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| * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 30, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 SPECIAL REPORT 90-4 May 30, 1990 This Special Report addresses the Steam Generator tubes plugged during the current fifth refueling outage. This report is submitted pursuant to the requirements of Technical Specification Surveillance 4.4.6.5.a.
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| This report is required within fifteen (15) days of completion of tube plugging.
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| MJP:pc Distribution 9006050288 900530 ADOCK 05000277 ,.-F'DC The Energy People Sincerely yours, L. K. Miller General Manager -Salem Operations 95-2189 (10M) 12-89
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| REPORT NUMBER IDENTIFICATION: | | SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 SPECIAL REPORT 90-4 This Special Report addresses the Steam Generator tubes plugged during the current fifth refueling outage. This report is submitted pursuant to the requirements of Technical Specification Surveillance 4.4.6.5.a. This report is required within fifteen (15) days of completion of tube plugging. |
| Salem Generating Station -Unit 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: | | Sincerely yours, |
| * Steam Generator Tubes Plugged During the Fifth Refueling Outage Event Date: Report Date: 5116190 5130190 This report was initiated by Incident Report Nos. 90-277 and 90-331. CONDITIONS PRIOR TO OCCURRENCE:
| | #~ |
| Mode 6 -Refueling Outage DESCRIPTION OF OCCURRENCE: | | L. K. Miller General Manager - |
| | Salem Operations MJP:pc Distribution 9006050288 900530 |
| | ~DR ADOCK 05000277 |
| | ,.- F'DC The Energy People 95-2189 (10M) 12-89 |
| | |
| | SPECI~L REPORT NUMBER ~4 P~ANT IDENTIFICATION: |
| | Salem Generating Station - Unit 2 |
| | * Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: |
| | Steam Generator Tubes Plugged During the Fifth Refueling Outage Event Date: 5116190 Report Date: 5130190 This report was initiated by Incident Report Nos. 90-277 and 90-331. |
| | CONDITIONS PRIOR TO OCCURRENCE: |
| | Mode 6 - Refueling Outage DESCRIPTION OF OCCURRENCE: |
| On May 16, 1990, Steam Generator (SIG) tube plugging was completed. | | On May 16, 1990, Steam Generator (SIG) tube plugging was completed. |
| Tubes were plugged either due to exceeding the percent degradation of 40% (as per Technical Specification 4.4.6.4.6) or were between 30% and 40% as a conservative measure (as determined by ISI). The following are the tubes plugged: No. 21 SIG No. 22 SIG Row Column % Degradation Row Column % Degradation 32 61 53 31 78 37 32 63 41 34 59 42 32 65 41 34 63 48 33 45 44 39 44 45 33 48 38 34 59 46 39 43 55 40 56 36 No. 24 SIG No. 23 SIG Row Column % Degradation Row Column % Degradation 33 38 45 4 38 56 33 56 42 14 62 47 34 79 39 25 10 46 35 77 40 32 34 37 42 44 73 34 49 45 42 45 62 38 43 48 42 63 32 40 40 61 43 32 33 40 47 59 43 36 DRI* 40 49 44 43 45 39 40 52 52 43. 61 49 40 57 35 41 32 37 43 64 84 * -Distorted Roll Transition 43 62 84 Indication 45 36 37 t?NIT SPECIAL REPORT *-4 | | Tubes were plugged either due to exceeding the percent degradation of |
| * During the eddy current inspection of No. 23 S/G, the inspectors discovered that a tube thought to be plugged was not. As indicated in the above list the No. 23 SIG tube associated with Row 25 Column 10 was plugged this outage. However, during the second refueling outage, this same tube was identified as being plugged. APPARENT CAUSE OF OCCURRENCE: | | ~ 40% (as per Technical Specification 4.4.6.4.6) or were between 30% |
| The root cause of the tube degradation has been attributed to normal wear caused by erosion/corrosion factors. The root cause of the wrong tube being plugged, in No. 23 S/G, has been attributed to personnel error associated with procedural noncompliance. | | and 40% as a conservative measure (as determined by ISI). The following are the tubes plugged: |
