SBK-L-07088, Steam Generator Inservice Inspection
SBK-L-06209, Generator Tubes Plugged During Refueling Outage 11 Inservice Inspection
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
SBK-L-05186, License Amendment Request 05-08, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet
SBK-L-05172, Response to Request for Additional Information Regarding Seabrook Station Unit No. 1, Steam Generator Tube Inspection Summary for the Fall 2003 Outage
SBK-L-04040, Steam Generator Inservice Inspection
NOC-AE-04001765, License Amendment Request - Proposed Amendment to Technical Specifications for Steam Generators
HNP-04-060, Response to the Request for Additional Information Concerning the License Amendment Request for a One-Time Increase in Steam Generator Inspection Interval
NOC-AE-04001678, Response to Request for Additional Information (RAI) Regarding Proposed Amendment to Technical Specification 4.4.5.3a
HNP-03-116, Request for License Amendment Regarding Technical Specification 4.4.5.3a
NOC-AE-03001580, License Amendment Request - Proposed Amendment to Technical Specification 4.4.5.3a
RC-03-0176, Revision to License Amendment Request - LAR 02-2767 Steam Generators - One Time Exclusion on Inspection Frequency
05000267/LER-1982-046, Forwards LER 82-046/03L-0.Detailed Event Analysis Encl
RC-03-0007, License Amendment Request - LAR 02-2767 Steam Generators - One-Time Exclusion of Inspection Frequency
NOC-AE-02001375, Submittal of Information Previously Sent by Facsimile to Support Ongoing Review of Request for a Change in the Steam Generator Inservice Inspection Frequency Requirements for Unit 1
NOC-AE-02001355, Response to Request for Additional Information Re License Amendment Request - Revised Proposed Amendment to Technical Specification 4.4.5.3a, Dated 06/20/2002
NOC-AE-02001245, License Amendment Request- Proposed Amendment to Technical Specification 4.4.5.3a
0CAN129701, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/97-14 & 50-368/97-14 on 970527-0808.Corrective Actions:Administratively Declared Both OTSGs Inoperable & TS 3.0.3 Entered W/Actions Delayed as Allowed by TS 4.0.3
ULNRC-03580, Forwards 10CFR50.59 Annual Rept Summaries for 1996, Summarizing Written Safety Evaluation of Changes,Tests & Experiments Approved & Implemented for Activities at Plant
2CAN119609, Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4)
NOC-AE-000526, Submits Listed Info on Number of Tubes Plugged in Unit 1 SGs During Recently Completed 1RE08 in-service Insp
NOC-AE-000345, Submits Special Rept on SG ISI Results for Unit 2
ST-HL-AE-5396, Submits Special Rept of Plugging of SG Tubes as Result of eddy-current Testing Indications
3F0792-02, Forwards 15-day Rept of Eddy Current Insp of once-through SG Tubes on 920629
ST-HL-AE-5064, Special Rept:On 950401,thirty-two SG Tubes Containing Circumferential Indications & 14 SG Tubes Containing Axial Indications Plugged
ST-HL-AE-4602, Special Rept:On 931007,insp Resulted in Plugging of fifty- One Tubes Between Four Steam Generators.Reasons for Tube Plugging Summarized as Listed
2CAN039204, Application for Amend to License NPF-6,revising TS 4.4.5 to Allow Installation of Tube Sleeves as Alternative to Plugging Defective SG Tubes.Encl Rept 51-1212539-00 Withheld
2CAN079293, Application for Amend to License NPF-6,revising Surveillance Requirements for SG Tubing,Tech Spec 4.4.5.Details of Sleeve Qualification Discussed in Encl Rept CEN-601-P,Rev 01-P, ANO Unit 2.... Rept Withheld (Ref 10CFR2.790)
05000395/LER-1985-031, :on 851014,inservice Insp of Steam Generator B Identified 9 Out of 700 Tubes W/Greater than or Equal to 40% through-wall Indications in Area of Hot Leg Tube Sheet
05000499/LER-1997-002-01, :on 970215,Steam Generators 2A Eddy Current Insp Results Fell Into Category C-3.Caused by Stress Corrosion Cracking at tube-to-tube Support Plate.Sg Tubes Were Plugged in Four Unit 2 Steam Generators
05000368/LER-1992-010-02, :on 921125,identified That 2 of 8291 Tubes in B SG Had Not Been Inspected During Refueling Outage 2R9, Due to Human Error.Qa Will Perform Surveillance of Eddy Current Data Mgt Sys During Outage
05000213/LER-1993-008, :on 930613,determined That Analyzed ECT Data Placed SGs 2 & 4 Into C-3 Category.Total of 39 Tubes Plugged & 83 Tubes re-rolled in Four SGs
ELV-01452, Submits Special Rept 1-90-02 Re Number of Steam Generator Tubes Plugged During 1R2.One of Four Tubes Exceeded Plugging Limit & Required Plugging.Remaining Three Tubes Plugged as Precautionary Measure.No Defective Tubes Detected
3F0290-08, Forwards Special Rept 90-003 Reporting on Steam Generator Eddy Current Insp,Per Tech Spec 4.4.5.5.a.Rept Includes Number & Extent of Tubes Inspected & Location & Percent of Wall Thickness Penetration for Each Indication
05000315/LER-1997-008, :on 970404,cycle 15 Operation of SGs Outside TS Tube Degradation Acceptance Criteria Occurred.Caused by Inadquate Analysis of Cecco-5 Eddy Data in 1995.Use of Cecco-5 Probes Discontinued
L-88-469, Forwards Special Rept for Eddy Current Exam of Steam Generator Tubing During Oct 1987 for St Lucie Unit 2
SBK-L-06166, Proprietary Information to Support Response to Request for Additional Information Re License Amendment Request 05-08, Limited Inspection of Steam Generator Tube Portion within the Tubesheet
ST-HL-AE-5227, Special Rept:On 951022,completed ISI of Unit 2 Sg.Tube Plugs Visually Inspected for Evidence of Leakage.Welded Plugs Installed at Locations
05000339/LER-1993-006-02, :on 930921,discovered SG Tube Degradation Due Water Stress Corrosion Cracking Originating Outside Diameter of Tube.Removed Tubes W/Pluggable Indications
05000267/LER-1983-019-01, /01T-0:on 830606,discovered That Reactor Operated Between 5% Power & Shutdown W/O Operable Analytical Moisture Monitors on 830603.Caused by Accidental Isolation of Sample Paths to Monitors