Weak link# QUERY8c6d98eb48a9b4f75ea4ae54419036ac
Weak link# QUERY323463d8edef3b2c2d6f81e0bb700cf1
Weak link Hope Creek
Weak link# QUERYcc50952caf12f2da8d8b184175628ec4
Weak link# QUERYa020234f6eee5c7cd09f35dbaeda6ce4
Weak link# QUERY12e5daeef1fd9501f97eb883a471e8b1
Weak link Millstone
Weak link# QUERYca30fb6c1e6d187141ca5aae10ec4efb
Weak link Nine Mile Point
Weak link Peach Bottom
Weak link# QUERY7b8de3881c16a0c3da66e33b130474e5
Weak link# QUERY53d8bf191b3e55e320f4dd845339596a
Weak link# QUERYd074c2cc1d8907e89f4cfbe264471ce2
Weak link Susquehanna
Weak link# QUERY908920e3ade6c7ad42fccb22f84d7ac6
Weak link# QUERY2c4cb0ebd2aa6242b00402797e2e2411
NRC Region 1 false
Weak link# QUERY7a67bed0767cfcf0d82172f65aac0556
Weak link Haddam Neck
Weak link# QUERYe995e4e0825e372b2a16cbd60b3785b6
Weak link# QUERYef7f2d445a012d86b6a337a9191a6a17
Weak link Indian Point
Weak link# QUERYae76b5cdc277061dd5ef3ad805d3dd47
Weak link# QUERYd3d8d39069e362ca4e62b3c203c5baf8
Weak link Maine Yankee
Weak link# QUERY1dae8731c8b59567cc5121420eec6c5c
Weak link Oyster Creek
Weak link# QUERY84c8c43b7e6ee6360ac5ae2de9d75195
Weak link# QUERY03af4351db0d45c0925cc16ddec4d512
Weak link# QUERYd5cfe6f4befc665b8fc26d6e3a08f4a7
Weak link# QUERY9a10d78f65013d455cf2356ca2804dc5
Weak link# QUERY8a3a5bcbeae7b182c1dc32e1c0ca85e4
Weak link Shippingport
Weak link# QUERY60468648f1c10eacda1f1ed9c6a9fce3
Weak link# QUERYc2a78050c4560bfb0aad327c2604cd4b
Weak link# QUERYc7e40aad9fec99977a0a9ee26df3b1ff
Weak link Three Mile Island
Weak link# QUERYd93e79e4735cdfa1575ff1747f847f79
Weak link# QUERY04451df2f585da411b2a280edf86e0ab
Weak link Vermont Yankee
Weak link# QUERY8bca47d985c2c04482d4d6a760efc493
Weak link# QUERY934e5427eeb8939de9990811bdceeba6
Weak link Yankee Rowe
Weak link# QUERYe15ee6acf8fd3b9c7cfe63dfa92f7ed9
Weak link# QUERY09e287bcb559d27f570cbd44eaa5d751
Weak link# QUERY068de7ca7e8d236b6f66aaddeabb0462
NRC Region 1 true
Weak link# QUERYa3013f81b2c3556f952fc20ebfb722f7
Weak link Browns Ferry
Weak link# QUERY349cd291bd268fc3446d05c1a745879b
Weak link# QUERYb76cd9fe397fc58cd082417b1fdd6137
Weak link Brunswick
Weak link# QUERY3cef9a7e31976669e09e9f3b878c80b6
Weak link# QUERY25c2a4e2d893a2c11e4f0ebd33ae47c6
Weak link# QUERY9a43cf8b1d36aecf5b007162b7eb96b1
Weak link# QUERY6f3c338e79f3eedaf09aa22965471b7d
Weak link# QUERY5377c12774dc82d44aac6a654d3899a4
Weak link# QUERYa6bd20b77a09865e43491cd55db5fa24
Weak link# QUERY006e79a38603ef18a38b12db8e7058b0
Weak link# QUERY97bdd68aff866c380a716c62ddd4ccc8
Weak link# QUERYc8efd6349823a5e22ec7d57d3a037df7
Weak link# QUERYe87287f6dc0eacee6ff96ddca89248ff
Weak link# QUERY514e5b4d772f8f8fff99384d61ed79d5
Weak link# QUERYd8237e1f0b37e3bb93e1e1acb76439fd
Weak link North Anna
Weak link# QUERY6021e4b2075fc9bb3636f0347c1921ea
Weak link# QUERY20d58a4a53ec91feee67f384b2ff9271
Weak link# QUERY2b0933d081d08652b864a1a7f6e31d5c
Weak link# QUERY7fcc3b3e463415a44f5e19fc18b6b671
Weak link# QUERY9fa6013172fe2fc580f40889b2b3d302
Weak link Saint Lucie
Weak link# QUERY43f1c9d20cee61d8841cb48bafa376a1
Weak link# QUERY9b31e13f0043332ef8301e5ef4e0a6fc
Weak link# QUERY4633be9649685e1ea38aac369d4f7d46
Weak link# QUERYf94910558e18dd764a6400d4e7389ecf
Weak link# QUERYc9af8eaf1677d227853b0bbc6cb6530a
Weak link# QUERY2b3fd46103565e22fa17bada6db6b542
Weak link# QUERYd6f4a16851e2986041467c6cabf0186b
Weak link# QUERY97c73bd6f558a54394d5f3633bc3b003
Weak link Turkey Point
Weak link# QUERYc9a8a2bceaaf2c8392e1c03510513e65
Weak link# QUERY67c3a215ea186a03be5f71e7ace1ebff
Weak link# QUERYd7b6e254dab7178bc598069364233d3f
Weak link# QUERYe9fcbc081f8f7f3c7428dbbeccf1dd33
Weak link Watts Bar
Weak link# QUERYa801fa8751648455a401f4dfce086d94
