ASME Code Case N-640# QUERY8f0f8fd61a345457b855aed78b5a5015
ASME Code Case N-640 Beaver Valley
ASME Code Case N-640# QUERY0f71c026159baec76ba6f637c7ff7eb6
ASME Code Case N-640# QUERYc74bd40cf7ff23fb417e9f5f8e977385
ASME Code Case N-640 Calvert Cliffs
ASME Code Case N-640# QUERY9ec7a167bd458e55933bfe43f920a356
ASME Code Case N-640# QUERY9c01c0cdf786b2eeded093b3afa2688b
ASME Code Case N-640 FitzPatrick
ASME Code Case N-640# QUERYdb73d7b9604e56c96cbbed54aa2fade7
ASME Code Case N-640# QUERY94cfae709af2729a6f68782ed3014737
ASME Code Case N-640 Ginna
ASME Code Case N-640# QUERY6ba9c34f1eb9a3df6f4daf2625f797e7
ASME Code Case N-640 Hope Creek
ASME Code Case N-640# QUERYed743b2d530263ff64bfe8939b77d937
ASME Code Case N-640# QUERY53f38942d9ffa09a6f72ec78df268fa1
ASME Code Case N-640 Limerick
ASME Code Case N-640# QUERY29a2b28a762a42009f688d9b8a7af44f
ASME Code Case N-640 Millstone
ASME Code Case N-640# QUERY38db51bc41446c24c9f4c01ff50a9418
ASME Code Case N-640# QUERY81247a57cf907486d32badd538cc5116
ASME Code Case N-640 Nine Mile Point
ASME Code Case N-640# QUERY66434ad8240b99a21808491fae18fbac
ASME Code Case N-640# QUERYe1f029c466225370b7107c9d766dd5bd
ASME Code Case N-640 Peach Bottom
ASME Code Case N-640# QUERYd4ac345358ed6e939838606bb00bdc2e
ASME Code Case N-640# QUERYa4ffb5683704a128230eade55f37393f
ASME Code Case N-640 Salem
ASME Code Case N-640# QUERY85c68ba70c0d83a749e55c66cc494670
ASME Code Case N-640 Seabrook
ASME Code Case N-640# QUERYb23e304f19461778ed8f9edcaab162a6
ASME Code Case N-640# QUERYe557111efe1e869a2cf94fd7f2227a41
ASME Code Case N-640 Susquehanna
ASME Code Case N-640# QUERYf3f0d6b5c2d4b74264d93a1edf2b4baa
ASME Code Case N-640# QUERY3247ea705da99f725cf64abdeac7017d
NRC Region 1 false
ASME Code Case N-640# QUERY7a67bed0767cfcf0d82172f65aac0556
ASME Code Case N-640 Haddam Neck
ASME Code Case N-640# QUERYf6b9530d7bd07953f6a664cd69db79d9
ASME Code Case N-640# QUERYd473625a2ada0bf5258b0cf8352d3fb9
ASME Code Case N-640 Indian Point
ASME Code Case N-640# QUERYb5caca2f388fb09362ac2b071ecc68b6
ASME Code Case N-640 Maine Yankee
ASME Code Case N-640# QUERY0abe6ee29c1374f5502b752cd35986fa
ASME Code Case N-640 Oyster Creek
ASME Code Case N-640# QUERYaddd9f91244aa8b9bfd047de4f989bac
ASME Code Case N-640 Pilgrim
ASME Code Case N-640# QUERY5a763056cf2b93138fbb71c61f5b5d1d
ASME Code Case N-640# QUERY8c1bfac667e8c6dd25a71caff3659b12
ASME Code Case N-640 Saxton
ASME Code Case N-640# QUERY7e753b3c3927a633fae08acc389fbcd8
ASME Code Case N-640# QUERY4a5fa4efc7d40a4e08e1a3e8ebec4415
ASME Code Case N-640 Shippingport
ASME Code Case N-640# QUERYda89face434ab382d374f1ca65e27be2
ASME Code Case N-640# QUERY5cc3331619ab15be80de144caa197bfe
ASME Code Case N-640 Shoreham
ASME Code Case N-640 Three Mile Island
ASME Code Case N-640 Vermont Yankee
ASME Code Case N-640# QUERYfd89f60f94685074b5eac68bf1bf30d3
ASME Code Case N-640# QUERYc2ba2043c40d46f5dfd1ac93ee2bd75c
ASME Code Case N-640 Yankee Rowe
ASME Code Case N-640# QUERYbb7d09b5c343f70df583f41f9ad8022d
ASME Code Case N-640 Zion
ASME Code Case N-640# QUERY16a4c682a84d58849b3abedecff79aa7
NRC Region 1 true
ASME Code Case N-640# QUERYa3013f81b2c3556f952fc20ebfb722f7
ASME Code Case N-640 Browns Ferry
ASME Code Case N-640# QUERYd65ac2e60fc6679887dad8e7db0050c7
ASME Code Case N-640# QUERYe408bf237bfe0c9e8caabf87eb6d221c
ASME Code Case N-640 Brunswick
ASME Code Case N-640# QUERY93fe92db4fed11418bba31e13a3b79e8
ASME Code Case N-640# QUERYa7016f4efbb2af7ccfc83003ce4559ea
ASME Code Case N-640 Catawba
ASME Code Case N-640# QUERY0d0a330495e5c9e5136855c7cceafc53
ASME Code Case N-640# QUERYa70f05a3c91b2c13ea97771946ae0017
ASME Code Case N-640 Clinch River
