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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 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 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 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
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4 SAFETY EVALUATION BY THE OFFICE OF NUCI FAR REACTOR REGULATION PRESSURl7FD THERMAL SHOCK EVALUATION QUQUESNE LIGHT COMPAMY BEAVER VAL t FY UNIT 2 DOCKET NO. 50-412 1,0 INTRODUCTION By letter dated February 13,1997, the Duquesne Light Company submitted WCAP 14784, Revision 2, " Evaluation of Pressurized Thermal Shock for_ Beaver Valley Unit 2 " which provided the Beaver Valley Unit 2 (GV 2) 10 CFR 50.61 pressurized thermal shock (PTS) assessment regarding the reactor vesselintegrity,- This submittal was provided in response to item 3 of an NRC request for additional information issued October 18,1996, concerning WCAP-14484,
" Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program,"
The PTS rule adop*ed on July 23,1985 and revised on May 15,1991, and December 19,1995 established screening criteria that are a measure of a limiting level of reactor vessel material embrittlement beyond which operation cannot continue without further plant specific evaluation.
The' screening criteria are given in terms of reference temperature, RT,rs, The screening criteria are 270*F for plates and axial welds and 300*F for circumferential welds. The RT,1,is -
defined as:
RT,7s = RT,.ru + ART,13 + M where: (a) RT,erm la the initial reference temperature, (b) ART,7 is the mean value in the adjustment in reference temperature caused by irradiation, and (c) M is the margin to be added to cover uncertainties in the initial reference temperature, copper and nickel contents, fluence, and calculational procedures.
The initial reference temperature is the measured unirradiated value as defined in ASME Code, Paragraph NB-2331, if a measured value is unavailable for the heat of material of interest, a generic value may be used. Generic values are based on the data for materials of all heats that were made by the same vendor using similar processes, Generic values of initial reference temperature for welds are defined in the PTS rule.
The ART,rs depends upon the amount of neutron irradiation and the amounts of copper and nickel in the material and is calculated as the product of a fluence factor and 3 chemistry factor (CF). The fluence factor is calculated from the best estimate neutron fluence at the clad-weld-metal interface on the inside surface of the vessel at the location where tne material receives the highest fluence at the end of the period of evaluation. The CF may be determined using _
credible surveillance data or from the CF tables in the PTS rule. The CFs in the tables are
_. dependent upon the best-estimate values of the amount of copper and nickelin the material.
The term "best-estimate" is not well defined statistically, but has normally been interpreted as the mean of the measured values.
ATTACHMENT g%Y y2 P
- o
3c
.4-2 The revised PTS rule cordains criteria for determining whether surveillance data is credible.
The rule also contains the procedure for calculating the vessel weld CF from the adjusted nr measured values of ARTns. Specifically, the rule states that if there is clear evidence that the copper and nickel content of the surveillance weld differs from that of the vessel weld, the measured values of ARTn, should be adjusted by multiplying them by the ratio of the CF of the vessel weld to that of the surveillance weld The CF is calculated by multiplyi_ng each adjusted or measured value of ARTns by its corresponding fluence factor, summing the products, and dividing by the sum of the squares of the fluence factors. The resulting CF will give the relationship of ARTn, to fluence that fits the plant surveillance data in such a way as to minimize the sum of the squares of the errors.
The margin term is intended to account for variability in initial reference temperature and the adjustment in reference temperature caused by irradiation. The value of the margin term is dependent upon whether the initial reference temperature wr.s a measured or generic value and whether the adjustment in reference temperature was determined from credible surveillance data or from the CF tables in the PTS rule.
2.0 DISCUSSION The BV 2 reactor vessel beltline includes the intermediate sheH plates B90041 and B9004 2 (heat identification numbers C05441 and C0544-2, respectively), the lower shell plates B9005-1 and B9005-2 (heat identification numbers C1408-2 and C1408-1, respectively), the intermediate and lower shell vertical seams, and the girth weld between the intermediate and lower shell plates (all welds were fabricated using weld wire heat identification number 83642).
