Letter Sequence Other |
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Results
Other: ML20151L878, ML20215B790, ML20215B804, ML20215G101, ML20215G650, ML20215G653, ML20234D077, ML20236D570, ML20236F145, ML20236F153, ML20236F168, ML20236M855, ML20236M871, ML20237J052
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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 ML20215B7901987-06-11011 June 1987 Forwards Evaluation Rept of Main Steam Pipe Wall Thickness, Describing Fatigue & Finite Element Analyses Performed on Affected Piping,Per ASME Boiler & Pressure Vessel Code.Affected Piping Will Be Reexamined in 1988 Project stage: Other ML20215G6531987-06-11011 June 1987 Trojan Nuclear Plant Evaluation of Main Feed Line Seismic Restraint Failure Project stage: Other ML20215G1011987-06-12012 June 1987 Forwards Evaluation of Displacement at Main Feedwater Restraint SR4 in Trojan Nuclear Plant & Trojan Nuclear Plant Evaluation of Main Feed Line Seismic Restraint Failure, as Result of Failure During 1987 Refueling Outage Project stage: Other ML20215B8041987-06-30030 June 1987 Evaluation Rept of Trojan Nuclear Plant Main Steam Pipe Wall Thickness Project stage: Other ML20215G6501987-06-30030 June 1987 Evaluation of Displacement at Main Feedwater Restraint SR4 in Trojan Nuclear Plant Project stage: Other ML20234D0771987-06-30030 June 1987 Advises That Util Agrees to Complete One of Three Listed Actions Re Resolution of Main Steam Line Wall Thickness Issue Before Startup from 1989 Refueling Outage Project stage: Other ML20236F1531987-07-17017 July 1987 Final Rept Trojan Nuclear Plant SR8 Failure Root Cause Evaluation Steam Condensation-Induced Water Hammer 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 ML20236F1451987-07-27027 July 1987 Forwards Bechtel Western Power Corp Final Rept, Trojan Nuclear Plant SR8 Failure Root Cause Evaluation Steam Condensation-Induced Water Hammer & Impell Corp Summary Rept, Independent Review of Action Plan Items.. Project stage: Other ML20236D5701987-07-27027 July 1987 Advises That Util Plans to Resolve Issue Re Code Acceptability Applications Prior to 871201.Util Will Perform Necessary Design & Order Matls to Repair or Replace Unacceptable Main Steam Line Wall Thickness Areas Project stage: Other 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 ML20236F1681987-07-31031 July 1987 Rev 1 to Summary Rept, Independent Review of Action Plan Items to Resolve Trojan Main Feedwater Piping Restraint Failure Issue Project stage: Other 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 ML20237J0521987-08-21021 August 1987 Responds to Util Proposing to Resolve Issue Re Main Steam Line Wall Thicknesses Which Did Not Meet Min Requirements.Util Adequately Demonstrated That Safe Operation of Plant Until May 1989 Will Not Be Compromised Project stage: Other 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 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 ML20236M8551987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure Project stage: Other ML20236M8711987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures Project stage: Other 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 ML20151L8781988-04-15015 April 1988 Forwards Addl Info Re Six Open Items/Recommendations Noted in NRC 871111 Safety Evaluation of Failure of Main Feedwater Sys Restraint SR-8,per Commitment During Audit of long-term Pipe Support Design Verification Program in Jan 1988 Project stage: Other 1987-07-17
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20058K1391993-12-0606 December 1993 Safety Evaluation Supporting Amend 193 to License NPF-1 ML20057D9951993-09-30030 September 1993 Safety Evaluation Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Plant ML20057D0791993-09-22022 September 1993 Safety Evaluation Supporting Amend 192 to License NPF-1 ML20127P5801993-01-26026 January 1993 Safety Evaluation Supporting Amend 189 to License NPF-1 ML20125B8071992-12-0404 December 1992 Safety Evaluation Supporting Amend 188 to License NPF-1 ML20127L4221992-11-19019 November 1992 SE Accepting IST Program Requests for Relief for Pumps & Valves ML20059D1031990-08-30030 August 1990 SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20059C7981990-08-27027 August 1990 Safety Evaluation Supporting Amend 162 to License NPF-1 ML20058L5641990-08-0202 August 1990 Safety Evaluation Concluding That Operable Instrumented Ammonia Detection Capability Unncessary for Protection of Control Room Personnel in Event of Spill of Anhydrous Ammonia in Vicinity of Plant ML20055C7531990-06-18018 June 1990 Safety Evaluation Supporting Amend 161 to License NPF-1 ML20245H4141989-08-10010 August 1989 Safety Evaluation Approving on-line Functional Testing of Reactor Trip Sys,Per Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20245E8091989-06-20020 June 1989 Safety Evaluation Supporting Amend 154 to License NPF-1 ML20247M9331989-05-24024 May 1989 Safety Evaluation Supporting Amend 153 to License NPF-1 ML20247H9571989-05-15015 May 1989 Safety Evaluation Supporting Amend 152 to License NPF-1 ML20247F1911989-03-17017 March 1989 Safety Evaluation Supporting Amend 151 to License NPF-1 ML20235T5351989-02-28028 February 1989 Safety Evaluation Supporting Amend 150 to License NPF-1 ML20151T4191988-08-0505 August 1988 Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures as Design Basis for Facility ML20151X8581988-08-0303 August 1988 Safety Evaluation Supporting Amend 149 to License NPF-1 ML20151H3041988-07-14014 July 1988 Safety Evaluation Supporting Amend 148 to License NPF-1 ML20151L4391988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20151E4551988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20196G0421988-06-23023 June 1988 Safety Evaluation Supporting Amend 145 to License NPF-1 ML20196C1571988-06-22022 June 1988 Safety Evaluation Supporting Amend 144 to License NPF-1 ML20196F9471988-06-16016 June 1988 Safety Evaluation Supporting Amend 143 to License NPF-1 ML20154D4931988-05-11011 May 1988 Safety Evaluation Supporting Amend 142 to License NPF-1 ML20154A1151988-05-0303 May 1988 Safety Evaluation Supporting Amend 141 to License NPF-1 ML20148S6491988-04-11011 April 1988 Safety Evaluation Supporting Amend 140 to License NPF-1 ML20151B3821988-03-31031 March 1988 Safety Evaluation Supporting Amend 139 to License NPF-1 ML20236X5311987-12-0101 December 1987 Safety Evaluation Supporting Amend 137 to License NPF-1 ML20236S4021987-11-12012 November 1987 Safety Evaluation Supporting Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Fire Protection of Safe Shutdown Capability Requirements ML20236M8711987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures ML20236M8551987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure ML20236M9931987-11-0909 November 1987 Safety Evaluation Supporting Amend 136 to License NPF-1 ML20236A9151987-10-13013 October 1987 Safety Evaluation Concluding That Corrective Actions for Design Deficiencies in Main Steam Line Pipe Supports Adequate & Acceptable & That Commencement of Heatup & Return to Power Safe ML20235V6121987-10-0202 October 1987 Safety Evaluation Supporting Amend 135 to License NPF-1 ML20238B0181987-09-0101 September 1987 Safety Evaluation Supporting Amend 134 to License NPF-1 ML20237G8351987-08-25025 August 1987 Safety Evaluation Re Util 870723 Request for Relief from 4 H Test Pressure Hold Time Requirement of Section XI of ASME Code,1974 Edition Through Summer 1975 Addenda ML20237G8421987-08-24024 August 1987 Safety Evaluation Re Ultrasonic Insp of RCS hot-leg Elbow (Loop B).Ultrasonic Exam Performed Acceptable W/Exception of Ultrasonic Beam Spread Correction Procedures Used to Estimate Indication Size.Continued Operation Permissible ML20236P6731987-08-0707 August 1987 Safety Evaluation Supporting Amend 133 to License NPF-1 ML20236H5581987-07-30030 July 1987 Safety Evaluation Supporting Amend 132 to License NPF-1 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar ML20209C6531999-07-0606 July 1999 Rev 8 to Defueled SAR, for Trojan Nuclear Plant ML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20207G9881999-03-0303 March 1999 Rev 6 to Trojan Nuclear Plant Decommissioning Plan ML20207J0781999-02-28028 February 1999 Update to Trojan ISFSI Sar ML20202G4511999-02-0202 February 1999 Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar ML20207C6981998-12-31031 December 1998 