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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20202B8571997-11-18018 November 1997 SE Approving Relief Requests for Second 10-Yr Interval for Pumps & Valves Inservice Testing Program for Beaver Valley Power Station,Unit 2 ML20199F4641997-11-13013 November 1997 SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2 ML20212G4961997-10-28028 October 1997 SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20217J5311997-10-0808 October 1997 Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2 ML20217J5891997-10-0707 October 1997 Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1 ML20211D8441997-09-17017 September 1997 SER Approving SG 90-day Rept Submitted by Duquesne Light Co for Beaver Valley Power Station,Unit 1,per GL 95-05 ML20216J5861997-09-0404 September 1997 Safety Evaluation Re Third 10-year IST Program.Approves Valve Relief Requests 1,3 & 4.Valve Relief Request 2 Not Required.Authorizes Pump Relief Requests 1,2,3 & 4 ML20148E1051997-05-28028 May 1997 Safety Evaluation Supporting Amend 204 to License DPR-66 ML20137X1441997-04-0909 April 1997 Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule ML20057B0641993-09-13013 September 1993 Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of Plant ML20056F3561993-08-12012 August 1993 Safety Evaluation Granting Licensee 930607 Request for Relief from Certain ASME Code Requirements for Temporary Repairs to Svc Water Sys ML20126H7601992-12-30030 December 1992 Safety Evaluation Approving Valve Relief Requests VRR-27, VRR-43 & VRR-44 & Will Provide Reasonable Assurance of Operational Readiness of Valves to Perform Intended Functions.Relief Request PRR-11 Cannot Be Approved ML20127P2081992-11-20020 November 1992 SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance ML20248D7681989-09-29029 September 1989 Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys ML20247N3561989-05-30030 May 1989 SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing ML20246M1791989-05-10010 May 1989 Safety Evaluation Re Verification & Validation Plan for Plant Safety Monitoring Sys.Hardware Design of Sys Found Acceptable.Verification & Validation Plan Found Incomplete & Unacceptable.Software Design Process Inadequate ML20246D5501989-04-26026 April 1989 Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for Unit ML20206G0431988-11-17017 November 1988 Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 Closed ML20153C0911988-08-17017 August 1988 Safety Evaluation Re Licensee 870731 Comments on Sser 5, Section 9.5.1.Fire Protection in Cable Rooms & Containment Constitutes Acceptable Deviations from Branch Technical Position Cmeb 9.5-1 ML20205T0021988-08-10010 August 1988 SER Accepting Util 831104,840330 & 870504 Responses to Item 2.2.1 of Generic Ltr 83-28 Re Equipment Classification Programs for All safety-related Components ML20154R4451988-05-31031 May 1988 Safety Evaluation Re Compliance W/Atws Rule 10CFR50.62.Util Proposed Design Acceptable Subj to Final Resolution of Tech Spec Issue ML20154P4341988-05-24024 May 1988 Safety Evaluation Concluding That Proposed Tech Spec Change Acceptable.No Amend Issued Since Conditions Resulting in Need for Amend to License NPF-73 No Longer Exist ML20154F9901988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 880322 Response to Open Issues Identified in 860722 Draft Technical Evaluation Rept of 840330 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20154F9841988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 851114 Response to Open Issues Noted in 851017 Draft Technical Evaluation Rept of 831104 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20153B6291988-04-25025 April 1988 Safety Evaluation Granting Util 870616 & 871110 Requests for Inservice Insp Relief for Welds on Nonregenerative Hxs,Per 10CFR50.55a(g)(6)(i) ML20148K5231988-03-18018 March 1988 Safety Evaluation Supporting Util Inservice Testing Program & Requests for Relief ML20234E0531987-12-0808 December 1987 Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change Unnecessary ML20236X4941987-11-0909 November 1987 Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal Surfaces ML20237B1651987-10-21021 October 1987 Safety Evaluation Supporting Elimination of Primary Component Support Snubbers from Primary Coolant Loops ML20204H7181987-03-18018 March 1987 Interim Safety Evaluation Re Pump & Valve Operability Assurance (SER Confirmatory Issue 13).Pages from Pvort Audit Encl ML20206G2231987-03-12012 March 1987 SER Accepting Licensee Request to Use Damping Values from ASME Code Case N-411 Per Conditions Outlined in Util ML20207P6551987-01-0202 January 1987 SER Accepting Licensee Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing ML20212B0111986-11-30030 November 1986 Safety Evaluation Granting Util Request for Exemptions from App R Requirements Re Separation of Cables & Equipment & Associated Circuits ML20205G4491986-08-31031 August 1986 Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20204G9281986-07-31031 July 1986 Safety Evaluation Supporting Util 860502 Submittal of Westinghouse Reload Safety Evaluation,Beaver Valley Nuclear Plant,Unit 1 Cycle 6 ML20203G2371986-07-28028 July 1986 Interim SER Re Dcrdr Summary Rept & Preimplementation Audit on 860211 & 12.Requirements of Suppl 1 to NUREG-0737 Generally Satisfied.Several Items Remain to Be Completed ML20206H4931986-06-19019 June 1986 Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable ML20205N1151986-04-22022 April 1986 Interim Rept Re Review of Util Response to Generic Ltr 85-12 on Reactor Coolant Pump Trip Criteria.Addl Info Required ML20202C5721986-04-0303 April 1986 Sser Accepting Util 860304 Response to Generic Ltr 83-28, Item 4.3, Seismic Qualification of Shunt Trip Components ML20214E3631986-03-17017 March 1986 Safety Evaluation Supporting Amend 2 to CPPR-105 ML20154N7451986-03-10010 March 1986 Safety Evaluation Supporting Util 850819 Request to Withdraw Original Commitment to Provide Steam Leakage Collection Sys Around Certain Steam Valves 1999-04-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
[Table view] |
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ENCLOSURE SAFETY EVALUATION REPORT ALTERNATIVE PLAN FOR THE PRESERVICE EXAMINATION OF CLASS 2 PIPING DUQUESNE LIGHT COMPANY (DLC)
BEAVER VALLEY UNIT 2 DOCKET NO. 50-412 A
MATERIALS ENGINEERING BRANCH INSERVICE INSPECTION SECTION I. INTRODUCTION This report was prepared with the technical assistance of DOE Contractors from the Idaho National Engineering Laboratory. _ _ ,
In a letter dated October 19, 1984, the Applicant requested staff approval to utilize'the ASME Code Section XI 1983 Edition, Winter 1983 -
Addenda (83W83) for the selection and examination of Class 2 piping welds at Beaver Valley Unit 2. Since this document is not referenced in -
10 CFR 50.55a(b), specific staff approval is required. The subject was discussed during a public meeting in Bethesda, MD on December 12, 1984.
Based on additional evaluations, DLC withdrew the request for use of the 83W83 Addenda and submitted a revised Class 2 piping examination plan in a ,
letter dated January 31, 1985. This re. vised plan (the Plan) incorporates the ASME Code Section XI 1980 Edition, Winter 1980 Addenda (80W80) and 1974 Edition, Summer 1975 (74S75) requirements as referenced in }
4 10 CFR 50.55a(b) and includes additional welds for examination based on s" g
the 83W83 Code for compatibility with anticipated ISI requirements. f
?
R A technical evaluation of the concepts described in this revised plan y follows. When the complete PSI Program, including isometric drawings, is
{i submitted for review, an evaluation of the entire program will be per- g formed by the staff, including confirmation that a representative sample ;
I 5-
'5
?
3 L . . . _ . . _ _ _ _ _ . . . . _ 2
+
of welds has been selected for volumetric examination and the Applicant was able to distribute the total number of volumetric examinations among the various diameters of pipe within a system.
