Similar Documents at Ginna |
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Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23258A1382023-09-18018 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010 IR 05000244/20230052023-08-31031 August 2023 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report IR 05000244/20234012023-08-15015 August 2023 LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only) IR 05000244/20230022023-08-0303 August 2023 LLC - Integrated Inspection Report 05000244/2023002 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 IR 05000244/20234022023-07-19019 July 2023 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only) RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report ML23121A0482023-05-0101 May 2023 R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000244/20230012023-04-26026 April 2023 LLC - Integrated Inspection Report 05000244/2023001 ML23100A0302023-04-10010 April 2023 2023 10 CFR 50.46 Annual Report ML23114A1152023-03-29029 March 2023 Electronic Reporting of Exposure Data for 2022 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23075A0872023-03-15015 March 2023 R. E. Ginna Nuclear Power Plant - Project Manager Assignment ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000244/20220062023-03-0101 March 2023 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006) ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23060A1622023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators ML22287A0692023-02-0808 February 2023 R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request ML23010A0112023-02-0101 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000244/20223012023-01-20020 January 2023 Initial Operator Licensing Examination Report 05000244/2022301 IR 05000244/20220122023-01-12012 January 2023 LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012 ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22348A2062022-12-14014 December 2022 Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 2024-02-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000244/LER-2017-0012017-06-16016 June 2017 During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction., LER 17-001-00 for R. E. Ginna re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction 05000244/LER-2016-0012016-04-0707 April 2016 Loss of Station Auxiliary Transformer 12A resulting in automatic start of Emergency Diesel Generator A due to undervoltage signals to safeguards buses 14 and 18., LER 16-001-00 for R. E. Ginna Nuclear Power Plant Regarding Loss of Station Auxiliary Transformer 12A Resulting in Automatic Start of Emergency Diesel Generator A due to Undervoltage Signals to Safeguards Buses 14 and 18 ML0509600362004-12-17017 December 2004 Final Precursor Analysis - Ginna Grid Loop ML0429403762004-10-12012 October 2004 LER 04-S01-00 for R. E. Ginna Regarding Safeguards Event ML0202800752002-01-22022 January 2002 LER 01-S01-00 for R E Ginna Nuclear Plant Re Safeguards Event ML18142A8511978-09-14014 September 1978 LER 1978-007-00 for R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator ML18142A8761978-08-0303 August 1978 LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom ML18142A8771978-06-0606 June 1978 LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump ML18142B2141978-05-0202 May 1978 LER 1978-005-00 for R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical ML18142B2131978-03-31031 March 1978 LER 1978-004-00 for R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip ML18142B2171978-02-10010 February 1978 LER 1978-002-00 for R. E. Ginna, Power Range Low Range Trip Set Point Test ML18142B2191978-02-0808 February 1978 LER 1978-003-00 for R.E. Ginna, B Steam Generator Tube Leak ML18142B2221977-07-18018 July 1977 LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak ML18192A0761977-07-0707 July 1977 LER 1977-006-00 for R.E. Ginna, C Charging Pump Varidrive on 6/19/1977 ML18142B2281977-06-0808 June 1977 LER 1977-024-00 for R.E. Ginna, Accumulation of Borated Water Near a Valve in Safety Injection System Piping ML18142B2291977-05-27027 May 1977 LER 1976-027-03 for R.E. Ginna, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak ML18142B2351977-05-16016 May 1977 LER 1977-003-00 for R.E. Ginna, Abnormal Degradation of Steam Generator Tubes ML18142B2211977-03-31031 March 1977 LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump ML18142B2381977-01-27027 January 1977 LER 1977-01-00 for R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump ML18142B2401977-01-12012 January 1977 LER 1976-030-00 for R.E. Ginna, a Mixed Bed Demineralizer Inlet Piping Leak ML18142B2431977-01-11011 January 1977 LER 1976-029-00 for R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition ML18142B2421977-01-11011 January 1977 LER 1976-028-00 for R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work ML18142B2441977-01-0404 January 1977 LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line ML18142B2461976-12-0808 December 1976 LER 1976-026-00 for R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma ML18142B2471976-11-0909 November 1976 LER 1976-025-00 for R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent ML18142B2491976-10-22022 October 1976 LER 1976-024-00 for R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps ML18142B2521976-09-14014 September 1976 LER 1976-023-00 for R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 ML18142B2531976-08-19019 August 1976 LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods ML18142B2571976-08-19019 August 1976 LER 1976-021-00 for R. E. Ginna, Unit 1, D Bank Group 2 Rcc'S G-3 and G-11 Partially Dropped Into Core ML18142B2761976-07-19019 July 1976 LER 1976-20-00 for R.E. Ginna, a Accumulator Level Below Technical Specification Limit ML18142B2721976-07-16016 July 1976 LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor ML18142B2751976-07-16016 July 1976 LER 1976-20-00 for R.E. Ginna, Unit 1, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2741976-07-16016 July 1976 LER 1976-20-00 for R. E. Ginna, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2781976-06-21021 June 1976 R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing ML18142B2801976-06-0404 June 1976 LER 1976-016-00 for R.E. Ginna, Rod Position Deviation Channel Was Found to Be Inoperable ML18142B2821976-05-24024 May 1976 LER 1976-015-00 for R.E. Ginna, Air Ejector and Blowdown Radiation Monitors Alarmed ML18142B2841976-05-11011 May 1976 LER 1976-013-00 for R.E. Ginna, Drop of Two Control Rods ML18142B2851976-05-10010 May 1976 LER 1976-014-00 for R.E. Ginna, N44 Power Range Detector High Voltage Power Supply Failure ML18142A9761976-04-23023 April 1976 LER 1976-012-00 for R.E. Ginna, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing ML18142A9791976-03-22022 March 1976 LER 1976-010-00 for R. E. Ginna, Containment Purge Supply Value Excessive Leakage During Testing ML18142A9781976-03-19019 March 1976 LER 1976-011-00 for R.E. Ginna, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System ML18142A9801976-03-12012 March 1976 LER 1978-009-00 for R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay ML18142A9811976-03-11011 March 1976 LER 1976-008-00 for R. E. Ginna, Abnormal Degradation of Steam Generator Tubes ML18142A9831976-02-28028 February 1976 LER 1976-007-00 for R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch ML18143A4971976-02-19019 February 1976 LER 1976-006-00 for R.E. Ginna, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 ML18142B8941976-02-0606 February 1976 LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage ML18142B8931976-02-0606 February 1976 LER 1976-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage ML18142B8951976-01-26026 January 1976 LER 1975-013-00 for R. E. Ginna, 30 Day, B Steam Generator Tube Degradation ML18142B8961976-01-0808 January 1976 LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak ML18142B8971976-01-0808 January 1976 LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak 2017-06-16
[Table view] |
Text
U,S, NUCLEAR REGULATORY Cob .<<<<SSION DOCKET NUMBER NRC FORM 196 I2 76 I FILE NUMBER rQRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL FROM: DATE OF DOCUMENT TO:
<<
Rochester Gas 6 Elec Corp 7/18/77 Mr- James P. OIReilly Rochester, Ni Yi DATE RECEIVED L. D White, Jr. 7/21/77 NUMBER OF COPIES RECEIVED
~~
TTE R QNOTORIZED PROP INPUT FORM Cl ORIGINAL LASS I F I E D Y
DESCRIPTION ENCLOSURE License'e Event Report (RO 50-244/77-08) on 7/5/77 concerning the Air Ejector and Blowdown rad2Iation monitors alarming ~ ~ . ~ ~ .
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PLANT NAME:
Ginna Unit No ~ (1-P) (2-P)
RJL 7/21/77 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION/INFORMATION C.