1998 Annual Rept for Trojan Nuclear Plant. with ML20195J2501998-11-17017 November 1998 Rev 7 to Trojan Nuclear Plant Defueled Sar ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155E0411998-10-27027 October 1998 Amend 7 to Quality-Related List Classification Criteria for Tnp ML20154R4121998-10-0202 October 1998 Requests Commission Approval,By Negative Consent,For Staff to Grant Two Specific Exemptions from Package Test Requirement Specified in 10CFR71 for Trojan Reactor Vessel Package & to Authorize one-time Transport for Disposal ML20237B6121998-08-13013 August 1998 Revised Trojan Reactor Vessel Package Sar ML20151W5471998-08-13013 August 1998 Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant ML20236Y2691998-08-0808 August 1998 Revised Trojan Rv Package Sar ML20249B4081998-06-17017 June 1998 Rev 6 to Trojan Nuclear Plant Defueled Sar ML20203E6291998-02-28028 February 1998 Trojan Nuclear Plant Decommissioning Plan ML20198T1741998-01-0404 January 1998 Rev 5 to Trojan Nuclear Plant Decommissioning Plan ML20248K6891997-12-31031 December 1997 Enron 1997 Annual Rept ML20203J3821997-12-31031 December 1997 Annual Rept of Trojan Nuclear Plant for 1997 ML20248K6931997-12-31031 December 1997 Pacificorp 1997 Annual Rept. Financial Statements & Suppl Data for Years Ended Dec 1996 & 97 Also Encl ML20203B0341997-11-26026 November 1997 Rev 5 to Trojan Nuclear Plant Defueled Sar ML20199F8141997-10-21021 October 1997 Requests Approval of Staff Approach for Resolving Issues Re Waste Classification of Plant Rv ML20216F4291997-07-25025 July 1997 Requests Commission Approval of Staff Approach for Reviewing Request from Poge for one-time Shipment of Decommissioned Rv,Including Irradiated Internals to Disposal Site at Hanford Nuclear Reservation in Richland,Wa ML20141F2311997-06-24024 June 1997 Rev 3 to PGE-1061, Tnp Decommissioning Plan ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148E8631997-05-31031 May 1997 Amend 6 to PGE-1052, Quality-Related List Classification Criteria for Trojan Nuclear Plant ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20140D9451997-03-31031 March 1997 Tnp First Quarter 1997 Decommissioning Status Rept ML20137K5811997-03-31031 March 1997 SAR for Rv Package ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134B6231997-01-15015 January 1997 Draft Rev 3 of Proposed Change to Trojan Decommissioning Plan ML20217M2381996-12-31031 December 1996 Portland General Corp 1996 Annual Rept ML20217M2471996-12-31031 December 1996 Pacific Power & Light Co (Pacifcorp) 1996 Annual Rept ML20217M2551996-12-31031 December 1996 1996 Enron Annual Rept ML20135C3521996-12-31031 December 1996 Annual Rept of Trojan Nuclear Plant for 1996 ML20132G2831996-12-19019 December 1996 Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan ML20132H0011996-12-12012 December 1996 Rev 20 to PGE-8010, Portland General Electric Nuclear QA Program for Trojan Nuclear Plant ML20132B8491996-12-12012 December 1996 Rev 20 to PGE-8010, Trojan Nuclear Plant Nuclear QA Program ML20135B5241996-11-27027 November 1996 Rev 4 to Trojan Nuclear Plant Defueled Sar ML20135B5341996-11-25025 November 1996 Trojan ISFSI Safety Analysis Rept ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134K6621996-11-11011 November 1996 Decommissioning Plan,Tnp ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20134F4661996-10-30030 October 1996 Final Survey Rept for ISFSI Site for Trojan Nuclear Plant ML20134P4321996-09-30030 September 1996 Tnp Quarter Decommisioning Status Rept,Third Quarter 1996 ML20137K5321996-09-0505 September 1996 Rev 0 to H Analysis of Residue Protocol ML20137K5091996-06-28028 June 1996 Summary Rept Poge Tnp SFP Project 1999-07-06
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ENCLOSURE B SAFETY EVALUATION REPORT ACCUMULATOR FILL LINE FAILURES TROJAN NUCLEAR PLANT Docket No. 50-344 l
1.0 Description of_ Event i 1
During the 1987. refueling outage, two failures.of the "A". safety injection-accumulator fill line occurred. On May 12, 1987 while. transferring water from-the "A" accumulator to the "D" accumulator.by sluicing.through the fill lines, a rupture of.the "A" fill line at the accumulator nozzle-to pipe weld occurred.