II. CODE REQUIREMENTS The construction permit for Beaver Valley Unit 2 was issued on May 3, 1974.
Paragraph 10 CFR 50.55a(g)(2) requires the use of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda in effect six months prior to the date of issuance of the construction permit. In the partial PSI Program submitted June 29, 1984, the Applicant stated that in accordance with these requirements, the Beaver Valley Unit 2 Program must comply with the requirements of the 1971 Edition of ASME Code Section XI with Addenda through Winter 1972. However, as permitted by the 10 CFR 50.55a(g),the Applicant had elected to voluntarily update the Code requirements to the 1980 Edition of Section XI with Addenda through Winter 1980 and, as required by 10 CFR 50.55a(b)(2)(iv) for Class 2 piping welds, apply the-1974 Edition with Addenda through Summer 1975 for selection of welds to be examined in the Residual Heat Removal (RH") systems, Emergency Core Cooling systems (ECCS),
and Containment Heat Removal (CHR) systems. The sampling criteria,-locations
-of welds to be examined and method of examination are different in the
. 74S75, 80W80 and 83W83 Addenda of Section XI.
L III.
SUMMARY
OF JANUARY 31, 1985 SUBMITTAL The Plan utilizes the 80W80 Code for' volumetric and surface examinations along with the 74S75 Code to select the welds in the Residual Heat Removal System, Emergency Core Cooling System, and Containment Heat Removal Systems. The Applicant provided the attached Table to summarize the con-
.cepts used in the Plan for the preservice examination by comparing the required examinations with the proposed alternative plan.
Y: ,
' I
', The 83W83 Code is used for guidance to select additional welds for examination to provide compatibility with anticipated ISI requirements.
A 10 percent sample criteria for stainless steel systems is utilized in lieu of the 7.5 percent sample criteria defined in the 83W83.
The Plan includes preservice ultrasonic examination of welds in high energy fluid systems subject to augmented ISI. These welds are located in the identified Break Exclusion Zone for the main steam system (MSS), feedwater system (FWS), and steam vent system (SVS), located outside containment.
The Plan increases the total number of volumetric examinations as compared with the 80W80 Code (with 74S75) and results in a total number of examinations which exceed the 80W80 Code total number of examinations, even when examinations are deleted for welds which would receive only a surface examination per the 80W80 Code. Deletion of the 80W80 Code
" unique", " surface only" examinations (399 welds) is requested as examination-of these welds may not be required by future Code edition and addenda.
IV. STAFF EVALUATION s
The regulations provide the Applicant with several options regarding the choice of the ASME Code edition. The Applicant recognized that following these requirements during the preservice inspection could result in the selection of welds and methods of examination that may be significantly different from possible requirements for the inservice inspection. In this event, a. baseline examination would not exist and the outside surface of the weld would not be profiled for volumetric inservice examination.
Therefore, the Applicant formulated an alternative plan that is intended to be equivalent or superior to the applicable Code requirements referenced in 10 CFR 50.55a(b).
,,__ - ..e- - -
r<-
m . .
_4-The ASME Code published revisions to the requirements for the examination of Class 2 piping in the Winter 1983 Addenda to address discussions with the NRC management that started in 1977. However, this Addenda has not yet been referenced in 10 CFR 50.55a(b). The 83W83 Code reduces the number of exclusions, eliminates most of the " surface only" examinations that are not effective and provides a better distribution of examinations among welds. One objective was to provide comprehensive Code rules that
-may be substituted for the variety of composite-Code approaches illus'trated in the attached Table.
The staff has evaluated the Applicant's revised Class 2 piping examination plan dated January 31, 1985. The submitted information was L
conceptual and did not include isometric drawings that would permit an
. independent review. Thus, the following evaluation is based on Applicant's interpretation of the Code requirements and his analysis of
-lines and welds. Objectives of the staff's review are to assure that a representative sample of welds is selected and appropriate examination techniques are used.
~
- 1. The Plan includes all welds which.are required to receive both volumetric and surface examinations per the 80W80 and .74S75 Code requirements. This includes-89 stainless steel and 29 carbon steel welds.
