Safety Evaluation Supporting Use of Mechanical Stress Improvement Process in Primary Sys Stainless Steel Piping to Modify Residual Stress Pattern at Piping Butt WeldsML20137D808 |
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LaSalle |
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11/18/1985 |
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NRC |
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Shared Package |
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ML20137D767 |
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NUDOCS 8511270149 |
Download: ML20137D808 (7) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings of Safety-Related Power-Operated Gate Valves ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20203B1941997-12-0404 December 1997 Supplemental SE Accepting Proposed Changes Which Are Consistent W/Recognized Battery Stds & Station Blackout Rule ML20148T8571997-07-0303 July 1997 SER Accepting Temporary Use of Current Procedure for Containment R/R Activities Instead of Requirements of Amended 10CFR50.55a Rule to Be Reasonable ML20137D4961997-03-24024 March 1997 Safety Evaluation of Second 10-year Interval Inservice Insp Program Plan Requests for Relief CR-17 & CR-18 Commonwealth Edison Co,Lasalle County Station,Units 1 & 2 ML20135D4661996-12-0606 December 1996 Safety Evaluation Granting Relief Request RP-01 & Alternative Testing Imposed Per 10CFR50.55a(f)(6)(i) Based on Impracticality of Performing Required Testing ML20129D9401996-09-26026 September 1996 SER Accepting Licensee Cycle 8 Core Reload Design Submittal Re Application of Anfb Critical Power Correlation to Coresident GE9 Fuel as Described in TR EMF-96-021(P),Rev 1 ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20128E4101992-12-0101 December 1992 Safety Evaluation Accepting Relief Requests RI-22 & RI-23 from ASME Code Requirements from Hydrostatic Pressure Testing Following Replacement of RCIC Steam Supply Inboard Isolation Valve as Part of ISI Program ML20059N0301990-08-22022 August 1990 Safety Evaluation Accepting Util Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping ML20154E5461988-09-0707 September 1988 Safety Evaluation Supporting Amends 60 & 40 to Licenses NPF-11 & NPF-18,respectively ML20151X0121988-08-16016 August 1988 Safety Evaluation Re Inservice Testing Program & Requests for Relief ML20237C8761987-12-16016 December 1987 Safety Evaluation Supporting Facility IGSCC Insp,Per Generic Ltr 84-11 ML20237C9091987-12-16016 December 1987 Safety Evaluation Supporting Licensee Response to IE Bulletin 79-26,Rev 1, Boron Loss from BWR Control Blades, Per License Condition 2.C(6) ML20205R6681987-04-0101 April 1987 Safety Evaluation Supporting Continued Use of Static O-Ring Differential Pressure Switches ML20211P2551986-12-15015 December 1986 Safety Evaluation Supporting Util Compliance W/License Condition 2.C.(25)(d) Requirements Re Mods to Six Fire Door Stops ML20214U8501986-12-0404 December 1986 Safety Evaluation Re Util 861006 Response to IE Bulletin 79-26,Rev 1, Boron Loss from BWR Control Blades, to Satisfy License Condition 2.C(13).Response Acceptable ML20214T3991986-12-0202 December 1986 Supplemental Safety Evaluation Accepting Licensee 860613 Analysis & Justification for Cable Separation Criteria to Resolve Deficiencies Described in Sser 7,App D ML20213G3181986-11-12012 November 1986 Safety Evaluation Accepting local-to-bulk Temp Difference of 12 F.Draft Technical Evaluation Rept Encl ML20215K8741986-10-21021 October 1986 Safety Evaluation Accepting Offsite Dose Calculation Manual Updated Through Rev 12.Changes Incorporated in Revs 11 & 12 Comply W/Tech Spec 6.8.2 ML20215K9631986-10-16016 October 1986 Safety Evaluation Granting Interim Acceptance of Process Control Program Updated Through 850718 ML20212Q7191986-08-29029 August 1986 Safety Evaluation Supporting Amend 27 to License NPF-18 ML20205F0791986-08-11011 August 1986 Safety Evaluation Supporting 860213 Procedures for Design of Single Angle Members for HVAC Hanger Frames for Plant. Related Info Encl ML20205C4051986-08-0707 August 1986 Safety Evaluation Supporting Facility Restart Following 860601 Feedwater Transient.Licensee Action Plan,Supplemented by Listed Actions,Adequate Basis for Restart & short-term Operation.Supporting Drawings & Matls Encl ML20206M6161986-06-23023 June 1986 Safety Evaluation Supporting Responses to Generic Ltr 83-28 Item 2.1 (Part 1) Re Equipment Classification ML20195D4121986-05-27027 May 1986 Safety Evaluation Summary of Inservice Testing Program for Pumps & Valves.Program Acceptable Subj to Listed Conditions in Encl SER ML20195D4171986-05-27027 May 1986 SER Re Pump & Valve Inservice Testing Program NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves1986-05-19019 May 1986 Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves ML20198B4221986-05-15015 May 1986 Supplemental Safety Evaluation Supporting Util Cable Separation Criteria Per Sser (NUREG-0519),App D.Addition of Zipper Tubing to Divisional Cables for Automatic Depressurization Sys Relief Valves Resolved NRC Concern ML20203N5531986-04-30030 April 1986 Safety Evaluation Concluding That Util IGSCC Insp Performed in Accordance W/Generic Ltr 84-11 & Satisfactory.Small Concerns Re long-term Growth of Small IGSCC Cracks Present But Not Detected During Insp Remain ML20140D6501986-03-19019 March 1986 SER Supporting Test Program,Results & Commitment for Nonqualified GE Control Switches.License Conditions 2.C.(21)(c) & 2.C.