Weak link# QUERYa4d33a89633321bd1ebae20d7002bff3
NRC Region 2 false
Weak link# QUERYef2ed89eccc51cc609623ec1f2ae0e81
Weak link Crystal River
Weak link# QUERY07e2b09dbd9987778fd8aa25658d99e9
Weak link# QUERYa160cdf9e9b847e4674c74f77adf45ce
Weak link# QUERY9d88a200e50bc3df9350f2b5d9f6c0eb
NRC Region 2 true
Weak link# QUERY03a4ee5432c9daa6cecac06e7884f24d
Weak link Braidwood
Weak link# QUERY8769302950fdeda98f32a987b37df33b
Weak link# QUERYfbd327e2c889a9b04b178aa33078ddc4
Weak link# QUERY345e5fd9f04a78d05a08daa7cb1431f0
Weak link# QUERY20b7f2ec87db50b45021df31562f8ea1
Weak link# QUERYeeb3ac19534fa4e57c9a85c6fe777994
Weak link# QUERY3c2dbb3564f712be30d1908cd0d7e020
Weak link# QUERYc2af400d0c71804abf9b4dd5c6d8c929
Weak link# QUERYa0c84079f6966251ccefc1b4a6a3c868
Weak link Davis Besse
Weak link# QUERY827e980c2c9005205bbdb13c10db2863
Weak link# QUERY999dc3acbb714b9821eaf2843618c918
Weak link Duane Arnold
Weak link# QUERY93faef0065316e86ab5fdfea2a260cd2
Weak link# QUERY097ea8eec8c821883eed87097a575df2
Weak link# QUERYb29be75e49bb2d10089770ddbff32b1f
Weak link# QUERYcd8719350ce42b43582c9ca947fe47d2
Weak link# QUERYc08c3ef098531f49e0db2954814a106c
Weak link Monticello
Weak link# QUERY333b5948d62bfa2dd270605d6ea2f2e6
Weak link# QUERY8d09e3c8f7de79b3e8cb20d897e318bd
Weak link Palisades
Weak link# QUERY1b15d4a0fc83764fbb8d27bd0d7fdd0d
Weak link# QUERYcd714382839d5800183deedc5da45473
Weak link# QUERYbda119c670ab61ada2fafe390110caa0
Weak link# QUERY3d074f25d98b93febb2e0ab21e701b3f
Weak link Point Beach
Weak link# QUERYdb532105bf50a398ad479cb477097f8e
Weak link# QUERYe5e2acea7f4c16098f4207d546248f57
Weak link Prairie Island
Weak link# QUERY6d557de5c74fbca5eacf4dad99fb3f4f
Weak link# QUERY4832c0716a77f119e06953aafcc8c34f
NRC Region 3 false
Weak link Big Rock Point
Weak link# QUERY2da69bce262d2b058ec0d40134fe7727
Weak link Elk River
Weak link# QUERYd505210d98a2d5af90e3f193916d30c4
Weak link# QUERY5cb2a523d8079ae98f31ed65a9c12aca
Weak link# QUERY7e55ffd4ff0eb884b8dade05c190f43f
Weak link La Crosse
Weak link# QUERYb33bacffe488df38e0ddd6a950ffd52b
Weak link# QUERY231eb00df3adbee9c279caad8cb77e0e
NRC Region 3 true
Weak link# QUERY4b875cd2f5745a1db5699c9bf7b8b28c
Weak link Arkansas Nuclear
Weak link# QUERYf1f3442d8c7c0380d9a110e3ef2ec004
Weak link# QUERYb7fcfc269a7de59fc527e2844d2cff00
Weak link# QUERY2a98f8b70453cdfe6a6e2fcc76538a1c
Weak link# QUERYaa4c8e94ca8faaa3789ac6c2ffe82ecc
Weak link# QUERYd0cbf1a32ecf759b6f1d4f8d0e00e8a8
Weak link Comanche Peak
Weak link# QUERY14c1081ba1034ba1db97a0d71a5fc706
Weak link# QUERYa63fb2abb34e9313749593cbcce1f000
Weak link# QUERYce3298c094fda5cd80e81295e69a655b
Weak link Diablo Canyon
Weak link# QUERY0860c63ca5efdf009fe9be8960ee7685
Weak link# QUERYf43e4fb37b6d978ac01dc315c5dbbd4f
Weak link Grand Gulf
Weak link# QUERYded525e53c7f289d0d8f3351c0fb433d
Weak link# QUERY9cad62e3f570f05d5d2a375e8e855a85
Weak link Palo Verde
Weak link# QUERYa59c4b190305fcb3f6f30e735e4910d6
Weak link# QUERYc24817c498b2dcec40499b53c1219c23
Weak link Quad Cities
Weak link# QUERY6554ee2b8d212e6a62813dca8290c5f3
Weak link# QUERYb105a3ddfe0af1ab7ce05f7f2e71a71c
Weak link River Bend
Weak link# QUERYa3e06ccbc2646f1b1fb12723ba08a597
Weak link# QUERY22dda617a06de872ae1966297dee81e6
Weak link South Texas
Weak link# QUERYe8ca9a5639e642b8e2cc4d1d7a9a995a
Weak link# QUERY13d0d919d7b15b99dac757fcc20f77cc
Weak link Sundesert
Weak link# QUERY12ee764c4121f7ab7632de4fd7b13d4f
Weak link# QUERYad5430fea7ea10ac16307cbd28e1f0dd
Weak link# QUERYa4bb0016de93f67feba7777d75edfcf8
Weak link Waterford
Weak link# QUERY7e3fe162aff5e1526886653d2a436f5f
Weak link# QUERY6ee77d0b9fc467e100bfe3b9646313cf