INTERNAL D IST RI BUTION EXTERNAL DISTRIBUTION CONTR NUMBER Q2$ 3 ACRS 16 SENT AS AT NRC FORM 196 (2-76)
T r
~ I1 ~ DAI ~ bO i/i Ji'"II.'"(i'oili?Il7Tin67 ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON O. WVHITE. JR, TCCCo><DNC YIrc pRcsIDENT AIICA rDDC VIII 546.2700 July 18, 1977 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement "'igyggtIttafff 00cket Fltjn Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Subj ect. Reportable Occurrence 77-08 (14-day report), "B" Steam Generator tube leak R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. O'Reilly:
In accordance with Technical Specifications, Article 6.9.2.a, the attached report of Reportable Occurrence 77-08, 14-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.
Very. truly yours, L. D. White, Jr.
Attachment cc: Dr. Ernst Volgenau (40)
Mr. William G. McDonald (3)
COIAIAI 77gp2p233
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e CONTROL BLOCK LICENSEE I LER 77-08/1T LICENSEE EVENT REPORTS fPlEASE PRINT ALL REQUIRED IMFORMAT(OM)
LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE QO1j N Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 7 89
~
14 15 25 26 30 3'I 32 REPORT REPORT CATEGORY ,DOCKET NUMBER EVENT DATE IQO1]ooN1 0 5 0 0 2 4 4 0 7 0 5 7 7 0 7 REPORT DATE 1 8 7 7 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION Qpg During normal operations the Air Ejector and blowdown radiation monitors alarmed.
7 8 9 80 Analysis of the B Steam Generator blowdown verified Iodine activity from a calculated I
7 89 80 t00~j leak rate of 0.006 gpm. The leaking tube was located with a hydrostatic test, and 7 8 9 80 Eddy Current testing was erformed to determine if a attern of degradation existed.
7 8 9 80 IOOI About 300 tubes were examined which included tubes in (cont'd. on attached sheet) 7 8 9 PRI4IE 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLFM MANUFACTURER VOLATION
[887I ~CB E II T E X C II ~N W 1 2 0 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION l00m The failure of the tube R45C54 and the defect indications in tubes R44CSS, 56, 57 and 7 8 9 80
[os 58 are postulated to be caused by stress corrosion cracking from the inside surface of 7 8 9
~10 the tubes. These inside diameter cracks are theorized to be (cont'd. on attached sheet)80 7 89 80 FACILITY METHOD OF STATUS ee powER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 7
I111j 8 9 E ~io 10 o NA c Rad monitors and sample analysis 12 13 44 45 46 80 FORM OF ACTIVITY COATENT 7
KO'~j8 RELEASED 8
OF RELEASE L~l 10 11 AMOUNT OF ACTIVITY NA 44 45 NA LOCATION OF RELEASE
'ERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~18 ~OO O E NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION
~4 ~oo o NA 7 89 11 12 80 OFFSITE CONSEQUENCES
@~75 NA ciao 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g p, 7 89 10 80 PUBLICITY
[i<~] News release.
7 89 80 ADDITIONAL FACTORS NA 7 89 80 7 89 80 A ~ E4 Curtis III PHDNE.7 1 6 546-2 700, ext ~ 22 63 eeI-eev
Licensee Event Report Seportable Occurrence SO-244/77-08 Event Descri tion (cont'd.)
the area of the leaking tube and other selected areas with previous indications.
These examinations revealed four additional tubes, in the area of the leaking tube, with similar (ID) indications. These four tubes and the leaking tube were explosively plugged. (Reportable Occurrence 77-08, 14-day).
Cause Descri tion (cont'd.)
caused by a dent at:he tube to tube sheet interface which induces stress into the tube wall resulting in cracking. There are not any chemical species postu-lated to be involved in this cracking phenomena due to the purity of the primary system's water, which flows through the tubes.
Corrective action taken included eddy current examination of surrounding tubes and tubes in areas where previous inservice inspections had revealed small defect indications. There were no other tubes identified of those examined which exhibited further degradation. Therefore, the failed tube and four others with similar (ID) indications were plugged. Further investigation is continuing with Westinghouse and RQ&E personnel involvement studying the generic PWR tube failure problem. At the next refueling outage, an inservice inspection of the steam generator tubes will include tubes in the area of this failure.
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