ASME Code Case N-640# QUERY6c03710de3e6899ac516d73d58bd4cd9
ASME Code Case N-640# QUERYaa5d189671ad6dbe9fb90b2567885e7e
ASME Code Case N-640 Farley
ASME Code Case N-640# QUERYe62ef41ab82fdfa538cc2f6272b995b1
ASME Code Case N-640 Harris
ASME Code Case N-640# QUERY12ed08babda649116352b04a5170d43a
ASME Code Case N-640# QUERY9978633906dfe56b8d0eb3a3b54e9802
ASME Code Case N-640 Hatch
ASME Code Case N-640# QUERY2ae8bd33bbf39fc2de893970d9fcd41e
ASME Code Case N-640# QUERY934d41bb3af3ea28de592443a1a2e650
ASME Code Case N-640 Lee
ASME Code Case N-640# QUERYb467f4f68570342d571d15cadd2df4b9
ASME Code Case N-640# QUERY9d37b0e0579dc2e486beb1095af342ac
ASME Code Case N-640 McGuire
ASME Code Case N-640# QUERY90c24d921982db009c0cc3428e7a55a4
ASME Code Case N-640# QUERY09690b90aefe3d589cb6e67e65c6b42f
ASME Code Case N-640 North Anna
ASME Code Case N-640# QUERY043ad3b22f723ec8aa2dea8057125f8a
ASME Code Case N-640# QUERYbf820d54abc49cb9c5b47e41cd592bd0
ASME Code Case N-640 Oconee
ASME Code Case N-640# QUERY78c96375cd70970fe0835ef9bc8c0ed5
ASME Code Case N-640 Robinson
ASME Code Case N-640# QUERY97e0eff622a1e8134bd167bacc842c6f
ASME Code Case N-640# QUERY9ac11cf9586690c7037574da53bc974f
ASME Code Case N-640 Saint Lucie
ASME Code Case N-640# QUERYb14f8f8ff67802f59ef712c58e99ad16
ASME Code Case N-640# QUERY638501ef3a4cddfe61ab4e1890514259
ASME Code Case N-640 Sequoyah
ASME Code Case N-640# QUERYc8214fefeee847381e68aaee04997fa6
ASME Code Case N-640 Summer
ASME Code Case N-640# QUERY5c1dadd15aff2c6da9abc67556902054
ASME Code Case N-640# QUERY6dc78fbee9d06b730819cd8584048090
ASME Code Case N-640 Surry
ASME Code Case N-640# QUERY38f1d54c307c689df944f9da61442b98
ASME Code Case N-640# QUERY087b10c15610e59f23f4860fbb3bd45d
ASME Code Case N-640 Turkey Point
ASME Code Case N-640# QUERYc3facfd848f71a3a272b8f1f0b7164c4
ASME Code Case N-640# QUERY5ddd78c646f3c4fda4319078cd26f926
ASME Code Case N-640 Vogtle
ASME Code Case N-640# QUERY0cca1b01a42df152eb7bf70cd98ef7ac
ASME Code Case N-640# QUERY66f5b997a7c333dc9853faa94868c03b
ASME Code Case N-640 Watts Bar
ASME Code Case N-640# QUERYaf7c77f5b6c3ea917c7891b005a6e623
ASME Code Case N-640# QUERY61ccc6185d0b408f7eb839f292f4fc81
NRC Region 2 false
ASME Code Case N-640# QUERYef2ed89eccc51cc609623ec1f2ae0e81
ASME Code Case N-640 Crystal River
ASME Code Case N-640# QUERY4dccdcccecea4d93840a0276e2ab6f43
ASME Code Case N-640 Parr
ASME Code Case N-640# QUERY31413f1b0eed72f1a02e268b3a5a1a86
NRC Region 2 true
ASME Code Case N-640# QUERY03a4ee5432c9daa6cecac06e7884f24d
ASME Code Case N-640 Braidwood
ASME Code Case N-640# QUERYa67f500337bfe961fcba31d293aa87c7
ASME Code Case N-640# QUERYe880344914b92a4caa4be72be3edafcf
ASME Code Case N-640 Byron
ASME Code Case N-640# QUERYfe015cc0bc52d7e02923390d6849d450
ASME Code Case N-640# QUERY1ce792cecce23e7a36ecb0673c74fafa
ASME Code Case N-640 Clinton
ASME Code Case N-640 Cook
ASME Code Case N-640# QUERY590dde3d82b26c557f19cbdd22cc6ed1
ASME Code Case N-640 Davis Besse
ASME Code Case N-640# QUERY95a0ea63b80a85f7ba1b4c39cfdfefce
ASME Code Case N-640# QUERY7aa97d555ed1466b706d4f9e141d2016
ASME Code Case N-640 Dresden
ASME Code Case N-640# QUERY5af840de78edce7f6b51f41c883a339a
ASME Code Case N-640# QUERY2ba9f5c0a6d1cae34322368b2dd42aec
ASME Code Case N-640 Fermi
ASME Code Case N-640# QUERY3d572ac049c9fe9c810b9d79d94275ae
ASME Code Case N-640 LaSalle
ASME Code Case N-640# QUERY3a81aef1bb7592c03a231a03221c20ff
ASME Code Case N-640# QUERY3a2b26b8dcaf1c674ea15ef03eea13f3
ASME Code Case N-640 Monticello
ASME Code Case N-640# QUERYf808a206cd293b5769dc9b96926071ae
ASME Code Case N-640 Palisades
