Letter Sequence Other |
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MONTHYEARML20236X2381987-06-0404 June 1987 Kerotest Valve Flow Test, Subtask Rept,Accumulator Fill Line Failure.Chronology & Action Plan Encl Project stage: Other IR 05000344/19870261987-07-27027 July 1987 Insp Rept 50-344/87-26 on 870706-10.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,External & Internal Exposure Control, Control of Radioactive Matls & Contamination & ALARA Project stage: Request ML20236L3451987-07-30030 July 1987 Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20237J2151987-08-21021 August 1987 Advises That Technical Issues Re Accumulator Fill Line Failure & Main Feedwater Pipe Restraint Failure Adequately Addressed by Licensee.Summary of 870617 Meeting Encl.W/O Encl Project stage: Meeting ML20238C3451987-09-0404 September 1987 Forwards Response to NRC Request for Addl Info Re Accumulator Fill Line Nozzle Stress Calculation.Areas Discussed Include Estimate of Previous Nozzle Loading & Fatigue Usage Factors Project stage: Request ML20236M8711987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures Project stage: Other ML20236M8551987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure Project stage: Other ML20236M8371987-11-11011 November 1987 Forwards SERs Re Main Feedwater Line Restraint Failure & Accumulator Fill Line Failures at Plant.Repairs Proposed by Util Acceptable to Ensure Integrity of Damaged Sys for Continuing Plant Operation Project stage: Approval ML20236X2261987-12-0303 December 1987 Forwards Presentation Handout & Subtask Rept Describing Backflow Test Conducted to Verify Postulated Failure Mode of Accumulator Fill Line & Recovery Action Plan Project stage: Other 1987-07-27
[Table View] |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass NUREG-5055, Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-50551990-10-10010 October 1990 Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-5055 ML20059C1331990-08-21021 August 1990 Notification of Enforcement Conference 90-143 W/Util on 900830 to Discuss Violation Noted During Special Security Insp 1999-09-03
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1561998-01-22022 January 1998 Staff Requirements Memo Re SECY-97-244, Waste Classification of Plant Reactor Vessel ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20216F2611997-08-26026 August 1997 Staff Requirements Memo Re SECY-97-164, Shipment of Decommissioned Reactor Vessel,Containing Irradiated Internals,From Trojan Nuclear Plant to Hanford Nuclear Reservation,Richland,Wa ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass 1999-09-03
[Table view] |
Text
December 3, 1987
. ..--s i
Decket No. 50-344
)
MEMORANDUM FOR: File FROM: Terence L. Chan, Project Manager Prcject Directorate V Division of Reactor Projects - III, IV, V and Special Projects !
SUBJECT:
ACCUMULATOR FILL LINE FAILURE (TAC 65473) l The attached presentation handout (Enclosure 1) was used by Portland General Electric Company in their presentation to Region V on June 5, 1987.
The licensee's Subtask Report (Enclosure 2) is a description of the back-flow test which was conducted to verify the postulated failure mode of the accumulator fill line.
Also attached is the licensee's Recovery Action Plan on this subject (Enclosure 3). These enclosures should be part of the TAC 65473 file.
original signed by Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated DISTRIBUTION:
!Docketlile NRC & Local FCRs PDV Reading TChan GKnighton PD5 .
TChan -
12/ 3 /87 jFJ 28eRSAS!h4 P
A December 3, 1987
% B-Docket No. 50-344-
~
liEMORANDUM FOR: File FROM: Terence L. Chan, Project Manager Project Directorate V l Division of Reactor Projects - III, IV, V and Special Projects
SUBJECT:
ACCUMULATOR FILL LINE FAILURE (TAC 65473) l The attached presentation handout (Enclosure 1) was used by Portland General
]
E-,ectric Company in their presentation to Region V on June 5. 1987.
The. licensee's Subtask Report (Enclosure 2) is a description of the back-flow test which was conducted to verify the postulated failure mode of the j accumulator fill line.
1 Also attached is the licensee's Recovery Action Plan on this subject (Enclosure 3).' These enclosures should be part of the TAC 65473 file.
l original signed by Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated DISTRIBUTION:
Docket File NRC & Local FDRs PDV Reading TChan l
GKnighton PD5' TChan .
