Safety Evaluation Accepting Clarification of Previous Reactor Vessel Surveillance Program Actions & Withdrawal Schedule Change for Reactor Matl Surveillance CapsuleML20127C057 |
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Site: |
Calvert Cliffs |
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Issue date: |
12/23/1992 |
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From: |
Office of Nuclear Reactor Regulation |
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To: |
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Shared Package |
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ML20127C053 |
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References |
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NUDOCS 9301130277 |
Download: ML20127C057 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20217Q7971998-05-0404 May 1998 Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively ML20217P7441998-04-0707 April 1998 SE Accepting Licensee Request for Second 10-yr Insp Interval to Use ASME Section IX Code Case N-416-1, Alternative Pressure Test Requirement for Replacement Items by Welding, Class 1,2 & 3,Div 1 at Plant Per 10CFR50.55a(a)(3)(i) ML20203E9741998-02-11011 February 1998 SER Accepting IST Program Requests for Relief Submitted for Third 10-yr Intervals for Pumps & Valves for Plant ML20198K3741998-01-0505 January 1998 Safety Evaluation Authorizing Second 10-yr ISI Interval for Plant,Units 1 & 2 Relief Request from ASME Boiler & Pressure Vessel Code Requirements to Use Performance Demonstration Initiative Program ML20197G1291997-12-15015 December 1997 Safety Evaluation Accepting Revised Withdrawal Schedules for Plant,Units 1 & 2 ML20134G5291997-02-0707 February 1997 Safety Evaluation Re Request Relief from ASME Code Requirement for Calvert Cliffs Nuclear Power Plant,Unit 1 ML20058G0561993-11-29029 November 1993 Safety Evaluation Granting Relief from Installation Requirements of Section Iii,Article 9 of 1968 Edition of ASME Boiler & Pressure Vessel Code for Plant ML20057C3831993-09-22022 September 1993 Sser Accepting Licensee 930707 Response to Station Blackout Rule,Per 10CFR50.63 ML20127C0571992-12-23023 December 1992 Safety Evaluation Accepting Clarification of Previous Reactor Vessel Surveillance Program Actions & Withdrawal Schedule Change for Reactor Matl Surveillance Capsule ML20128B9371992-11-20020 November 1992 Safety Evaluation Accepting Licensee Response to Suppl 1 to GL 87-02 IR 05000317/19900801990-11-21021 November 1990 SER Determining That Load Profile Used During Surveillance Test Procedure Meets Requirement of Tech Spec 4.8.2.3.2.e, Per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 ML20059N2251990-10-0101 October 1990 Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 ML20245E8561989-06-22022 June 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20247D0361989-03-24024 March 1989 Safety Evaluation Supporting Amend 119 to License DPR-69 ML20205P6491988-11-0202 November 1988 Safety Evaluation Re Compliance w/10CFR50.62 ATWS Rule. Auxiliary Feedwater Actuation Sys Designs in Conformance W/ Requirements of TMI Action Plan Item II.E.1.2,surveillance Testing,Complies W/Atws Rule ML20238A3141987-08-24024 August 1987 Safety Evaluation of Encl Technical Evaluation Repts EGG-NTA-7243,EGG-NTA-7720 & EGG-NTA-7463 & Licensee Submittals in Response to Generic Ltr 83-28,Items 2.1.1, 2.1.2 & 4.5.2.Responses Acceptable ML20213E8731987-05-11011 May 1987 Safety Evaluation Supporting Util 861002 Request for Relief from Inservice Insp Requirements of ASME Code Section XI Re Peripheral CRD Housings ML20205R7061987-03-26026 March 1987 Safety Evaluation Supporting Relief from Certain ASME Code Hoop Stress Requirements Until Next Refueling Outage to Repair Flaw in Base Metal of Steam Generator Main Steam Line 12 ML20210P0911987-02-0404 February 1987 Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Util Must Submit Reevaluation of Resistance Temp PTS ML20207P0721987-01-0606 January 1987 Safety Evaluation Supporting Conformance to Reg Guide 1.97 W/Noted Exceptions ML20198G6971986-05-22022 May 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20210P2801986-05-0606 May 1986 Safety Evaluation Accepting Licensee Response to Items 3.1.3 & 3.2.3, Post-Maint Testing of...Safety-Related Components, of Generic Ltr 83-28 ML20202E0721986-03-31031 March 1986 Safety Evaluation Supporting Amend 116 to License DPR-53 ML20141N7691986-03-10010 March 1986 Safety Evaluation Granting Util 850913 & 860113 Requests for Relief from ASME Boiler & Pressure Vessel Code,Section XI Re Observation of Lubricant Level or Pressure During Pump Testing ML20136G7371985-11-14014 November 1985 Safety Evaluation Granting Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirement Re Pressure Testing of Class 2 Piping Associated W/Rcs ML20138E2821985-10-10010 October 1985 Safety Evaluation Re Extended Burnup of C-E PWR Fuel. Methodologies Acceptable for Extended Burnup Application ML20137W8811985-09-18018 September 1985 Safety Evaluation Granting Relief from Radiographic & Visual Insp of Reactor Coolant Pump Casings