ASME Code Case N-640# QUERY6249f152706fde9bda26d5bda7983a4a
ASME Code Case N-640 Perry
ASME Code Case N-640# QUERYb45f5811b0e418dccd25d14252c6862e
ASME Code Case N-640# QUERYcbe403b4585f5b188bf6c6cb2b94b4a0
ASME Code Case N-640 Point Beach
ASME Code Case N-640# QUERY9a28727db8c1966b9da10755b9b294de
ASME Code Case N-640# QUERY1f1737cf4c9d3ad65d7487bc2fdb111d
ASME Code Case N-640 Prairie Island
ASME Code Case N-640# QUERY57f888df7268f81b87e70a5d9e2bc1a4
ASME Code Case N-640# QUERY8c8c2f01ed5edbc244a783baa8861f36
NRC Region 3 false
ASME Code Case N-640 Big Rock Point
ASME Code Case N-640 Duane Arnold
ASME Code Case N-640# QUERY78c5578fd2c8b21addf84b3d31a8d606
ASME Code Case N-640 Elk River
ASME Code Case N-640# QUERYa73240a4ef70fa94da284bc42e00a33e
ASME Code Case N-640# QUERY470eeffc125f87d288664ea5b3d7aeef
ASME Code Case N-640 Kewaunee
ASME Code Case N-640 La Crosse
ASME Code Case N-640# QUERY2b4b7566c2e1aa82978b23efb5d4601c
ASME Code Case N-640# QUERY89954af5ef19f71316289aa13b7c93da
NRC Region 3 true
ASME Code Case N-640# QUERY4b875cd2f5745a1db5699c9bf7b8b28c
ASME Code Case N-640 Arkansas Nuclear
ASME Code Case N-640# QUERY38433e3f2f282f4a4f9c4a3ea3738c78
ASME Code Case N-640# QUERY111cf005c4797a6e0be1ab22d5ee56ff
ASME Code Case N-640 Callaway
ASME Code Case N-640# QUERYb325f2a8bcc510b96970fc7d4d116093
ASME Code Case N-640 Columbia
ASME Code Case N-640# QUERY504b4524b9eec2dc8bf883aa3e1dcd6e
ASME Code Case N-640# QUERYb764ba73a4afc270debd758244d4af43
ASME Code Case N-640 Comanche Peak
ASME Code Case N-640# QUERY9bb6e7019a6215757fc1ae43e2d986b9
ASME Code Case N-640# QUERYc15f37c9fafa18e165f3d5308a3a8421
ASME Code Case N-640 Cooper
ASME Code Case N-640 Diablo Canyon
ASME Code Case N-640# QUERYdb8c6302ee7b8b38cd589ddf09047373
ASME Code Case N-640# QUERYe847928f0cb9a003e59be5b4fe6cd1d7
ASME Code Case N-640 Grand Gulf
ASME Code Case N-640# QUERY987b20abdcf3a5373c255e80165d1c3d
ASME Code Case N-640# QUERY2c12dc671ca4e1a393eaf8c85410380c
ASME Code Case N-640 Kemmerer
ASME Code Case N-640# QUERYfef94325d7d209630a4ce2e7e394cae7
ASME Code Case N-640 Palo Verde
ASME Code Case N-640# QUERY04de6ce35e48d84f8183317c8d0a4a1f
ASME Code Case N-640 Quad Cities
ASME Code Case N-640# QUERYd49ac2a3b1b0943ef0ebbd420f24045c
ASME Code Case N-640 River Bend
ASME Code Case N-640# QUERY4cb46ecd9de586c4f1001c9b6d12ad4c
ASME Code Case N-640# QUERYcb5dcaf9bf07e9dcff923e6c8e9e3bab
ASME Code Case N-640 South Texas
ASME Code Case N-640# QUERY5ee4ebbfa322bfebbc2d04022fde6dac
ASME Code Case N-640# QUERY4ca2fb7473a18fb767e41a39d3f21861
ASME Code Case N-640 Sundesert
ASME Code Case N-640# QUERYa5aff0ee34302b97970e0be3eb3aaade
ASME Code Case N-640 Victoria
ASME Code Case N-640# QUERY6992e51ce9c2f8c3be4a6a13b5fd7dbd
ASME Code Case N-640# QUERYca7e8579196bcb3829b6028c19f91cc1
ASME Code Case N-640 Waterford
ASME Code Case N-640# QUERY228f9eed01e901d4c66ee917ca0cae35
ASME Code Case N-640# QUERY2086d642a00c83c4e776fa87ee9af9b6
ASME Code Case N-640 Wolf Creek
ASME Code Case N-640# QUERYb2fbd19abb0cbc7aad5c1bc4c9cbd399
ASME Code Case N-640# QUERY8383b4b93c91e69ee9b9325a77dbc87a
NRC Region 4 false
ASME Code Case N-640 Fort Calhoun
ASME Code Case N-640# QUERY794a383c35f3b2a9e572b3cfe5548d48
ASME Code Case N-640 Fort Saint Vrain
ASME Code Case N-640# QUERY31f47915e197916a842e77caef9ad1bd
ASME Code Case N-640# QUERY32b52ace3e2f8be97e8b5b2f26a463d0
ASME Code Case N-640 Hallam
ASME Code Case N-640# QUERY361c528c9b83bae1bc63bf1239229999
ASME Code Case N-640# QUERY54907603927ad578c37debe6fbdb6e2e
ASME Code Case N-640 Humboldt Bay
ASME Code Case N-640# QUERY6c1dc7a906e533ef86dc59010c3518ad
ASME Code Case N-640# QUERYa0c9af036fd9d9ac5b8c5dcd4a472813