(12)(a) for Units 1 & 2,respectively,will Be Satisfied When GE Switches Removed from Engine ML20210E0961986-02-0404 February 1986 Safety Evaluation Accepting Util 851113 Proposal for Amend Changing Tech Specs to Include Previously Approved Trip Setting on Low CRD Pump Discharge Water Header Pressure & to Delete Associated Surveillance Requirement ML20137D8081985-11-18018 November 1985 Safety Evaluation Supporting Use of Mechanical Stress Improvement Process in Primary Sys Stainless Steel Piping to Modify Residual Stress Pattern at Piping Butt Welds NUREG-0889, SER Conditionally Supporting Response to Procedures Generation Package1985-10-18018 October 1985 SER Conditionally Supporting Response to Procedures Generation Package ML20137S6391985-09-30030 September 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks.Deviation from SRP Acceptable for Piping Sys Identified in Ref 2 Except Portion of RHR Sys Made of 304SS Matl ML20129D9511985-07-16016 July 1985 Safety Evaluation Supporting Acceptance Criteria for Firecode CT Gypsum Fire Stops ML20126K9121985-07-12012 July 1985 Revised SER Re Util 831105 & 850605 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review Program. Program & Procedures Acceptable ML20129E8881985-05-24024 May 1985 SER of Util 831105 Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capabilities.Capabilities Acceptable 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML20199E4601998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for LaSalle County Station,Units 1 & 2.With ML20207C7371998-12-31031 December 1998 Annual Rept for LaSalle County Station for Jan 1998 Through Dec 1998 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20206N2261998-12-0909 December 1998 LER 98-S03-00:on 981116,protected Area Was Entered Without Current Authorization for Unescorted Access Due to Programmatic Deficiency Error.Changed Badge Control Process ML20197K0981998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for LaSalle County Station,Unts 1 & 2.With ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings of Safety-Related Power-Operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3191998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for LaSalle County Station.With ML20154H6781998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151W0241998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for LaSalle County Station.With ML20237E2921998-08-21021 August 1998 Special Rept:On 980811,channel 5 of Lpms Became Inoperable. Caused by Channel Failed pre-amplifier Located Inside Primary Containment at Inboard Side of Electrical Penetration E-19.Initiated Repairs of Channel ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B4861998-07-31031 July 1998 Monthly Operating Repts for July 1998 for LaSalle County Nuclear Power Station Units 1 & 2 ML20236V7701998-07-31031 July 1998 Revised LaSalle Unit 1 Cycle 8 COLR & Reload Transient Analysis Results ML20236P8231998-07-14014 July 1998 Special Rept:From 980614-17,various Fire Rated Assemblies Were Inoperable for Period Greater than Seven Days.Caused by Test Equipment Being Routed Through Fire Doors.Established Fire Watches & on 980619 Assemblies Were Declared Operable ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20236P3611998-06-30030 June 1998 Monthly Operating Repts for June 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20249C4891998-06-22022 June 1998 Special Rept:On 980522,Fire Detection Zone 1-31 Was Noted out-of-service for More than 14 Days.Detection Sys Was Taken out-of-service on 980508 to Prevent False Alarms During Hot Work Activities.Sys Was Returned to Operable Status 980528 ML20248M3101998-05-31031 May 1998 Monthly Operating Repts for May 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20236V7771998-05-31031 May 1998 Rev 1 to 24A5180, Supplemental Reload Licensing Rept for LaSalle County Station Unit 1 Reload 7 Cycle 8 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20247M4491998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for LaSalle County Station ML20216F4941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for LaSalle County Station,Units 1 & 2 ML20217N6581998-03-30030 March 1998 Special Rept on Fire Detection,Deluge Sys & Fire Rated Assemblies During Period of 980303-25.Established Fire Watches Until Affected Equipment Is Returned to Operable Status ML20216D9511998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for LaSalle County Station,Units 1 & 2 ML20247M4631998-02-28028 February 1998 Rev Monthly Operating Rept for Feb 1998 for LaSalle County Station ML20203D7241998-02-20020 February 1998 Special Rept:On 980118,Fire Detection Zones 1-18 & 2-18 Taken out-of-svc to Prevent False Alarms During Hot Work Activities on Auxiliary Electric Equipment Room Ventilation Sys.Fire Watches Will Remain in Place ML20202G9851998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for LaSalle County Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr 1999-09-30
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ENCLOSURE SAFETY EVALUATION OF THE MECHAHICAL STRESS IMPROVEMENT PROCESS Introduction By letter dsted July 19, 1985, Comonwealth Edison Company (the licensee) proposed the Mechanical Stress Improvement Process (MSIP) developed by O'Donnell & Associates as an alternative to Induction Heating Stress Improvc-ment (IHSI) that was previously committed for the LaSalle County Unit I during the first refueling outage. The purpose of these stress improvcment processes is to modify the residual stress pattern at piping butt welds. Normal welding practice induces a detrimental residual stress, putting the inside surface of ,
the weldment area in a state of residual tensile stress. This, in conjunction with service-induced stresses, causes IGSCC at the heat-affected-zone (HAZ) next to the weld fusion line. The intent of the stress improvement processes is to induce plastic strain in a manner that will leave the insice surface in the weld area in a state of residual cenpressive stress.