- 2. -Additional stainless steel welds for both volumetric and surface examinations are included by applying the 83W83 Code rules with an.
. augmented 10 percent sampling criteria in lieu of the specified 7.5 percent sample. This adds 155 more stainless steel and 10 more carbon steel welds. Previous Code editions and addenda often resulted in exempting entire engineered safety systems from C
m ..; -
3=
y
_g_ l l
l l
volumetric examinations as illustrated on sheet 1 of the Table.
-This was'the subject of staff- Question 250.1 which states .in part:
" Paragraph 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the Residual Heat Removal Systems, Emergency Core Cooling l I . ' Systems'and Containment Heat Removal Systems shall be examined.
These systems should not be completely exempted from preservice
-volumetric examination based on Section XI exclusion criteria contained in IWC-1220". The proposed 83W83 Code additions satisfy
-this question.' l
- 3. The Plan adds 195 volumetric-only examinations for carbon steel 1 systems subject to augmented ISI and states that the ultrasonic.
method will be used. 7 1
- 4.- .-The Plan. requests' dropping all surface-only examinations that would be required uniquely,by the.80W80 Code requirements and deletes 375
- stainless steel'and 24 carbon. steel welds. The additional volumetric' examinations covered in paragraphs 9-and 3 above, which are better suited for detection of' inservice degradation, compensate for this-requested deletion of surface-only examinations.
I
- 15. The Plan significantly increases the number' of volumetric examina-
.tions when compared with the 80W80 Code rules. By adding the 83W83~
Code sampling criteria,-the volumetric examinations better. distributed among systems of. interest. For. example, welds in the High Pressure
- c Injection System thac are 2 inch through 4 inch NPS and with wall
- > thickness greater than 1/5 inch are included for examination whereas-
.the earlier Code editions and addenda exempted these welds.
- 6. The additional 83W83 Code examinations provide for.better compat-
, .ibility between the PSI baseline and anticipated ISI requirements.
1 Syd
~- -
IV. CONCLUSION The staff-has determined that methodology in the alternative plan for
-the preservice examination of Class 2 piping, as described in the Applicant's letter of January 31, 1985, is equivalent or superior to the requirements of the applicable Codes referenced in 10 CFR 50.55a(b) and therefore meet the provisions of 10 CFR 50.55a(a)(3). The Applicant's Plan includes the following features:
. 1. A preservice volumetric examination will be performed on engineered safety systems that could be excluded from v'olumetric and surface examinations based on paragraph IWC-1220 of Section XI, 74575 Code.
- 2. A preservice volumetric examination will be performed on high energy fluid system subject to augmented inservice inspection.
- 3. A large number of Code-required " surface only" examinations will be eliminated. Surface examination techniques alone are not normally effective in the early detection of inside diameter service-induced degradation of welds in the pressure boundary.
- 4. A greater number of preservice volumetric examinations will be performed and the distribution of welds should be superior to.the requirements of the 80W80 Addenda.
( -
.=.. .
Therefore, the staff has concluded that the Applicant's proposed plan is acceptable for the preservice examination. The staff intends to review the complete Preservice Inspection Program when the document is submitted and confirm that the Applicant was able to distribute the total number of volumetric examinations among the various diameter of pipe within a system. The requirements for inservice inspections are established by the regulation based on the date of issuarce of the operating license.
The staff assumes that the Applica1t will be permitted to select Class 2 piping welds during the initial 10 year inspection interval at locations with a preservice baseline. The staff review of the Applicant's proposed preservice inspection methodology is not intended to modify the staff review of high energy fluid systems described in FSAR Section 3.6.
- ATTACllMErlT l' . jL TABLE 1 .
CLASS. 2. PIPING WELD EXAMINATION SIMMARY SHEET .
Sect. XI, Table IWC-2500-1, Exam. Cat. C-F-1 .