Weak link Wolf Creek
Weak link# QUERYff7bb23f2d2ff36ab025d9093e7b7e3c
Weak link# QUERYcbbc63f36e869c9cadb56617b01ae621
NRC Region 4 false
Weak link Fort Calhoun
Weak link# QUERYbd0a7d6e15cc8e04775991bfa1573aa4
Weak link Fort Saint Vrain
Weak link# QUERYf9793c4cec64802780c165b288b4b7ad
Weak link# QUERY4558caf08d7497dcc9da0b038ca80320
Weak link# QUERY4d4d392e2489f4c5d0613faf38a9e952
Weak link# QUERY51ff3daffb60417e5f9b8c93f83d1811
Weak link Humboldt Bay
Weak link# QUERYb31677af59ed71e73cf6fa627916f486
Weak link# QUERYd7fb88660562f9dd763a416f55070bf2
Weak link Rancho Seco
Weak link# QUERY5270ff5b820160ff5ec2a73e7b802f53
Weak link# QUERY5ae26c8cdfc9dab88baf29830d657f1b
Weak link San Onofre
Weak link# QUERYadc88f7daad08b66cd9d469a756ecd84
Weak link# QUERY01688c71d88d5ce60d5193ba0dee866b
Weak link# QUERY16c9c2aa46c5da54b11970621a98fcca
NRC Region 4 true
Weak link# QUERY3f48e2e2d298162fc4e22365ef7b7e59
Weak link# QUERY67d4ed0b20510646db1e350b0c3552c5
Weak link# QUERY3fc39057ad819c3ca76d7bd52c0cd79f
Weak link Clinch River
Weak link# QUERY7871ebb7e96fd93e1aec400d51573d60
Weak link# QUERYad85b1da36c5db7bab46ede1ab5a84c9
RC-17-0019, Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 1
RA-17-0016, Duke Energy - Proposed Alternative in Accordance with 10 CFR 50.55(z)(1) for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange (17-GO-001)
L-2017-104, Submittal of Report Pursuant to 10 CFR 71.95(a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
LR-N17-0104, Submittal of Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of Tn RAM Packaging Certificate of Compliance No. 9233
NLS2017057, Submittal of Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
L-17-195, CFR 71.95 Report - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package
RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)
RS-16-142, Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange
NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0
NL-16-0723, Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.0
RIS 2000-03, Resolution of Safety Issue 158: Performance of Safety Related Power-Operated Valves Under Design Basis Conditions
LR-N15-0259, Denial of NCV 05000354/2015007-02, Inadequate Work Order Instructions and Drawings Resulting in Improper Installation of a Safety-Related SW Valve
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5
Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves
Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections
Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents
NLS2017100, Anchor Darling Double Disc Gate Valve Information and Status
CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 3
CP-201400736, Submittal of Regulatory Issue Summary (RIS) 2014-07 Requested Information
BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A
BSEP 13-0066, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
JAFP-13-0025, Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
TMI-12-161, Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page D-1 Through End
DCL-11-005, Report on the Analysis of the Shoreline Fault Zone, Appendix C, Seismicity Reviews Through Appendix D, Potential Field Data - Magnetic Surveys
RS-18-030, Relief Requests Associated with the Fourth Inservice Inspection Interval
AEP-NRC-2018-33, Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination
RS-13-145, Byron, Units 1 and 2 - Environmental Report, Part 2
RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report
NL-10-101, Response to August 11, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual
NL-10-042, Response to January 20, 2010 Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NRC 2009-0132, Transmittal of Information to Support License Amendment Request 241, Alternative Source Term Seismic Evaluation Guidelines for HVAC Duct and Damper Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 3.0 - Design of Structures, Components, Equipment, and Systems
JAFP-18-0050, Report of Full Compliance with Phase 1 & Phase 2 of 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
NRC 2009-0121, Enclosure 1 - S&A Report No. 09Q0839-R-001, Rev. 0, Pbnp Vnpab and CREFS Seismic Verification
NRC-19-0016, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval
L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange
RS-19-116, Relief Requests Associated with the Fourth Inservice Inspection Interval
L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval
L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
IA-97-177, Discusses Potential 10CFR21 Reportable Concern from Crane Valves on Weak Link Analyses,Per .Considers Action Taken by Crane to Be Reasonable in Alerting Nuclear Utils to Updated Weak Link Calculations for MOVs Used in Plants
B17347, CFR50.59 Annual Rept for Jan-Dec 1997
BSEP-97-0408, Informs NRC of Status of BSEP GL 89-10, SR MOV Testing & Surveillance, Program.List of Commitments Provided
0CAN049910, Forwards Response to NRC 990401 Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Gate Valves
3F1297-24, Provides Supplemental Info to Support Util Response to NRC Request for Addl Info,Dtd 970128.Clarification to Util RAI Responses,Discussed During NRC Audit USI A-46 & Calculations Encl also.W/10 Oversize Drawings
B16923, Forwards Info Which Identifies Criteria for Declaring RBCCW Sys Ready for Functional Insp,Details of Remaining Work in Area & Details on Sys Mods Re Independent CA Verification Program Tier 1 out-of-scope Insp
BSEP-98-0244, Responds to NRC Re Violations Noted in Insp Repts 50-324/98-10 & 50-325/98-10.Corrective Actions:Replacement of Torque Switch & Spring Pack,Valve 1-SW-V-106,has Successfully Passed Periodic Testing Requirements
3F0897-01, Forwards Response to RAI on Resolution of USI A-46,stating That Anchorage Calculations for Tanks & Heat Exchangers to Confirm Engineering Judgement of Anchorage Adequacy Will Be Completed Prior to Restart But No Later than 971201
JPN-94-057, Requests 6 Month Extension to Original Schedule Commitment for Completion of GL 89-10 Program Re safety-related MOV Testing & Surveillance Program
PNO-II-96-060A, on 961004,licensee Notified NRC That Extended Shutdown Was Being Initiated to Accomplish Design Mod to Increase Safety Margins.On 960902,plant Was Shutdown Due to Problem W/Turbine Oil Sys.Meeting Scheduled on 961009
NSD-NRC-97-5100, Forwards Three Copies of Responses to RAI Re Automatic ADS Testing Performed in Support of AP600 Design,Provided to Close Open Items 27,500,1616 & 3397 in Oits.Provide Comments by 970516 to Meet Milestone in SECY-97-051
E000-97-011, Discusses Revised Schedule for Completion of MOV Program Review
B16240, Annual Repts for 10CFR50.59 PORV & SV Challenges Primary Coolant Specific Activity Analysis Occupational Radiation Exposure for 1996
JAFP-97-0062, Forwards Comments Re Draft NRC Info Notice 97-XX, Potential Failures of GE Magne-Blast Circuit Breaker Subcomponents & Draft Notice
ST-HL-AE-2132, Submits Interim Rept on Activities Undertaken in Order to Evaluate Use of Welded Attachments on ASME III Class 2 & 3 Piping at Plant,Per .Evaluation of Pipe Supports Continuing.Final Rept Will Be Forwarded by 870710
ST-HL-AE-2025, Forwards Program for Control of Welded Attachments in Sys Where Arbitrary Intermediate Pipe Breaks Eliminated,Per 870331 Discussion.Info & Commitments Adequate to Resolve Staff 870227 Request for Addl Info