ML20126L8241985-07-18018 July 1985 Suppl to Safety Evaluation Supporting Response to IE Bulletin 80-11 Re Reevaluation of 22 Masonry Walls,Utilizing Methods Other than Energy Balance Technique ML20133E1101985-07-18018 July 1985 Corrected Suppl to Safety Evaluation Accepting Util 850612 Reevaluation of Masonry Wall Design Using Linear Elastic Methodology.Action Completed on IE Bulletin 80-11 ML20205B2591985-07-10010 July 1985 Safety Evaluation Accepting Licensee Position on Generic Ltr 83-28 Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability ML20127N2351985-05-0909 May 1985 SER Re NUREG/CR-3511, Interim Reliability Evaluation Program:Analysis of Calvert Cliffs Unit 1 Nuclear Power Plant. Use of PRA Results Out of PRA Context Clearly Inappropriate ML20132B8731984-03-21021 March 1984 SER on Multi-Plant Action C-14 Re Seismic Qualification of Auxiliary Feedwater Sys ML20148A9641978-01-0404 January 1978 Safety Evaluation Supporting Amends 27 & 12 to Licenses DPR-53 & DPR-69,respectively 1999-07-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
[Table view] |
Text
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CLARifl( M l0lL0f PREV 1QVS REACTOR VESSEL SURVEILLANCE PROGRAM ACTIONS AND i
WITHDRAWAL SCHEMLE CHANGE FOR REACTQR MATERI AL SUREE1LLAN[L(AP_5MLE BAL11MORL GA,S E D ELECTRIC COMPANY
[ALVERT Cliffs ffVCLEAR POWER PL ANT. UNIT NOS.1 AND 2 DOCKET NQS 50-317 AND 50-318 1.0 INIRQDEHQN Appendix H of 10 CFR Part 50 specifies the requirements for reactor vessel material surveillance programs. The purpose of these programs is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors. The programs are used to determine the effects of neutron irradiation and thermal stresses on the vessel materials. Each of the Calvert Cliffs reactor vessels contain six surveillance capsule assemblies which contain reactor vessel material test specimens. The six surveillance capsules have approved withdrawal schedules which span the 40-year license period of each reactor.
By letter dated August 28, 1992, Baltimore Gas and Electric Company (BG&E) provided clarification on previous reactor vessel surveillance program actions and requested Commission approval for a change to the withdrawal schedule for the Unit 2 reactor vessel material surveillance capsules.
This safety evaluation (SE) will assess the significance of the clarification provided by BG&E relating to previous actions taken and their impact on the reactor vessel material surveillance program at the Calvert Cliffs facility and the request for a change to the withdrawal schedule for the Unit 2 reactor vessel material surveillance capsules. The requested change in the withdrawal schedule was submitted pursuant to Appendix H of 10 CFR Part 50.
Section ll.B.3 of Appendix H to 10 CFR Part 50 requires that proposed withdrawal schedules for the material specimens must be provided to the Nuclear Regulatory Commission (NRC), with technical justification, for review and approval prior to implementation.
2.0 [YALVA110N The clarification provided by BG&E in its August 28, 1992, letter indicated that the BG&E letter dated January 20, 1982, was submitted on the Units 1 and 2 dockets and provided justification for withdrawing the first surveillance capsule of each reactor vessel from tne 263 degree location instead of the 97 degree location initially approved in the reactor vessel material surveillance program for each vessel. However, the NRC staff appre,al let u r of february 2,1982, was for Unit 1 only.
7 NOIISbb P
r Since the initial request and justification was for both units, BG&E revised the Final Safety Analysis Report to reflect the change in the withdrawal ,
schedules for both units and the surveillance capsules at the 263 degree locations were removed at the first removal interval for each of the reactor ,
vessels. This error was not identified until the recent update, Revision 13, to the Updated Final Safety Analysis Report (UFSAR) dated July 17, 1992.
The NRC staff has confirmed that the January 20, 1982, letter, which provided the justification for the change in the schedule for withdrawal of the surveillance capsules, was for both Unit I and Unit 2 reactor vessels. i Part 50 of Title 10 of the Code of Federal Regulations, Appendix H, requires that material surveillance programs be in place to monitor fracture toughness properties of ferritic materials in reactor vessel beltline regions. Since the surveillance programs are the same for each vessel, including the surveillance cassules and locations, the NRC staff has determined that the withdrawal of t1e 263 degree surveillance capsule at the first removal interval for Unit 2 has no adverse impact on the ability of the surveillance program to determine the effects of neutron irradiation and-thermal stresses on the reactor vessel materials and is, therefore, acceptable.
BG&E further noted that it had incorrectly stated that the surveillance capsules located at the 263 degree and 97 degree locations were identical when the requested change in the withdrawal schedules were made. This error was ,
also identified during the recent UFSAR update.