| Investigation revealed that the No. 23 SIG tube associated with Row 10 Column 25 was in fact plugged during the second refueling outage and not the one associated with Row 25 Column 10. Apparently, the robotics operator reversed the Row and Column for this one tube, thereby marking the wrong tube to be plugged. The S/G tube plugging procedure requires a Quality Assurance inspection to verify that the correct tube is marked prior to plugging. | | No. 21 SIG No. 22 SIG Row Column % Degradation Row Column % Degradation 32 61 53 31 78 37 32 63 41 34 59 42 32 65 41 34 63 48 33 45 44 39 44 45 33 48 38 34 59 46 39 43 55 40 56 36 No. 24 SIG No. 23 SIG Row Column % Degradation Row Column % Degradation 33 38 45 4 38 56 33 56 42 14 62 47 34 79 39 25 10 46 35 77 40 32 34 37 42 44 73 34 49 45 42 45 62 38 43 48 42 63 32 40 40 61 43 32 33 40 47 59 43 36 DRI* 40 49 44 43 45 39 40 52 52 |
| This was not completed for this tube. On December 6, 1984, a QA inspection was performed for tubes which were to be plugged due to tube wear caused by vibration of the tube lane blocking device. On December 12, 1984, another tube was identified to be plugged as determined from eddy current inspections. | | : 43. 61 49 40 57 35 41 32 37 43 64 84 |
| This tube is the one for Row 25 Column 10 in No. 23 S/G. This tube was never verified by QA as being correctly marked, subsequently, the wrong tube was marked and eventually plugged. A second tube marking and plugging procedure had not been initiated; the original procedure | | * - Distorted Roll Transition 43 62 84 Indication 45 36 37 |
| {with its signoffs} | | |
| was used for plugging the December 12, 1984 tube. The procedure for identifying those S/G tubes required to be plugged during the second refueling outage involved the use of remotely controlled robotics equipped with TV cameras. Tubes to be plugged are marked with a zyglo penetrant mixed with a Nissan marker. A Quality Assurance signoff is performed verifying that the correct S/G tube had been marked. Additionally, both Inservice Inspection Services {ISI) and Quality Assurance personnel viewed a live remote showing of the tube{s) plugged after which they sign the procedure certifying that the tube marked has been appropriately plugged. This second inspection | | t?NIT ,~ SPECIAL REPORT * - 4 |
| {performed by QA and ISI inspectors) is not a verification that the correct tube has been plugged, only that the tube marked has been plugged. A possible contributor to the plugging of the wrong tube is that the SIG Tube Map does not indicate which axis represents rows and which represents columns. This should be self evident though since there are more than twice the number of columns than rows {i.e., 94 columns and 46 rows). ANALYSIS OF OCCURRENCE: | | * During the eddy current inspection of No. 23 S/G, the inspectors discovered that a tube thought to be plugged was not. As indicated in the above list the No. 23 SIG tube associated with Row 25 Column 10 was plugged this outage. However, during the second refueling outage, this same tube was identified as being plugged. |
| The tube which should have been plugged during the second refueling outage had a percent degradation of 38% when inspected in December 1984. During the recent inspection, its percent degradation | | APPARENT CAUSE OF OCCURRENCE: |
| ?NI:._.2 SPECIAL REPORT *-4 | | The root cause of the tube degradation has been attributed to normal wear caused by erosion/corrosion factors. |
| * AMALYSIS OF OCCURRENCE: (cont'd) increased to 46%. Since the Technical Specifications for the maximum allowable percent degradation were not violated, as per the December 1984 inspection, this event is not reportable as per NUREG 1022, "Licensee Event Report System". In summary of the entire fifth refueling inspection, the tubes found with 40% degradation is considered normal. Also, primary to secondary leakage was not observed during the Unit 2 operating period between the fourth (4th) outage and this outage. Therefore, the events identified by this report did not affect the health or safety of the public. This report satisfies Technical Specification Surveillance 4.4.6.5.a which states: "Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15*days." CORRECTIVE ACTION: Modifications to the independent review process were implemented prior to completion of tube plugging this outage. The process now requires SQA to prepare a separate map of the tubes to be plugged and to then independently verify that the correct tubes have been marked. The plugging of the incorrect tube in No. 23 SIG was an isolated occurrence.
