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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20213F1841986-11-0606 November 1986 Safety Evaluation Re Util 850614 Request for Approval to Use ASME Boiler & Pressure Vessel Code,Section XI,1983 Edition, Winter 1984 Addenda,Subsection IWA 2213.NRC Evaluation of Winter Addenda Incomplete.Request Denied ML20140B8251985-12-0404 December 1985 Safety Evaluation Accepting Util Re Conformance to App R Requirements ML20198F4041985-10-30030 October 1985 Safety Evaluation Supporting Licensee 830624 & 1110 Ltrs Addressing License Condition 22, Control Sys Failures & IE Bulletin 79-27 ML20198F5871984-03-20020 March 1984 SER Recommending Acceptance of Applicant Action Re Magnetic Particle Linear Indications on Containment Weld Pads ML20198E9781984-01-27027 January 1984 SER Concluding Applicant Demonstrated That Structural Integrity of Sacrificial Shield Wall Will Meet Design Requirements W/Known & Postulated Flaws ML20198E9311984-01-23023 January 1984 SER Recommending Applicant Actions Re Magnetic Particle Linear Indications on Containment Weld Pads ML20213D6771981-04-13013 April 1981 Safety Evaluation Concluding That Proposed Spent Fuel Storage Racks Meet General Design Criteria 62 Criticality Requirements 1986-11-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
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ATTACHMENT SAFETY EVALUATION REPORT WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT N0. 2 DOCKET NO. 50-397 MAGNETIC PARTICLE LINEAR INDICATIONS ON CONTAINMENT WELD PADS MATERIALS APPLICATION SECTION MATERIALS ENGINEERING BRANCH BACKGROUND Purpose of Weld Pads There are 19 containaent shell weld pads at the 512' and 524' elevations which are steel plates, two inches in thickness, round or rectangular in shape, and approximately five feet in diameter or length of side.
Beam seats are welded to the pads, and the seats support the radial
+ beams between the Mark II boiling water reactor containment shell and the drywell .
Each pad attaches to the containment shell with a 3/8" fillet weld for t.he entire periphery of the pad. This is the minimum allowed fillet weld size for joints with material two inches in thickness as required l
l by the American Society for Mechanical Engineers Boiler and Pressure Vessel Code,1 Section III, Subsection NE, " Class MC Components." The peripheral welds are adequate by themselves to take all loads. There are redundant plug (circular fillet) welds within the pads that also attach the pads to the containment shell which are also capa' ole by themselves of supporting all the loads. The plug welds are a little over two inches in diameter and range in size from 1/2 to 5/8 inch.
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History of Events The Quality Verification Program required reinspection of a sample of attachment welding to the containment vessel under Contract 213. Rein-spection by magnetic particle testing (MT) revealed linear indications beside the thick weld pads' peripheral fillet welds to the steel containment shell. The reinspections were expanded to all 19 two inch thick pad attachments and all had linear indications. The indications have an average length of 3.3 inches on the pad side and grinding showed average depths of approximately 1/4 inch. Metallurgical investigations determined the indications in the weld pads and shell to be hydrogen underbead cracks.
In the weld pads, some of the underbead cracks ended as lamellar tears.
For the linear indications in the containment shell plating, metallurgical examination and ultrasonic testing (UT) showed no evidence of lamellar tearing, and the shell MT indications' lengths averaged about half of those in the weld pads. All peripheral fillet welds around the weld pads at the 512' and 524' elevations had their magnetic particle indications removed by grinding. These fillet welds were weld repaired and weld built-up to 1/7 inch, exceeding their original size of 3/8 inch, I
and the final welds met MT inspection criteria.
The 19 weld pads also have 405 plug or circular fillet welds which also attach the wild pad to the containment shell. A statistically significant (55) of these welds were inspected by liquid penetrant testing and 13 had linear indications. The indications were removed by grinding to sound metal demonstrated by liquid penetrant inspection, and the excava-l tions were allowed to remain as is.
These welds were not restored to their design configuration because:
o design did not require them as they were redundant to the peripheral fillet welds, o repair of these welds in these small holes would be very difficult.
o fracture mechanics analysis determined that the flaws were innocuous.
The inspections were further expanded to include ten other field welded pads of smaller size in the drywell and a sampling of all other attachment welds to the containment shell.
A few magnetic particle linear indications and one UT indication where (MT was not practical) were found. The total length of the indications is less than 1% of the lengths of welds reinspected. This ratio is normal for reinspections of structural steel weldments. The indications were short in length, and, where depths were determined, very shallow (maximum of 1/8 inch). Most MT linear indications were removed by grinding and weld repaired. Fracture mechanics analyses were performed based upon the largest size of the flaws found which far exceeded the size of linear indications not repaired and the analysis demonstrated that the flaws remaining would not propagate.
DISCUSSION / EVALUATION The extent and severity of the linear indications found on the original 19 thick weld pad attachments were not repeated in the expanded surface and UT examinations. This indicates that the original causative factors of cracking in the two inch thick pad weldments were unique, a local problem, and not generic to other. welded steel structures.
The expanded reinspection sample size appears adequate. The small per-centage of li.near indications length found vs. total length inspected is normal for reinspections of steel weldments which had previously been inspected. The AC yoke magnetic particle inspection method is an acceptable surface inspection technique. There are other magnetic particle inspection techniques which are more effective for detecting defects which do not break the surface, such as underbead cracking and lamellar tearing, the crack causing mechanisms in this case. However, the configuration of the assembly, and the sequence of fabrication and loading caused the underbead cracks to break to the surface or caused lamellar tears to initiate at the surface. Accordingly, the AC yoke method is viewed by the staff as acceptable for this application. At the present time, we do not have a demonstration that would convincingly justify our establishing particular surface examination techniques for structural steel constructions. The fracture prevention approach by the applicant is a standard app' roach, often used and accepted by the staff for many other applications.
CONCLUSION Based upon the data presented, we recommend acceptance of the applicant's actions.
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