(Sheet 1 of 2)_ '
STAINLESS STEEL SYSTEMS:
1 2 3 4 5 6 7- 8 9 10 11 12 13 14 74S75 Sect. XI Rules' 83W83 Sect. XI Guidance Using 104 Selection Nonexempt Welds ISI Req'd Exams Nonexempt Welds ISI Reg'd Exams I vol i i vol I I vol I i 10.01 I ' vol System Surf + and = Total Surf + and = Total Surf + and + Exam = Total As % of Prorata =' Surf + and Only i Surf i Only i Surfi Only i Surf l N/A SS Welds Share i Onlyi Surf CHS 108 0 108 52 0 52 526 431 108 1065 41.009 107 59 48 QSS ------- Exempt IRC - 1220 (b) --------- 0 47 125 172 6.623 17 0 17 212 2 214 107 1 -108 0 64 203 267 10.281 27 0 27 RHS RSS ------- Exempt IWC - 1220 (b) --------- 0- 126 28 154 5.930 15 0 15 SIS 342 151 493 217 88 305 176 494 269 939 36.157 94 26 68 Su total 815 376 89 465 702 1162 733 2597 100 260 85 175 662 153 NOTES: A. 10CFR50.55a(b) (2) (iv) ' invokes requirements to use the 74S75 Code for the- above systems to deter-mine. only exemption criteria (IWC-1220) and selection criteria (IWC-2411 and Table IWC-2520, Cat. C-F and C-G). The preservice requirement and the specific required examination method remain in accordance with the Code of choice, namely 80W80.
B. The high number of' welds in the CHS and SIS Systems which are candidates for surface and not volumetric examinations under the 83W83 Code is due largely to the fact that 2" NFS lines in these systems are of socket weld construction.
C. Exemption IWC-1220 (b) : Components in systems or portions of systems, other than emergency core cooling systems, which do not function during normal reactor operation.
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e ,
. TABLE.1 .
CLASS.2 PIPING WELD EXAMINATION SISO4ARY! SHEET 1 ,*J '
Sect. XI, Table IWC-2500-l',: Exam. Cat. C-F-2 ,
(Sheet 2 of 2)
~ CARBON STEEL SYSTEMS: ,
1 2 3' 4 'S 6- '7 8 9' 10 11- 12 13 14 I
80W80' Sect. XI Rules 83W83 Sect.'XI Rules Nonexempt Welds ISI Reg'd Exams Nonexempt Welds ISI Req'd Exams i Vol il l Vol I I Vol I I 7.5% ' vol
. Sy::tcm Surf + and' = Total Surf + and = Total Surf + and + Exam'= Total . As & of Prorata = Surf + and.
Onlyi Surfi Onlye Surf i Onlyi Surfa N/Ae CS Welds Share i Only i surf FWS. 0 $2 52 0 13 13 0 52 0 52 27.660 8 0 8 MSS ,3 71 74 1 16 '17- 3 71. 0 74 39.361 11. 1 10 SVS 96 0 96 24 0 24 0 62 0 62- 32.979 9 0 9 , i i
Sub tal 99 124 222 25- 29 54 3 185 0 188 100 28 1 27 .
Subtotal 733 2597 260 85 175 662 153 815 376 89 465 702. 1162 ---
SS -
Total 761 274 1037 401 118 519 705 1347 733 2785 ---
288 86 202 ;
NOTE: A decrease of one weld which is required to be volumetrically examined is realized by moving to the ;
83W83 Code (columns 5 and 14) . However this is offset by the fact that the major portion of the nonexempt weld candidates are located in the " break exclusion zone" which is subject-to an augmented volumetric examination program during the operating phase of the plant. Therefore, additional welds will be
~ volumetrically examined during each inservice inspection interval.
Advrntage of Utilizing the 83W83 Code for CS Systems:
. SVS is now included in the population subject to volumetric examination due to inclusion of 3/8" through 1/2" wall under this examination requirement.
. PSI compatability with the ISI Program.