ASME Code Case N-640 Rancho Seco
ASME Code Case N-640# QUERY8cc434d5e7e452395db1570be0f199a7
ASME Code Case N-640 San Onofre
ASME Code Case N-640# QUERYf1eaa2ec2f9be1c593ff2a473bf7a22b
ASME Code Case N-640# QUERYb4ae370081a09e0ff97a6a212827080f
ASME Code Case N-640 Trojan
ASME Code Case N-640# QUERY4cc66abc255f34286770ecd1d688e400
NRC Region 4 true
ASME Code Case N-640# QUERY3f48e2e2d298162fc4e22365ef7b7e59
L-17-111, License Amendment Request to Modify Technical Specifications 4.2.1 and 5.6.3 and a 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 9
RIS 2004-04, Use of Code Cases N-588, N-640, and N-641 in Developing Pressure-Temperature Operating Limits
RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application
HNP-15-046, Transmittal of Technical Specifications Bases
NLS2015040, Technical Specification Bases Changes
L-15-026, License Amendment Request to Steam Generator Technical Specifications
CNL-14-144, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-494)
CNS-15-007, License Amendment Request (LAR) for Measurement Uncertainty Recapture (MUR) Power Uprate - Response to NRC Requests for Additional Information (Rals)
BSEP 14-0121, Completion of Activities Required for Entry Into the Period of Extended Operation
L-14-289, Pressure and Temperature Limits Report. Revision 2
CNL-14-065, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-491)
L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report
NL-14-0639, Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report
BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill
L-13-360, Pressure and Temperature Limits Report Revision
NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
HNP-12-130, Transmittal of Technical Specifications Bases
L-12-324, Reply to Supplemental Request for Additional Information for the Review of License Renewal Application (TAC No.ME4640) and License Renewal Application Amendment No. 33
L-12-271, License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions
L-12-077, Pressure and Temperature Limits Report Revision
L-11-319, Pressure and Temperature Limits Report
BSEP 11-0093, Response to Request for Additional Information Regarding Reactor Pressure Vessel Shell-to-Flange Indication Analytical Evaluation
NLS2011015, License Amendment Request to Revise Technical Specification Pressure/Temperature Limit Curves and Surveillance Requirements
HNP-11-001, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate
L-11-116, Pressure and Temperature Limits Report
LIC-11-0041, Transmittal of Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-11-085, Regarding the Submittal of the Unapproved Pressure and Temperature Limits Report
BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System
NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems
BVY 10-071, Technical Specifications Proposed Change No. 293 Revised Reactor Vessel Pressure-Temperature Limitation Curves
LR-N10-0111, Response to Request for Additional Information March 22, 2010, Related to Section 4 of License Renewal Application
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
L-08-327, Pressure and Temperature Limits Report, Revision 3
LIC-08-0071, Transmittal of Fort Calhoun, Unit 1, Reactor Coolant System Pressure and Temperature Limits Report, Revision 4
LIC-08-0013, Transmittal of Editorial Corrections to the Pressure Temperature Limits Report (PTLR)
L-08-060, License Renewal Application Amendment 1: Revision to Reactor Vessel Integrity Aging Management Program Information and Details of Reactor Vessel Surveillance Capsule Withdrawal Schedule Information