The beneficial effect of stress improvement effected by IHSI has been shcwn by_ analysis, residual stress measurements, and service experience in Japan, where it was developed and first applied. The NRC has reccuended the use of IHSI for BWR piping weldrents, and permits a significant reduction in augmented inspection schedules for piping so treated. The process has been applied to about one thousand welds in at least ten operating BURS.
- Ongoing tests of IHSI treated welds in pipe test facilities at GE and Phl are sponsored by EPRI and the BWROG. It is expected that the results of these tests, in conjunction with actual field service will provide further verification on the amount of benefit in reducing the potential for inter-granularstresscorrosioncracking(IGSCC)overthelongterm.
l Description of the Process The HSIP process has only recently been developed as an alternative stress l improvement process. Instead of using a large tr.rporature gradient through the wall of the pipe to achieve the desired plastic strain pattern,F. SIP 0511270149 851110 PDH ADOCK 05000373 U PDR
f uses mechanical methods stated to be less expensive and time-consuming, and involves less radiation exposure to the technicians performing the operation.
t In the MSIP process, the pipe is plastically " squeezed" or contracted at a location about two inches to one side of the weld being treated. The ;
force is provided hydraulically, working through split rings with flexible metallic pads between the rings and the pipe. A permanent reduction in diameter of about one to two percent is achieved by this process. After the equipment is renoved, elastic springback results l in residual tensile stresses in the squeezed area, balanced by compressive l stresses in the weld and HAZ area at the inside surface of the pipe.
O'Donnell&Associateshasperformedfiniteelementanalysestopredibthe resultant residual stress patterns produced in various weld configurations.
Some surface residual stresses were also experimentally evaluated, and confirmed the analytical results. The results of these evaluations show that the desired compressive residual stresses are developed in the weld and HAZ l area.
t Such analyses were also performed to determine the effects of general j and local out-of-roundness and mismatch conditions on the end result.
These showed that the resulting beneficial residual stresses were essentially not affected by these conditions.
The process itself is closely controlled by physical measurements before and after application. The amount of defomation desired is calculated, and mechanical spaces are used between the two split rings to positively ;
control the amount of diametral reduction to that desired.
Magnesium Chloride Test
' A test that has been regularly applied to pipe samples to detect detrimental residual stresses induced by welding, and to evaluate process variables intended to reduce such detrimental stress is a boiling magnesium chloride test. This is routinely performed at the EPRI NDE Center (managed by J. A. Jones Applied Research Company).
A utility planning to use MSIP on replacement piping (Vermont Yankee) sponsored a standard magnesium chloride test on a piping sample containing two welds. One of the welds was intentionally given the HSIP treatment.
The adjacent weld was close enough that it also was subjected to some stress improvement. Although there originally was some confusion regarding details of the test results, these were clarified in a September 27, 1985 letter from the J. Jones Company, who perfonned the test. The test was run in confonnance with ASTM G36-73 (reapproved 1979), except that the exposure time was 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> instead of the 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> usually considered adequate.
Neither the MSIP treated weld or the adjacent pipe butt weld cracked in this test, although the weld applied to hold the botten plate to the pipe test section did show cracking, both in the pipe and in the plate material (this bottom plate is put on to make the pipe test secticn serve as a container for the magnesium chloride). According to J. A. Jones, this cracking verified that the test was a valid one, even though the butt weld not intentionally processed by MSIP did not crack. A review of the actual sample geometry shows that the one-sided flSIP treatment was actually performed within two inches of the cptimum location for MSIP of the weld not intented to be treated. Therefore, it can be assumed that it was at least partially treated, and this partial treatment was sufficient to prevent cracking in the test.