12/ 3 /87
)
Enclosure 1 L. Y x ACCUMULATOR FILL LINE FAILURE CHRONOLOGY AND OPERATIONAL ISSUES - ART OLMSTEAD ENGINEERING ISSUES - ALEX ROI.LER i
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ACCUMULATOR FILL LINE FAILURE 4
CHRONOLOGY MAY 12, 1987: -
"A" ACCUMULATOR FILL LINE FAILS WHILE SLUICING FROM "A" To "D" ACCUMULATOR EVENT REPORT INITIATED PHOTOGRAPHS OF FAILURE MAINTENANCE REQUEST (WORK ORDER) INITIATED NUCLEAR PLANT ENGINEERING (NPE) INFORMED OF FAILURE l
t
l 1
.I a I
i 1
l ACCUMULATOR FILL LINE FAILURE i CHRONOLOGY k
MAY 13-20, 1987: -
COMPANY METALLURGIST REQUESTED TO EVALUATE FAILURE l
INITIATED AND COMPLETED NONDESTRUCTIVE EXAMINATION ;
0F OTHER ACCU,MULATOR CONNECTIONS !
DISCUSSED POSSIBLE FAILURE MECHANISMS WITH NPE ,
I i
REPLACED PIPING BEIWEEN "A" ACCUMULATOR AND CONTROL i VALVE (CV) 8878A I PRELIMINARY EVALUATION OF FAILURE INDICATES HIGH STRESS-LOW CYCLE FATIGUE CLEARANCE OF SYSTEM RELEASED BY MAINTENANCE i
"A" LINE KER0 TEST AND CONTROL VALVE INSPECTED
)
l
-3_
1 I
i e ACCUMULATOR FILL LINE FAILURE CHRONOLOGY MAY 20-23, 1987: -
HYDROSTATIC TEST PROCEDURE PREPARED "A" ACCUMULATOR FILLED USING FILL LINE FILL LINE OBSERVED DURING FILL OPERATION - NO MOVEMENT l
l l
u _ __ _ _ _ _ --_-_ _ --_ -_-
l :
9 ACCUMULATOR FILL LINE FAILURE CHRONOLOGY MAY 23, 1987: -
HYDROSTATIC TEST OF "A" ACCUMULATOR PERFORMED SATISFACTORILY BEGAN SLUICING OPERATION FROM "A" To "D" ACCUMULATOR l VIA FILL LINE OBSERVED WATER HAMMER-LIKE NOISE DURING SLUICIflG FILL LINE BREAKS AT SAME LOCATION IMMEDIATE EVENT REPORT INVESTIGATION.INIIIATED E'0VIPMENT-QUARANTINED -
PERFORMANCE MONITORING / EVENT ANALYSIS (PM/EA) GROUP BEGAN INVESTIGATION ALL SLUICING OPERATIONS PR0HIBITED i
l 1
l 5
l r ACCUMULATOR FILL LINE FAILURE CHRONOLOGY.
MAY 24-25, 1987: -
COMPANY METALLURGIST BACK ONSITE TO EVALUATE FAILURE BEGAN NONDESTRUCTIVE EXAMINATION NO NEW PROBLEMS OR DEFICIENCIES IDENTIFIED BLENDED AREAS EXCEED MINIMUM WAl.L MAY 27, 1987: -
ACTIONS COMPLETED TO QUARANTINE OTHER SAFETY INJECTION SYSTEM EQUIPMENT 4
fl e j ACCUMULATOR FILL LINE FAILURE CHRONOLOGY __
MAY 28 -
JUNE 3, 1987: -
HOLD TAGS PLACED ON QUARANTINED EQUIPMENT INSPECTION PLANG PREPARED INSPECTIONS BEGAN ON QUARANTINED EQUIPMENT OPERATING INSTRUCTION (01) 5-2, SAFEIY INJECTION, REVISED DELEIING ALL BACKFLOW OPERATIONS PRELIMINARY STRESS ANALYSIS INDICATES HIGH STRESS AT N0ZZLE TO PIPE INTERFACE VALVE BACKFLOW TEST DEVELOPED AND PERFORMED
- f. '
ACCUMULA10R FILL LINE FAILURE OPERATIONAL ISSUES COMPARISON OF AUGMENTED INSPECTION TEAM (All)
GUIDELINES FOR QUARANTINED EQUIPMENT WITH PGE