PLA-6277, Follow-up to Request for Additional Information for the Review of the License Renewal Application (LRA) Section 4.1.3
L-07-087, Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report
PLA-6222, Application for Renewed Operating Licenses Numbers NPF-14 and NPF-22, Requests for Additional Information (RAI 4.1.3)
BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)
NL-07-008, Proposed Changes to Indian Point, Unit 3 Technical Specifications Regarding Updated Pressure-Temperature and Low Temperature Overpressure Protection System Limits
LIC-06-0138, Transmittal of Revision 3 of Fort Calhoun Station, Unit No. 1 (Fcs), Pressure Temperature Limits Report (PTLR)
L-06-131, Core Operating Limits Report, COLR 18-1 Pressure and Temperature Limits Report, Revision 2
L-06-119, Supplement to License Amendment Request Nos. 324 and 196, Steam Generator Tube Integrity
L-06-088, Supplement to License Amendment Request Nos. 324 & 196 Steam Generator Tube Integrity
CNRO-2006-00009, Request for Alternative W3-R&R-005, Proposed Alternative to ASME Requirements for Evaluating Postulated Flaw Remnants
L-19-102, Submittal of Pressure and Temperature Limits Report Revision
RA-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits
RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 2
L-05-144, License Amendment Request Nos. 324 and 196 Re Steam Generator Tube Integrity
LIC-05-0081, Transmittal of Revision 1 of Fort Calhoun Station, Unit, Pressure Temperature Limits Report (PTLR)
NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval
NL-05-1159, Revision to the Pressure Temperature Limits Report
NL-05-0834, Revision to the Pressure Temperature Limits Report (PTLR)
L-05-063, Pressure and Temperature Limits Reports, Revision 1
NRC-05-0011, Proposed License Amendment Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10
NRC 2003-0018, Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves for Pbnp Units 1 & 2
BSEP 04-0160, Submittal of Technical Specification Bases Change
RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits
PLA-5811, Proposed Amendment No. 235 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-temperature (P-T) Limits PLA-5811
RNP-RA/04-0098, Request for Technical Specifications Change to Reactor Coolant System Pressure and Temperature Limits
BSEP 04-0065, Units, 1 and 2 - Submittal of Technical Specification Bases Changes
W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years
NL-04-0134, Request to Revise Technical Specifications to Relocate the Cold Overpressure Protection System Arming Temperature
2CAN040405, License Amendment Request Technical Specification Change Request for Modification of ANO-2 RCS
LR-N04-0136, Request for Change to Technical Specifications Pressure/Temperature Limits
NL-03-2177, Request to Revise Technical Specifications and Pressure and Temperature Limits Report
NLS2004005, License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3
L-13-359, End-of-Life Moderator Temperature Coefficient Testing Revision
L-03-151, Original Issuance of the Pressure and Temperature Limits Report
LIC-03-0124, Transmittal of Fort Calhoun Station (FCS) Pressure Temperature Limits Report (Ptlr), Revision 0
NG-03-0608, Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center
BSEP-03-0126, Submittal of TS Bases Changes for Revision 30 & 29
NG-03-0577, Evaluation of Indication in Dollar Weld HCC-B002
BSEP 03-0062, Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50
NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years
NG-03-0304, Revision of Technical Specification Change Request (TSCR-059A): Update to Reactor Coolant System Pressure and Temperature Limit Curves.
LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request
NG-03-0123, Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.'
RS-03-010, Supporting Documentation for Amendment to Technical Specifications Section 3.4.11, RCS Pressure and Temperature (P/T) Limits. Attachment 4, Table of Contents - Appendix F
LR-N02-0406, Request for Change to Reactor Material Surveillance Program Hope Creek Generating Station
L-02-112, Supplement to License Amendment Request Nos. 295 and 167
L-02-094, Technical Specifications Bases Change Submittal
LIC-02-0021, Response to Request for Additional Information: P-T Curve License Amendment Request
NL-02-006, Response to Request for Additional Information Indian Point 2 License Amendment Request for Reactor Coolant System Heatup and Cooldown Limitation Curves
RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System
L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits
RC-99-0201, Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl
RC-99-0154, Application for Amend to License NPF-12,revising Heatup & Cooldown Curves Located in TS Section 3/4.4.9.Requests Supersedes 990218 Application for Amend in Entirety.Rev 1 to WCAP-15102 Encl
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 5
L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement
L-20-059, License Amendment Request to Extend License Expiration Date by Recapturing Low-Power Testing Time
RS-18-105, License Amendment Request to Recapture Low-Power Testing Time
NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
RC-05-0090, License Amendment Request Re Reactor Coolant System - Heatup/Cooldown Curves
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
L-18-030, WCAP-18102-NP, Rev 1, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation
L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction
L-17-292, Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule
BW150112, Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7
CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (MUR) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations
BW140044, Pressure and Temperature Limits Reports (Ptlrs), Revision 7 and Braidwood Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision
BW140001, Pressure and Temperature Limits Reports (Ptlrs)
TMI-12-183, Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial RT NDT Values for Linde 80 Welds
L-09-141, Application to Permit Operation with ASTRUM Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology
05000266/LER-2007-008, For Point Beach, Unit 1, Non-Conservative Low Temperature Overpressure Protection System Basis
BW070019, Pressure and Temperature Limits Reports (Ptlrs), Revision 4
NUREG-1916 Volume 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
BSEP 05-0148, Revised License Renewal Commitment List
RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures for
BSEP 05-0097, Clarification of Responses to Requests for Additional Information - License Renewal
L-MT-05-052, Monticello. Response to Request for Additional Information and Submittal of Additional Information in Support of the Plant License Renewal Application
NRC 2004-0111, License Renewal Application Response to Request for Additional Information
NRC 2004-0085, License Renewal Application Revised Information
B18556, Technical Specifications Change Requests 2-21-01 and 3-18-01 Re Relocation of Selected Technical Specifications Related to the Reactor Coolant System and Plant Systems
NL-03-094, Proposed Exemption Request from Requirements of 10 CFR Part 50, Section 50.60 & Appendix G
RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits
L-21-190, Request for an Amendment to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
BVY 06-001, Technical Specification Proposed Change No. 263 - Supplement No. 44 Extended Power Uprate - Revised License and Technical Specifications
L-MT-05-089, Documentation of Responses to Aging Management Program and Aging Management Review Audits for the Monticello License Renewal Application