Each of the surveillance capsules contains 57 test specimens of which 45 are '
identical. In addition to the identical specimens, the capsules located at the 263 degree location of each reactor vessel contained 12 standard reference material (SRM) test specimens and the capsules located at the 97 degree location of each reactor vessel contained 12 base metal (transverse) ,
specimens.
BG&E has indicated that there is only one more surveillance capsule in each vessel, the 104 degree location, which has SRM. BG&E also notes it is important that the surveillance capsules located at the 104 degree location be withdrawn at later dates to assure that the SRM test specimens have a greater difference in fluence exposure. The greater difference in fluence exposure will result in more meaningful test data when the second set of each reactor vessel's SRM specimens are withdrawn and tested.
The NRC staff has determined that the differences in the materials of the 263 degree location and the 97 degree location has no adverse impect on the sequence of withdrawal and effectiveness of the reactor vessel material surveillance programs to determine the effects of neutron irradiation and-thcrmal stresses on the reactor vessel materials and is, therefore, acceptable. This is based on the fact that the SRM and base metal are not limiting in respect to embrittlement for the Calvert Cliffs reactor vessels.
The axial welds are limiting in relation to embrittlement concerns for the reactor vessels. This was noted in the NRC staff's SE relating to pressurized thermal shock sent to BG&E by letter dated July 15, 1992. The fluence
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exposure for the SRM test specimens has already been addressed for Unit 1 in the NRC letter dated March 11, 1992, which approved the current withdrawal j schedule for Unit 1 and is addressed for Unit 2 in the following portion of l this SE.
I Section 11.B.3 of Appendix H to 10 CFR Part 50 requires that proposed withdrawal schedules for specimens must be provided to the NRC, with technical justification, for review and approval prior to implementation. BG&E >
requested NRC review and approval of changes to the previously-approved withdrawal schedule for the material specimen capsules in the Unit 2 reactor.
Specifically, the request is to switch the capsule at the 104 degree location currently scheduled to be withdrawn at the second withdrawal interval, which will be during the upcoming refueling outage (Rf0-9) in the spring of 1993, with the capsule at the 97 degree location which is currently scheduled to be withdrawn at the. fourth withdrawal interval. This change has already been reviewed and approved for Unit 1. The supporting SE for the Unit I schedule change was provided to BG&E by letter dated March 11, 1992.
The material specimen capsule at the 104 degree location contains SRM Charpy impact specimens. The material specimen capsule at the 97 degree location contains base metal (transverse) Charpy impact specimens. The material specimen capsule at the 263 degree location that was removed during first interval withdrawal, as previously noted, contained SRM Charpy impact specimens which are the same as those contained in the 104 degree location capsule. Deferring the withdrawal of the capsule at the 104 degree location will result in an increase in its exposure to fluence. This in turn creates a greater difference in exposure of the SRM Charpy impact specimens withdrawn during the first interval. BG&E indicates, and the staff agrees, that the greater the difference in the fluence exposures of the two SRM specimens will result in more meaningful data when the second SRM Charpy impact specimen is withdrawn and tested.
3.0 (ONCLUSION The NRC staff has concluded that the clarifications provided by BG&E are acceptable based on the above evaluation. The NRC staff further concludes that BG&E has provided the necessary technical justification required by Section ll.B.3 of Appendix H to 10 CFR Part 50 to support the proposed changes to the withdrawal schedules for the vessel material specimens for Calveri Cliff, Unit 2, capsules. The capsule at the 97 degree location in the Unit 2 reactor will be the specimen withdrawn for the second withdrawal interval and the capsule at the 104 degree location will become scheduled for withdrawal at the end of the fourth withdrawal interval. These changes are consistent with those approved for Unit I and will be reflected in the next UFSAR update.
Principal Contributor:
Daniel G. Mcdonald Date: December 23, 1992
1- \
i Hr. Robert E. Denton December 23,- 1992 i s
location and the 104 degree location capsule will be scheduled for withdrawal at the end of the fourth interval. Details supporting these conclusions are !
included in the enclosed safety evaluation. These approved changes will be ;
reflected in the next update of the Updated Final Safety Analysis Report. i Sincerely, ,
Original signed by:
Daniel G. Mcdonald, Senior Project Manager i Project Directorate 1-1 -
Division of Reactor Projects - 1/11 ,
Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page ,
Distribution:
~ Docket file- DMcDonald
, NRC & Local PDRs JStrosnider, 7/0/4 ,
PDI-l Reading OGC SVarga ACRS (10)
JCalvo Plant File '
RAcapra CCowgill, RGN-1 CVogan i
O nn PDI-1:LA 1DI-1:PO[k EMCB M OGC N PDI-1:0 ,
CVogan M} DMcDonalNmm JStrosbder DGO@gh RACapra d/ N/92 \t /d/92 iL /t1/92 /2-/ 2-292 11/M/92 / /
OFFICIAL RECORD COPY FILENAME: CC85113.LTR
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