Effect of Varying Strength Across the Weld Area Soce concern has been expressed regarding the efficacy of the process censidering the variation of strength levels of the base material and the weld area. It should be pointed out that the residual stress on the HAZ depends primarily on the plastic strain in the compressed area outside the weld. The yield strength in this area of the criginal pipe will be at least 30,000 psi, and after: compression to 2 22, plastic strain would be expected to be in the range of 40-50,000 psi - the same range as the weld and cold worked region adjacent to the weld would have before treatment. Because the weakest material will yield first, and the deforma-tion is compressive (no reduction in area during plastic flow), the differing yield strengths will tend to become more uniform. That is, the weakest areas will defonn most, and therefore undergo the most strain hardening.
The resulting residual elastic stress pattern will therefore be dependent primarily on the strain hardened elastic properties of the originally lower strength base material, and not the original properties.
Possible Deleterious Effect of Cold Work It has been well known that severe cold work, such as that produced by abusive grinding, will enhance crack initiation in 8WR primary coolant.
General Electric has recently submitted proprietary data regarding the effect of lesser amounts of cold work on the susceptibility of austenitic stainless steels to IGSCC in the absence of classical sensitization.
Although these data cannot be disclosed, the results are not inconsistent with other test results and service experience that are not proprietary.
t . ;
(
i 1
f 1 I
t The Standard Review Plan for Control Rod Drive Structural itaterials, I
4.5.1, permits the use of cold worked stainless steel with a maximum i of 90,000 psi yield strength. This usually corresponds to something j in the range of 10 to 12% plastic strain. This criterion was based on ,
early published infonnation and unpublished work. Although we might now question the resistance of 90,000 yield strength material under high ,
! load controlled stress in BWR primary coolant, the information available !
i does not indicate any expected problem with material with 5 to 8% cold work j at about 65 to 80 ksi yield strength.
The MSIP process has been stated to produce up to 2% plastic strain in the base material of the pipe at the location where results in residual !
I tensile stress. The process is well controlled, so it is unlikely that l j the amount of plastic strain would exceed twice that amount. There are j no data that we know of that would indicate that even 4% plastically strained
! material would be subject to IGSCC initiation in BWR primary coolant.
t i
Staff Evaluation -
i i
l Although the basic concept of MSIP appears theoretically sound, and the
! process is inherently controllable, there has not been sufficient time j to develop confirmatory data to provide the same degree of confidence
! as is generally felt in the IHSI. The analytical work performed by l O'Donnell & Associates is ccmparable to that performed by vendors of l the'IHS1 process, but no independent analysis have yet been performed by j the staff.
i The successful service experience obtained in Japan on !HSI treated welds l l (4000hoursuntilpipeswerereplaced)providedadditionalevidencethatstress improvement, and IHS! in particular, reduced the probability of IGSCC.
The ongoing EPRI pipe tests on litSI treated weldments is expected to i
i
j , .
4 4 l 1
, provide even more quantifiable data, because stress levels are known and f controlled. These are expected to confirm the staff's conclusions regarding the degree of recuction in IGSCC severity and probability that l
i IHSI can be relied upon to produce. .
[
i !
, There are three main actions that should be taken to further confirm that }
l NSIP is also a viable stress improvement process, and to provide a quantifiable assessment: l j (1) Pipe samples containing MSIP treated weldcents should be included in the
- ongoing EPRI test program. l I
I l (2) independent clasto-plastic analyses should be perfonred to confirm those ;
j already done by O'Donnell & Associates; and [
l (3) through-the-wall experimental residual stress analyses should l be performed to confim the theoretical analysis results. !
)
r
} L 4
Conclusions ;
I It is the staff's conclusion, on the basis of information now available, that j the MSIP process will be proven to be effective. It appears likely that it f can be as effective as IHS! proved to be. The staff's interim positions on (
its use are as follows: !
(1) MSIP appears to have no deleterious effects, so can be used on replacement !
piping to further reduce the probability of IGSCC. [
i (2) IISIP can be used to reduce the extent and frequency of augmented inspec-I tions of piping susceptible to IGSCC. This reduction is expected to be i comparable to that afforded IHS! treated wolds if and when action items :
listed above are satisfactorily completed. :
l >
(3) The long range benefits of MSIP can only be proven out by long term pipe ,
tests and actual service experience. All types of stress improvement will be continuously evaluated as more test data and service experience are accumulated. As a result, augmented inspections to confirm the performance of MSIP treated welds are recomended.
1 i