The material with the greatest amount of embrittlement (limiting material) is plate B90041.- The limiting plate in the BV-2 reactor vessel beltline, B9004-1, has an initial reference temperature value of 60*F. The licensee's best estimate values of the amount of copper and nickelin the limiting plate for BV-2 are 0.07% and 0.55%, respectively. Linear interpolation of the CFs in -
Table 1 of the PTS rule indicates that the CF is 44 degrees F. The best estimate values of copper and nickel are mean values from the plate certification test and the Combustion Engineering analysis from a sample obtained at 1/4 thickness of the plate.
The licensee calculated the margin value for the limiting plate in accordance with the methodology in 10 CFR 50.61. The standard
.. deviation of the initial reference temperature (RTery) is zero since the RT.1% is a measured value. The standard deviation for the adjustment in the reference temperature for the plate is 17 degrees F. The licensee calculated a margin value of 34 degrees F. This value is -
acceptable since it was calculated in accordance with the methodology in 10 CFR 50.61.
The RTns value calculated by the licensee for the limiting plate at EOL is 149 degrees F. The RTns value calculated by the staff for BV-2 is 148.48 degrees F. The staff's value is calculated using (a) a measured value of the initial reference temperature, (b) best-estimate value of
F 4
i l 3 copper and nickel for the vessel ste, (c) a CF determined from the CF table for plates in 10 i
CFR 50.61, (d) an EOL neutron fluence of 3.85E19n/cm', and (e) a margin value of 34 degrees ,
F, The slight difference between the staffs and the licensee's RTpt, values is due to round off -
error (149 degrees F calculated by the licensee and 148.48 degrees calculated by the staff).
, The intermediate shell plate, B9004 2, is the surveillance program base metal material for BV 2.
l- The chemistry data for B9004 2 was obtained from material test certifications from the original fabricatiori The staff independently verified that the surveillance data for this base metal was l
credible. This is explained in detail, below, in addition, the staff verified that the RTpre value for j the intermediate shell plate, B9004-2, is significantly lower than the RTer, value for the limiting L plate, i
Th9 chemistry data for the best-estimate chemistry for the beltline welds were obtained from i their surveillance welds, material test certifications from the original fabrication, as well as the two additional material chemistry tests performed for St. Lucie Unit 2 and Almaraz Unit 2. The BV 2 surveillance weld and the St. Lucie Unit 2 and Almaraz Unit 2 welds were made of the same weld wire heat identification number and flux type as the intermediate and lower shell vertical seams and the girth weld between the intermediate and lower shell plates for BV 2
- (3/16 inch diameter weld wire type B-4, heat number 83642, Linde 0091 flux, lot number 3536),
i The licensee revised the best-estimate chemistry for the beltline welds in WCAP-14784, Revision 2. The licensee added two new data points of copper / nickel values for the weld metal i (0.04% Cu/0.06% Ni and 0.03% Cu/
l 0.06% Ni) sad removed the last data point of the weld metal copper / nickel values (0.04%
l Cul0.07% Ni) that had been previously reported. The revised values were indicated in i Attachment 2 of the Florida Power & Light Co. letter, JPN-PSL-SESP-93-47 Revision 0, ' Table i 1: St. Lucle Unit 2 Reactor Vessel Beltline Weld Material."
I As a result of the revised chemistry data, the licensee's best-estimate chemistry for the beltline
- welds and surveillance welds are 0.05% Cu and O.07% Ni. According to Regulatory Guide (RG) 1.99, Revision 2, the chemistry factor for welds with this chemistry is 34.1 degroes F. The weld samples have low Cu and Ni values and the i RTpr values for the weld metal is significantly lower than the RTpts value for the limiting plate.
Therefore, the changes in the Cu and Ni values are not significant in '5is assessment, l The licensee found the base metal and weld surveillance data to be credible. However, the i method of determining credibility did not satisfy Regulatory Guide 1.99, Revision 2, because the
'1 east squares" method for curve fitting -
- cf the best-fit line did not go through the origin for the BV-2 surveillance data. As a result, the staff independently performed the "least squares" method for curve fitting with the best fit line going through the origin.
. Credibility Criterion (C) in section (c)(2)(i) of 10 CFR 50.61 indicates that the scatter of the measured ARTpr3 values must be less than 17 degrees F for base metals and 28 degrees F for
{.