BW220019, Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22)
ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads
CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
AECM-85-0357, Special Rept 85-014/0:on 851012-13,temps in Auxiliary Bldg Steam Tunnel Exceeded 125 F Limit of Tech Spec 3.7.8.Temp Limit Exceeded Due to Valve Packing Gland Leaks.Leaks Will Be Repaired by 851119
NPL-97-0090, Responds to GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs
NPL-97-0038, Responds to Requesting That Util Provide Info to NRC Staff,Per 10CFR50.54(f) Re Adequacy & Availability of Design Bases Info for Pbnp
ET-NRC-92-3777, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 920923 & 1001 Ltrs.Transmittal Partial Response to Ltrs.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
BVY-92-111, Submits Info Re Methodology/Plans to Address Suppl 4 to GL 88-20 Re IPE of External Events for Severe Accident Vulnerabilities.Internal Fires & Internal Floods Will Be Analyzed W/Level 1 Pra.Results Will Be Sent by 950630
ST-HL-AE-4215, Responds to Insp Followup Observations in Insp Repts 50-498/92-26 & 50-499/92-26 on 920903-04.Corrective Actions: Util Will Refer to Thrust Values Calculated Using Degraded Voltage & Running Coefficient as Min Running Thrust
RBG-20967, Forwards Revised Environ Qualification Justification for Interim Operation Previously Submitted on 850215.Rev Provides New Completion Date of 851130 for Srn 228214-2, Motor-Operated Valves W/Limitorque Type Smc Operators
LIC-96-0121, Responds to RAI Re Resolution of USI A-46
RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves
0CAN079601, Forwards Response to Request for Addl Info Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
ST-HL-AE-5405, Provides Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves
RBG-20-386, Forwards Justifications for Interim Operation of Class 1E Electrical Components Located in Harsh Environ for Which Qualification Incomplete.Encl Inadvertently Omitted from 850215 Submittal
JPN-92-035, Responds to GL 89-10 Re Consideration of Results of NRC Sponsored Tests of motor-operated Valves.Mod Proposed to Remove Bypass Line & 12MOV-80
0CAN029605, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
BVY-95-114, Provides Addl Info Re GL 88-20, IPE for Severe Accident Vulnerabilities 10CFR50.54(f)
AECM-84-0299, Forwards Supplemental Info on Tech Spec Review Problem Sheets 100,305 & 336
RBG-36-637, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-458/91-24.Corrective Actions:Developed Engineering Dept Procedure EDP-ME-27 to Provide Methodology to Feed Back Info from Diagnostic Testing & Maint
BVY-91-108, Responds to Weaknesses/Concerns Noted in Team Insp Rept 50-271/91-80 Re Proposed motor-operated Valve Program,Per Generic Ltr 89-10.Corrective action:motor-operated Valve Program Will Be Revised by 920601 to Address Generic Ltr
AECM-83-0329, Interim Deficiency Rept 3 Re Nelson Stud Failures on Type 86 Embed Plates.Initially Reported on 821221.Unit 1 Embed Plates Replaced W/Surface Mounted Plates.Final Rept to Be Submitted by 830705.Also Reported Per Part 21
L-2022-157, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report
CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval
AECM-82-0387, Final Deficiency Rept PRD-82-38 Re Nelson Stud Failures on Embedded Plates.Initially Reported on 821221.Condition Not Reportable Per Part 21 for Unit 2.Failure Unique to Type 86 Plate.Welds Will Be Redesigned