The differential pressure between the accumulators at:the time.was 583 psid. , s A metallurgical evaluation indicated that a. low-cycle fatigue failure had occurred. >
The failed weld was repaired and the system was hydrostatically tested on Mayl23,
'1987. The pressure was then reduced to 650 psig and the si,uicing operation was.
repeated. A loud banging noise was heard, and'the operation was stopped.u A a' i second attempt was made and the loud banging noise continued;' Following a' valve '
line-up check, the operation was started again, and a rupture of the fill.line i
at the line nozzle weld location occurred. -
2.0 The Licensee's Efforts -l 2.1 Root Cause Evaluations Metallurgical evaluations were performed after the first and the second failures :
with the determination that failures were caused by low-cycle fatigue. The.
Licensee then conducted investigations to determine the cause of the failure land the source of the banging noise.
Through vendor and industry experience, the Licensee determined that the Kerotest -
Y pattern packless metal diaphragm (PMD) manual valves which.are used-in the
, accumulator fill line are subject to chattering when exposed to excessive back- ;
i
, flow. The sluicing flow will cause reverse flow through the PMD valve. Because the PMD valve's globe is held. open by a spring, when reverse flow through this-u valve reaches a specific velocity and the fluid closing force. exceeds'the spring force,.the disk will be forced down, shutting the valve. - The the valve will open and close repeatedly due to pressure oscillations. Industry data. suggests that backflow rates exceed 55 gallons per minute _(gpm).can result in valve chatter-and violent pressure surges in the attached piping system. _
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The 1.icensee conducted a test to determine the backflow. rate at which the Kero-test valve becomes unstable.and " chatters". A-section of. piping which replicated the geometry of a section of accumulator fill line, piping was: fabricated _for -
the tests. When the steady state backflow rate exceeded 68 gpm, chatter.was-noted. Pipe motion was violent and loud noises were. heard. The piping failed at the locations corre5ponding to the accumulator connection. The number of cycles to failure was' estimated at approximately-100. . s 8711130315 871111 ':
PDR ADOCK 05000344 -
8 1
PDR 1.
w l
. t The Licensee performed calculations to determine the expected backflow rates !
from the "A" to "D" accumulators when transferring water via tne fill and sample lines assuming a 600 psi differential pressure. The results indicated that the )
backflow rate via the fill line was 95 gpm. The backflow rate through the sample {
line was 45 gpm and the backflow rate to the CVCS holdup tank was 26 gpm. Based on these results, the Licensee concluded that valve chatter would be expected !
during a transfer operation via the accumulator fill line since the flow rate exceeds the critical flow rate. Valve chatter would not be expected in the l other two cases.
To verify. that the valve chatter was the cause of the piping failure, the Li-censee had Bechtel perform a water hammer analysis to predict the pipe stress during the event. In order to generate hydraulic forcing functions for struc-tural evaluations, a thermal hydraulic analysis of the piping between the ec-cumulators was performed. The model assumed a differential pressure of 580 psi, a backflow rate of 56 gpm and an assumed closure time of 5 milliseconds for the PMD valve (based on engineering judgement). The analysis indicated that sig-nificant pressure pulses would be generated due to valve clcsure, water column I separation and void collapse. Sensitivity studies with longer valve closure time and lower flow rate also indicated that high pressure pulses would be expected.
The force time history generated from the hydraulic analysis was applied to the '
piping system in a linear elastic dynamic time history analysis. The calculated !
stress at the pipe junction with the accumulator nozzle indicates that signifi-cant plastic deformation would occur.
The calculation also indicated that the piping was in resonance with the hydraulic force time history. Thus the analysis provided additional evidence that the hydraulic transient resulting from the l '
valve chattering could cause a low cycle fatigue failure.
l 2.2 Inspection of Accumulator Fill Lines j
The Licensee repaired the nozzle-to pipe weld and conducted a number of inspec- {'
tions to assure the integrity of piping and components of the affected line and similar safety injection lines. The inspection included the following:
- a. Surface examinations on (1) all nozzle-to pipe welds; (2) fill line pipe welds from accumulator to second support upstream of control valve, and (3) sample line pipe welds about 10 feet on either side of packless diaphragm globe valves, b.
Ultrasonic examinations on nozzle to vessel weld on "A" accumulator.
- c. Visual examinations on (1) pipe supports of fill lines for all ac-cumulators; (2) control valves and packless diaphragm globe valves on sample and fill lines, and (3) small piping in containment with packless diaphragm globe valves. .'
The inspection results indicated that all piping and nozzle-to pipe welds were satisfactory. All pipe supports were found to be satisfactory. Some damage was observed on the "A" fill line control valve and PM0 valve. These valves were repaired.