4 welds. Evaluation of this criterion was the basis for the licensee's dete mination that the BV-2 base metal and weld surveillance data met the credibility criteria in 10 CFR 50.61. As stated ,
l 4
3
.- --- = . .,- , , , , . - . , , , , . _ - , ,,
t 4
above, the staff independently evaluated the scatter of the measured ARTp13, and determined that the base metal and weld surveillance data satisfy Criterion (C) in section (c)(2)(i) of 10 CFR 50.61. In addition, the licensee's calculated CFs are in agreement to the staffs calculated CFs (approximately 35.3 degrees F for plates and 15 2 degrees F for welds). Hence, the surveillance data are credible and should be used to determine the CF for the base metal and vessel weld.
The licensee's chemistry values for the weld heat identification number 83642 are 0.05% Cu and 0.07% Ni. The chemistry values for this heat in the Combustion Engineering Owners Group Final Report, CE NPSD-1039, Revision 02, are 0.046% Cu and 0.086% Ni. Because the difference in the chemistry values is small, the change in the RTpy, value for the subject weld is not significant.
The staff verified that all of the beltline region materials in the BV 2 reactor vessel have EOL RTpys values well below 149 degrees F at EOL (32 EFPY).
3.0 CONCLUSION
The licensee and staff assessment indicate that the reactor pressure vessel would be below the PTS screening criteria at the expiration of its license.
6 References
- 1. Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2, May 1988.
- 2. NUREG-0800, Standard Review Plan, Section 5.3.2: Pres'. re-Temperature Limits.
- 3. Code of Federal Regulations, Title 10, Part 50, Appendix G, Fracture Toughness Requirements.
j 4. Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor
- Vessel Materials and its impact on Plant Operations, July 12,1988.
- 5. ASME Boiler and Pressure Vessel Code, Section Ill, Appendix G for Nuclear Power Plant Components, Division 1, " Protection Against Non-ductile Failure."
- 6. WCAP-9615 Revision 1, "Duquesne Light Company Beaver Va! ley Unit 2 Reactor Vessel Radiation Surveillance Program," S.E. Yanichko, et. al., September 1989.
- 7. WCAP-14484, "Anelysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," P.A. Grendys, et al., February 1996.
- 8. Attachment 2 to JPN-PSL-SESP-93-47 Revisicn 0, " Table 1: St. Lucie Unit 2 Reactor Vessel Beltline Weld Material."
- 9. Letter Report MT/ SMART-210(88), " Response to U.S. Nuclear Regulatory Commission Generic Letter 88-11 for the Beaver Valley Unit 2 Reactor Vessel," N.K. Ray, et al.,
November 1988.
- 10. WCAP-9228," Central Nuclear de Almaraz, Almaraz Unit No. 2 Reactor Vessel Radiation Surveillance Program," P.J. Fields, et. al.,
December 1977.
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SALPINPUT FACILITY NAME Beaver Valley, Unit 2 3UMMARY OF REVIEW ACTIVITIES By letter dated February 13,1997, the Duquesne Light Company (the licensee) submitted WCAP 14784, Revision 2, " Evaluation of Pressurized Thermal Shock for Beaver Valley Unit 2,"
which provided the revised Beaver Valley Unit 210 CFR 50.61 pressurized thermal shock assessment regarding the reactor vesselintegrity. The cubmittal was provided in response to item 3 of the NRC request for additionalinformation issued October 18,1996, concerning WCAP-14484, " Analysis of Capsule V for the Duquesne Light Ccmpany Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program."
The staff concluded that the Beaver Valley Unit 2 reactor vessel is projected to be below the PTS screening criteria at the expiration of its license.
NARRATIVE DISCUSSION OF LICENSEE PERFORMANCE FUNCTIONAL AREA Enaineerina/ Technical Supp. pit The licensee svas very responsive to the staffs requests for assistance and clarification on minor technicalissues. The staff noted that the licensee provided good supporting technical information in their submittal. In addition, sufficient data and information was provided by the licensee to conduct an independent review of the PTS assessment.
Principal Contributor: M. Khanna (301)415-2150 i
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