__ ACTION FOR FAILED SI ACCUMULATOR l AIT GUIDELINES PGE ACTIONS PROCEDURES TO CONDUCI EVENT REPORTING SYSTEM 05/12/87 INVESTIGATION CONFIRMATORY AC110N PLAN PLANT GENERAL MANAGER (PGM) DIRECTED TO FREEZE EQUIPMENT QUARANTINE OF EQUIPMENT 05/23/87 ACl10N PLAN TO DEIERMINE EVENT REPORT SYSTEM USED TO DEVELOP AC110N CAUSE OF FAILURE PLAN TO DEIERMINE CAUSE OF FAILURE 05/23/87 DEVELOP QUARANTINED NUCLEAR PLANT ENGINEERING /0VALITY ASSURANCE EQUIPMENT LIST (NPE/0A) IDENTIFIED EQUIPMENT TO BE ANALYZED VERBALLY TO OPERA 110NS AND MAINTENANCE 05/26/87 QC HOLD TAGS IDENTIFIED EQUIPMENT TO BE PROCEDURALLY CONTROLLED AND INSPECTION (S)
DOCUMENTED 05/28/87 l
ESTABLISH BARRIERS OF OA SIGNED ON CLEARANCE TO CONTROL B0UNDARIES l THE QUARANTINE AREA 05/28/87 GUIDELINES FOR 1ROUBl.E- VALVE DISASSEMBLY PROCEDURES AUCMENTLD BY SH00 LING WORK NPE WRilIEN GUIDANCE AND NPE DIRECI
- INVOLVEMENT 05/30/87 1
REPOR1[NG EVENT REPOR1 SYSTEM USED FOR REPOR11NG 05/12/87 8-U _ _ _ - _ _ - _
9 r ACCUMULATOR Fil.L LINE FAILURE OPERATIONAL ISSUES CHANGE ANALY1LS. j l
.10NDIT10NS PREVIOUS PRESENT CONDITIONS CHANGE l 1. SYSTEM INTACT SYSTEM DAMAGED SLUICE FROM "A" l ACCUMULATOR T0 "D" l ACCUMULATOR VIA FILL l LINE
- 2. SYSTEM DANGER TAGS REMOVED FOR HYDRO- NO CLEARANCE I TAGGED (CLEARED) STATIC TEST l
- 3. SLUICE THROUGH SLUICE THROUGH FILL CLEARANCE ON SAMPLE
! SAMPLE LINES LINES LINES (LAGGED OU1) l USING 1 INCH LINE VERSUS 3/L1 INCH Lt . REVERSE FLOW REVERSE FLOW THROUGH No CHANGE THROUGH KER0 TEST KER0 TEST VALVE VALVE
- 5. OPERATIONAL OAR FOUND IN FILES No CHANGE ASSESSMENT REPORT WITH No ACTION TAKEN (OAR) 1DENTIFIED BUT WAS NOT COMMUNICATED i
- 6. WATER LEVELS "A" ACCUMULATOR SOLID DECREASE IN NORMAL EXPANSION SPACE 1
l
- 7. LOW DIFFERENTIAL DP = 650 PSI INCREASE IN FLOW PRESSURE (DP) VELOCITY BEIWF.LN' lANKS
.g_
- f. r-ACCUMULATOR FILL LINE FAILURE OPERATIONAL ISSUES l 1 l
ENERGY-BARRIER-TARGEllNALY1LS l LESS THAN
- ENERGY BARRIER ADE0UAIL AD_E011 AIL. NOT U Sell TARGET PRESSURIZED SEISMIC X REACTOR ACCUMULATOR PIPING CORE NDP 600-2 X PERSONNEL WATER HAMMER 01 5-2 X A0 3-9 X HANGERS X COMMUNICA- X TION OAR'S X DESIGN X (NORMAL)
DESIGN X (BACKFLOW)
MANAGEMENT X POLICY l
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.I e ACCUMULATOR FILL.LINE FAILURE l
l OPERATIONAL ISSUES FINDINGS
- 1. COMMUNICATIONS INADEQUATE W11HIN OPERATIONS BRANCH i
BETWEEN OPERATIONS AND SYSTEM ENGINEERS FROM OPERATIONAL EXPERIENCE REVIEW PROGRAM (GERP)
- 2. PROCEDURES 01 2 DEVI Al [0N WI IHOU T APPROVAL I
POLICY FOR OPERATING EQUIPMENT DURING REFUELING / MAINTENANCE NOT CLEAR 01-5-2 PERMllTED REVERSE FLOW THROUGH PACKLESS DIAPHRAGM GLOBE VALVES VIA SAMPLE LINES NONCONFORMANCE REPORT (NCR) PROCEDURE NOT CLEAR ON WHEN HOLD TAGS ARE REQUIRED
- 3. CONTROL ROOM LOGS LACK SPECIFICITY AND COMPLETENESS.