| | The root cause of the wrong tube being plugged, in No. 23 S/G, has been attributed to personnel error associated with procedural noncompliance. |
| All tubes previously plugged have been verified as being correctly plugged. The S/G Tube Maps will be revised to label the axis. This event has been reviewed by Station Quality Assurance (SQA) management. | | Investigation revealed that the No. 23 SIG tube associated with Row 10 Column 25 was in fact plugged during the second refueling outage and not the one associated with Row 25 Column 10. Apparently, the robotics operator reversed the Row and Column for this one tube, thereby marking the wrong tube to be plugged. The S/G tube plugging procedure requires a Quality Assurance inspection to verify that the correct tube is marked prior to plugging. This was not completed for this tube. On December 6, 1984, a QA inspection was performed for tubes which were to be plugged due to tube wear caused by vibration of the tube lane blocking device. On December 12, 1984, another tube was identified to be plugged as determined from eddy current inspections. This tube is the one for Row 25 Column 10 in No. 23 S/G. This tube was never verified by QA as being correctly marked, subsequently, the wrong tube was marked and eventually plugged. A second tube marking and plugging procedure had not been initiated; the original procedure {with its signoffs} was used for plugging the December 12, 1984 tube. |
| The circumstances surrounding the incorrect tube plugging event will be reviewed with appropriate | | The procedure for identifying those S/G tubes required to be plugged during the second refueling outage involved the use of remotely controlled robotics equipped with TV cameras. Tubes to be plugged are marked with a zyglo penetrant mixed with a Nissan marker. A Quality Assurance signoff is performed verifying that the correct S/G tube had been marked. Additionally, both Inservice Inspection Services {ISI) and Quality Assurance personnel viewed a live remote showing of the tube{s) plugged after which they sign the procedure certifying that the tube marked has been appropriately plugged. This second inspection {performed by QA and ISI inspectors) is not a verification that the correct tube has been plugged, only that the tube marked has been plugged. |
| !SI and Quality Assurance personnel. | | A possible contributor to the plugging of the wrong tube is that the SIG Tube Map does not indicate which axis represents rows and which represents columns. This should be self evident though since there are more than twice the number of columns than rows {i.e., 94 columns and 46 rows). |
| The accident analysis, associated with S/G tube rupture, will be reviewed in respect to the significance of not plugging the correct tube. A summary of the incorrect tube plugging event will be sent over the INPO Nuclear NETWORK as information for all other utilities. | | ANALYSIS OF OCCURRENCE: |
| MJP:pc SORC Mtg. 90-061 /t(Mµ General Manager -Salem Operations}}
| | The tube which should have been plugged during the second refueling outage had a percent degradation of 38% when inspected in December 1984. During the recent inspection, its percent degradation |
| | |
| | ?NI:._.2 SPECIAL REPORT * - 4 AMALYSIS OF OCCURRENCE: (cont'd) |
| | * increased to 46%. Since the Technical Specifications for the maximum allowable percent degradation were not violated, as per the December 1984 inspection, this event is not reportable as per NUREG 1022, "Licensee Event Report System". |
| | In summary of the entire fifth refueling inspection, the tubes found with ~ 40% degradation is considered normal. Also, primary to secondary leakage was not observed during the Unit 2 operating period between the fourth (4th) outage and this outage. Therefore, the events identified by this report did not affect the health or safety of the public. |
| | This report satisfies Technical Specification Surveillance 4.4.6.5.a which states: |
| | "Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15*days." |
| | CORRECTIVE ACTION: |
| | Modifications to the independent review process were implemented prior to completion of tube plugging this outage. The process now requires SQA to prepare a separate map of the tubes to be plugged and to then independently verify that the correct tubes have been marked. |
| | The plugging of the incorrect tube in No. 23 SIG was an isolated occurrence. All tubes previously plugged have been verified as being correctly plugged. |
| | The S/G Tube Maps will be revised to label the axis. |
| | This event has been reviewed by Station Quality Assurance (SQA) management. The circumstances surrounding the incorrect tube plugging event will be reviewed with appropriate !SI and Quality Assurance personnel. The accident analysis, associated with S/G tube rupture, will be reviewed in respect to the significance of not plugging the correct tube. |
| | A summary of the incorrect tube plugging event will be sent over the INPO Nuclear NETWORK as information for all other utilities. |
| | /t(Mµ General Manager - |
| | Salem Operations MJP:pc SORC Mtg. 90-061}} |
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Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
[Table view] |
Text
PS~G *
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 30, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 SPECIAL REPORT 90-4 This Special Report addresses the Steam Generator tubes plugged during the current fifth refueling outage. This report is submitted pursuant to the requirements of Technical Specification Surveillance 4.4.6.5.a. This report is required within fifteen (15) days of completion of tube plugging.
Sincerely yours,
- ~
L. K. Miller General Manager -
Salem Operations MJP:pc Distribution 9006050288 900530
~DR ADOCK 05000277
,.- F'DC The Energy People 95-2189 (10M) 12-89
SPECI~L REPORT NUMBER ~4 P~ANT IDENTIFICATION:
Salem Generating Station - Unit 2
- Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Steam Generator Tubes Plugged During the Fifth Refueling Outage Event Date: 5116190 Report Date: 5130190 This report was initiated by Incident Report Nos.90-277 and 90-331.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 6 - Refueling Outage DESCRIPTION OF OCCURRENCE:
On May 16, 1990, Steam Generator (SIG) tube plugging was completed.