2
4 2.3 Accumulator Nozzle Evaluation In the course of the two failures of the "A" fill line at the pipe-to-nozzle weld, the nozzle was exposed to higher then normal loading. In order to verify j the adequacy of the nozzle for continuing service, the Licensee performed addi- )
tional evaluations to estimate the stress and the fatigue usage factors due to !
the pipe failure events. The nozzle loads were calculated based on the moment range required to produce bending stress equal to'twice the yield stress at the junction of the pipe and the socket weld. Using the methodology described in Welding Research Council (WRC) Bulletin No. 207, the combined membrane and bend-ing stress intensities were determined to be 1,484 psi at the vessel and 31,303 psi at the nozzle.
Since the vessel stress was significantly below the fatigue endurance limit of 14,000 psi, it was concluded that there was no loss in fatigue life. For the i nozzle, fatigue usage factors were calculated at two locations. The first loca-tion was at the bottom of the socket and the second at the base of the nozzle at ,
the interface with the vessel weld. The usage factors were conservatively based I on 2500 cycles at the calculated load. The resultant fatigue usage factors were C.01 for the first location and 0.004 for the second. A sensitivity check was performed using bending moments of double and half the calculated value. The usage factors for double the bending moment were 0.009 and 0.001, and for half the bending moment were 0.071 and 0.003, r w pectively. All of these values are well below the limit of 1.0, indicating that the effect on the fatigue life on the nozzle is negligible. ]
2.4 Corrective Actions The Licensee has made the necessary repairs on pipe-to-nozzle connection welds to make the system operational. To prevent future recurrence of the PMD valve chatter-induced water hammer, Operating Procedure 01-5-2 was revised to prohibit sluicing between accumulators through the fill or sample lines.
3.0 Staff Evaluations The staff reviewed the summary and results of the Licensee flow calculations (Attachment A to Reference 1) which indicated that during the sluicing opera-tion which resulted in the pipe failure, the backflow rate through the PMD valve l was 95 gpm. The staff also reviewed the test report on the PMD valve flow test (Reference 2) which demonstrated that valve chatter at high backflow rates can be expected when backflow exceeds a critical rate of approximately 70 gpm. The ,
test simulated the piping geometry of the accumulator fill line that failed. j At the critical flow rate, violent pipe motion was observed and the test piping failed at the location corresponding to the accumulator nozzle connection. I Based on these reviews, the staff concludes that the Licensee has adequately !
demonstrated that valve chatter and water hammer loads were a direct result of I the sluicing operation through the "A" to "D" fill lines. l 1
The staff reviewed Bechtel's report (Attachment B to Reference 1) on the thermal J hydraulic analysis and stress analysis of the piping due to rapid closure of 1 the PMD valve. The analysis indicated that the loads associated with the water hammer would result in stresses of sufficient intensity to cause a low cycle ]
fatigue piping failure at the nozzle connection. Based on these results and the 3 -
- - q i
^
9 l
i test results, the staff concludes that the Licensee has properly identified the root cause of the piping failure. The staff also concurs with the Licensee's corrective action in revising procedures to prohibit'the sluicing operations'in order to prevent recurrence of this type of failure.. '
j i
The Licensee performed several inspections and a stress analysis of the "A" vessel nozzle to verify the structural integrity of_.the system. The inspections included surface examinations of welds, ultrasonic examinations of the nozzle-to-vessel weld, and visual inspection of pipe supports, valves and other piping. L All inspection-results showed the system to be' satisfactory except for some valve '
damage. The valves were subsequently repaired. The staff finds the! inspections acceptable.
The staff reviewed the Licensee's accumulator nozzle stress evaluation (Attach-ment A to Reference 1). The staff concurs with the Licensee's conclusion that l the calculated fatigue usage factors would have a neg.ligible effect on the l fatigue life of the nozzle. ;
I i 4.0 Conclusion The staff evaluation concludes that the Licensee has properly identified the ,
cause of the accumulator fill line failures and has taken appropriate correc-tive actions to prevent future recurrences. The inspections have demonstrated the adequacy of the system in its present condition. '
References l
- 1. PGE letter, C. P. Yundt to USNRC, " Accumulator F 11 Line Failure Engineer-ing Analyses" dated June 12, 1987.
- 2. PGE Subtask Report, "Kerotest Valve Flow Tes. . Action Plan Item No.1A.2.1, Accumulator Fill Line Failure, dated June 4,1987.
- 3. PGE letter, D.W. Cockfield to USNRC, dated September 4, 1987 t
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