- 4. MAINTENANCE REl. EASED CLEARANCE AFIER REPAIR WORK WAS COMPLETED, LOSING CONIROL OF SYSTEM.
- 5. PLANT PIPING AND INSTRUMENT DRAWINGS (P&lDS) DO NOT PROVIDE ALL INFORMAL [0N NECESSARY TO WRITE PROCEDURES.
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ACCUMULA10R FII.L LINE Fall.URE OPERATIONAL-ISSUES _
SUMMARY
OF CORRECTIVE AClIONS
- 1. DEVELOP BETTER VERTICAL AND HORIZONTAL COMMUNICATIONS WITHIN AND OUTSIDE OPERATIONS DEPARTMENT.
- 2. PROVIDE TRAINING ON POLICY REGARDING PROCEDURAL COMPLIANCE.
- 3. PERFORM OUALITY ASSURANCE SURVEILLANCE OF THE OPERATIONAL EXPERIENCE REVIEW PROGRAM (OERP).
- 4. IMPROVE CONTROL ROOM LOGS.
- 5. REVISE NCR PROCEDURE TO PROVIDE DEIAILED CRIIERIA FOR HOLD 1AGS.
- 6. REVISE WORK ORDER PROCEDURE TO PROVIDE REQUIREMENTS FOR CONTROL 0F SYSTEMS BEIWEEN REPAIR AND CLOSEOUT OF ACCEPTABLE TESTING AND EVALUATIONS.
- 7. REVIEW ALL PROCEDURES TO ENSURE NO OTHER BACKFLOW OPERAll0NS ARE PERMITTED FOR PACKLESS DIAPHRAGM GLOBE VALVES.
- f. r ACCUMULATOR FILL LINE FAILURE ENGINEERING _ ISSUES INSPECTIONS ANALYSES ROOT CAUSES CORRECTIVE ACTIONS l
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ACCUMULATOR FILL LINE FAILURE ENGINEERING. ISSUES ,
INSPECTIONS SURFACE EXAMINATIONS ON:
ALL N0ZZLE-10 'IPE P WELDS FILL LINE PIPE WELDS FROM ACCUMULATOR 10 SECOND SUPPORT UPSTREAM 0F CONTROL VALVE SAMPLE LINE PIPE WELDS ABOUT 10 FEET ON EITHER SIDE OF SAMPLE LINE PACKLESS DIAPHRAGM GLOBE VALVES
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FILL LINE SLUICING PATHWAY FROM "A" TO "D" ACCUMULATOR l
RESULTS INDICATION ON "B" ACCUMULATOR INJECTION LINE N0ZZLE SCAB ON "B" ACCUMULATOR INJECTION LINE INDICATION ON "D" ACCUMULATOR INJECTION LINE N0ZZLE INDICATION ON FILL LINE FOR "B" ACCUMULATOR ULTRASONIC EXAMINATIONS N0ZZLE-TO-VESSEL WELD ON "A" ACCUMULATOR RIDGES ON "C" ACCUMULATOR FILL LINE TO DETERMINE WALL THICKNESS VISUAL PIPE SUPPORTS ON FILL LINES FOR ALL ACCUMULATORS CONTROL VALVES AND PACKLESS DIAPHRAGM GLOBE VALVES ON SAMPLE AND FILL LINES SMALL PIPING IN CONTAINMENT WITH PACKLESS DIAPHRAGM GLOBE VALVES ,
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ACCUMULATOR FILL LINE FAILURE ENGINEERING ISSUES ANALYSES:
METALLURGICAL ANALYSIS OF FAILURE DYNAMIC ANALYSIS OF SLUICING OPERATION DETERMINE FLOW RATES BACKFLOW THROUGH PACKLESS DIAPHRAGM GLOBE VALVES OTHER APPLICATIONS INDUSTRY EXPERIENCE N0ZZLE-TO-VESSEL WELD STRESSES ON "A" ACCUMULATOR TEST CONDUCTED AT BOARDMAN l
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ACCUMULATOR FILL LINE FAILURE ENGINEERING ISSUES ROOT CAUSES HIGH BACK FLOW THROUGH KER0 TEST VALVES CORRECTIVE ACTIONS EVALUATE APPLICATIONS AND USE OF PACKLESS DIAPHRAGM GLOBE VALVES PR0HIBIf SLUICING OPERATIONS
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