Tubes were plugged either due to exceeding the percent degradation of
~ 40% (as per Technical Specification 4.4.6.4.6) or were between 30%
and 40% as a conservative measure (as determined by ISI). The following are the tubes plugged:
No. 21 SIG No. 22 SIG Row Column % Degradation Row Column % Degradation 32 61 53 31 78 37 32 63 41 34 59 42 32 65 41 34 63 48 33 45 44 39 44 45 33 48 38 34 59 46 39 43 55 40 56 36 No. 24 SIG No. 23 SIG Row Column % Degradation Row Column % Degradation 33 38 45 4 38 56 33 56 42 14 62 47 34 79 39 25 10 46 35 77 40 32 34 37 42 44 73 34 49 45 42 45 62 38 43 48 42 63 32 40 40 61 43 32 33 40 47 59 43 36 DRI* 40 49 44 43 45 39 40 52 52
- 43. 61 49 40 57 35 41 32 37 43 64 84
- - Distorted Roll Transition 43 62 84 Indication 45 36 37
t?NIT ,~ SPECIAL REPORT * - 4
- During the eddy current inspection of No. 23 S/G, the inspectors discovered that a tube thought to be plugged was not. As indicated in the above list the No. 23 SIG tube associated with Row 25 Column 10 was plugged this outage. However, during the second refueling outage, this same tube was identified as being plugged.
APPARENT CAUSE OF OCCURRENCE:
The root cause of the tube degradation has been attributed to normal wear caused by erosion/corrosion factors.
The root cause of the wrong tube being plugged, in No. 23 S/G, has been attributed to personnel error associated with procedural noncompliance.
Investigation revealed that the No. 23 SIG tube associated with Row 10 Column 25 was in fact plugged during the second refueling outage and not the one associated with Row 25 Column 10. Apparently, the robotics operator reversed the Row and Column for this one tube, thereby marking the wrong tube to be plugged. The S/G tube plugging procedure requires a Quality Assurance inspection to verify that the correct tube is marked prior to plugging. This was not completed for this tube. On December 6, 1984, a QA inspection was performed for tubes which were to be plugged due to tube wear caused by vibration of the tube lane blocking device. On December 12, 1984, another tube was identified to be plugged as determined from eddy current inspections. This tube is the one for Row 25 Column 10 in No. 23 S/G. This tube was never verified by QA as being correctly marked, subsequently, the wrong tube was marked and eventually plugged. A second tube marking and plugging procedure had not been initiated; the original procedure {with its signoffs} was used for plugging the December 12, 1984 tube.
The procedure for identifying those S/G tubes required to be plugged during the second refueling outage involved the use of remotely controlled robotics equipped with TV cameras. Tubes to be plugged are marked with a zyglo penetrant mixed with a Nissan marker. A Quality Assurance signoff is performed verifying that the correct S/G tube had been marked. Additionally, both Inservice Inspection Services {ISI) and Quality Assurance personnel viewed a live remote showing of the tube{s) plugged after which they sign the procedure certifying that the tube marked has been appropriately plugged. This second inspection {performed by QA and ISI inspectors) is not a verification that the correct tube has been plugged, only that the tube marked has been plugged.
A possible contributor to the plugging of the wrong tube is that the SIG Tube Map does not indicate which axis represents rows and which represents columns. This should be self evident though since there are more than twice the number of columns than rows {i.e., 94 columns and 46 rows).
ANALYSIS OF OCCURRENCE:
The tube which should have been plugged during the second refueling outage had a percent degradation of 38% when inspected in December 1984. During the recent inspection, its percent degradation
?NI:._.2 SPECIAL REPORT * - 4 AMALYSIS OF OCCURRENCE: (cont'd)
- increased to 46%. Since the Technical Specifications for the maximum allowable percent degradation were not violated, as per the December 1984 inspection, this event is not reportable as per NUREG 1022, "Licensee Event Report System".
In summary of the entire fifth refueling inspection, the tubes found with ~ 40% degradation is considered normal. Also, primary to secondary leakage was not observed during the Unit 2 operating period between the fourth (4th) outage and this outage. Therefore, the events identified by this report did not affect the health or safety of the public.
This report satisfies Technical Specification Surveillance 4.4.6.5.a which states:
"Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15*days."
CORRECTIVE ACTION:
Modifications to the independent review process were implemented prior to completion of tube plugging this outage. The process now requires SQA to prepare a separate map of the tubes to be plugged and to then independently verify that the correct tubes have been marked.
The plugging of the incorrect tube in No. 23 SIG was an isolated occurrence. All tubes previously plugged have been verified as being correctly plugged.
The S/G Tube Maps will be revised to label the axis.
This event has been reviewed by Station Quality Assurance (SQA) management. The circumstances surrounding the incorrect tube plugging event will be reviewed with appropriate !SI and Quality Assurance personnel. The accident analysis, associated with S/G tube rupture, will be reviewed in respect to the significance of not plugging the correct tube.
A summary of the incorrect tube plugging event will be sent over the INPO Nuclear NETWORK as information for all other utilities.
/t(Mµ General Manager -
Salem Operations MJP:pc SORC Mtg.90-061