NRC-94-4154, Forwards Responses to NRC RAIs on AP600 from NRC 940301,16, 18 & 0429 Ltrs.Rev of Previous Response Also Included.Ltr Completes Responses to 940301 & 18 Ltrs
NG-94-1445, Requests Schedule Extension to Complete GL 89-10, Safety Related Motor Operated Valve Testing & Surveillance, Activities for 51 Motor-Operated Valves in Ies Utilities Inc GL 89-10 Program
BECO-90-158, Responds to Suppl 3 to Generic Ltr 89-10, Consideration of Results of NRC-Sponsored Tests on Motor-Operated Valves. Subj Valves in Hpci,Rcic & RWCU Sys Capable of Providing Containment Isolation in Event of Line Break
B14646, Provides Addl Info Re Issues Discussed During 931001 Enforcement Conference,Relative to Focus on Nuclear Safety, 2-CH-442 Previous Leakage History,Ultrasonic Testing Capability & Valve Repair Logic
RBG-39189, Responds to GL 89-10,Suppl 5, Inaccuracy of MOV Diagnostic Equipment
TXX-6057, Forwards Response to 860911 Request for Addl Info Re Elimination of Arbitrary Intermediate Pipe Breaks. Configurations of Eliminated Piping Attachments within Five Diameters of Breaks Will Be Identified
TXX-6014, Forwards Changes Scheduled for Future FSAR Amend,Resulting from Analysis to Justify Cable Slices in Raceways,Per 860804 Commitments
TXX-4839, Forwards Gibbs & Hill,Inc Analysis of Cable Splice Terminations Located in Raceways,In Response to Reg Guide 1.75,Rev 1.Bunker Ramo Electrical Penetration Assemblies (EAP) Will Be Replaced W/Environmentally Qualified EPAs
LD-88-005, Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl
PY-CEI-NRR-1849, Amends 940408 Response to GL 89-10,Suppl 6 to Include Info Obtained as Result of Refueling Outage 4 Activities.Gl 89-10 MOV Testing Schedule Extension & Application of Grouping Methodology,Bases & Justification Encl
RA24-023, Response to NRC LaSalle County Station, Units 1 and 2, Integrated Inspection Report 05000373/2024001 and 05000374/2024001
05000458/LER-1989-026, :on 890512,determined That Three safety-related Motor Operated Valves Operated Outside Design Basis.Caused by Size & Location of Restricting Orifices.Orifices Resized & Relocated
05000318/LER-1998-005-01, :on 980725,initiated Plant Cooldown Due to RCS Pressure Boundary Leakage.Caused by Crack in Inconel Alloy 600-type Weld Filler Matl of Nozzle.Leaking Penetration Was Repaired from Outside of Pressurizer
05000254/LER-1988-005, :on 880201,control Room Ventilation Isolation Occurred.Caused by Personnel Error.Personnel Retrained & Chlorine Monitor Probe Replaced & Tested Satisfactorily
05000440/LER-1996-006, :on 960718,MOV Control Circuitry Design Deficiency Resulted in Fire Protection Violation.Fire Impairment Was Issued for Control Room Fire Protection Features & Addl MOVs Considered for Mod
05000266/LER-1997-002, :on 970109,potential to Overpressurize Piping Between Containment Isolation Valves Occurred.Caused by Original Design Not Providing Overpressure Protection for Piping.Review Completed
05000346/LER-1996-002, :on 960320,noted Potential for Loss of Remote Shutdown Capability.Caused by Fire Induced Hot Short Which Could Bypass Valve Protection Features.Implemented Hourly Roving Fire Watches & Completed Evaluations
05000416/LER-1992-002-03, :on 920320,determined That Actuators for Suppression Pool Makeup Sys Dump Valves Undersized,Per Generic Ltr 89-10.Caused by Use of Min Flowrate in Actuators.Torque Switch Setting Reset
B15388, Forwards Generic Ltr 89-10 Design-Basis Closure Millstone Unit 3
05000328/LER-1990-018-01, :on 901121,limiting Condition for Operation Entered RHR cross-tie Valve to Closed to Perform Maint to Correct Valve Torque Switch Setting.Caused by Inadequate Training of Personnel.W/Undated Ltr
05000331/LER-1993-009, :on 931005,HPCI Valve Tripped Breaker After Being Closed.Caused by Incorrect Torque Setting.Torque Switch & Motor Replaced
05000454/LER-1994-001-05, :on 940201,discovered Several Valves May Not Stroke Under High Differential Pressure Conditions Due to Inadequate Torque Switch Setting.Caution Cards Placed on Effected Valves
05000456/LER-1994-001-06, :on 940202,identified Minimum Required Torque to Open & Close Valves Under High Differential Pressure Conditions Greater than Motor Capability.Caused by Inappropriate Valve Actuator Sizing
05000336/LER-1993-015, :on 930913,discovered That Actuator Motor Brakes on FW MOVs 2-FW-38A&B & 2-FW-42A&B Might Not Release at Design Undervoltage Due to Personnel Error.Engineering Review Conducted
B14504, Eqe Procedure to Perform Seismic Screening Walkdowns for Main Steam,Feedwater & Svc Water Piping at Cyap
AECM-81-335, Forwards Addl Info Re Evaluations of Class IE Electrical Equipment,Per NUREG-0588
NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Inservice Inspection Intervals
PLA-3949, Provides Revised Plan & Commitments for Completion of Tasks Necessary to Meet Guidelines of GL 89-10 & Justification for Deferral of Work on Valves Associated W/Msivlcs within GL 89-10 Program.Rev 1 to Calculation EC-VALV-0503 Encl
L-86-241, Forwards Addl Info Re NUREG-0737,Item II.D.1 Re Performance Testing of Relief & Safety Valves,In Response to NRC 850714 Request
GO2-93-217, Forwards Response to Generic Ltr 89-10 & Suppls, Safety- Related Motor-Operated Valve Testing & Surveillance, Per 930809 Submittal.Summary of Activities Initiated & Completed Since Insp Rept 50-397/91-16 Also Encl
GO2-93-205, Forwards Revised Response to GL 89-10,Suppl 3, Safety Related MOV Testing & Surveillance. Response to GL 89-10, Suppl 5 & Summary of Activities Initiated & Completed Since NRC Insp Rept 50-397/91-16 Also Encl
NL-16-0724, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 1.0
DCL-15-136, Response to Requests for Information Related to the Environmental Review of the License Renewal Application - Severe Accident Mitigation Alternatives
RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the
L-2013-198, Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 4
RS-13-067, Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 1 of 13
PLA-3660, Forwards Calculations to Support Available Valve Factors,Per Commitment Made During Insp of Generic Ltr 89-10,Suppl 3 During Wk of 910923
DCL-02-045, Response to Final NRC Request for Additional Information Re Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented Intersections in Steam Generator Tubing
DCL-02-023, Gregory M. Rueger, P G& E Co., Response to NRC Request for Additional Information Regarding Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented, Intersections in Steam Generator Tubing
PNP 2024-019, Updated Final Hazards Summary Report, Revision 19
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5
ULNRC-02964, Submits Actions Taken to Comply W/Gl 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Note That Attachment Represents Licensee MOV Program to Date
L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)
NRC-94-4249, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs 940407,15,29,0505,11,16,23 & 0608. Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
BECO-LTR-96-013, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
05000282/LER-2016-001, Regarding Unanalyzed Condition Due to Non-Compliant Fire Protection Manual Operator Actions
L-2025-025, Response to Requests for Additional Information Regarding Turkey Point Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02