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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
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[hKfC UNITED STATES
[ 9, NUCLEAR REGULATORY COMMISSION 5 j W ASHINGTON, D. C. 20555
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SUPPLEMENT TO SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION BALTIM0RE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 MASONRY WALL DESIGN, IE BULLETIN 80-11 In a Safety Evaluation (SE) dated November 21, 1984, the NRC staff concluded that, except for 22 walls (out of a total of 147) qualified by the licensee via the use of the energy balance technique to resist the out-of-plane seismic forces, Items 2(b) and 3 cf IE Bulletin 80-11 have been fully implemented at the Calvert Cliffs facility for the remaining walls. The Safety Evaluation also included a staff position on the energy-balance technique and stated that the implementatior, of this position was required to render the above wa'ils acceptable to the staff.
The licensee met with the staff on April 5, 1985, to discuss its proposed approach to respond to the staff position. The proposed approach was to reexamine the original seismic analysis of the auxiliary building which contains the masonry walls in question and the analysis of the masonry walls themselves to identify existing excessive conservatism above and beyond the current staff acceptance criteria in the area of the seismic analysis. The intent was, then, to account for these excessive conservatisms in the wall 4 analysis and qualify the walls on the basis of linear elastic methodoloqv consistent with the staff acceptance criteria. Based on the information presented at the meeting, the staff found this approach to be acceptable.
By a letter dated June 12, 1985, the licensee has now provided the details and results of its evaluation using the above approach. Based on the recent review of the masonry walls, four of the walls have been reclassified as non-safety relsted walls. The cause for the reclassification is that the failure of these walls will not have any impact on the safety related equipment.
To qualify the remaining 18 walls using the above discussed approach, the licensee has identified several areas of conservatisms in the original analysis. These areas can be divided into two main categories: (1)which affects the seismic analysis of the auxiliary building; and (2) which affects the analysis of the masonry walls. These areas are as follows:
Seismic Analysis of the Auxiliary Building
- Input Time History - the original time history used in the analysis
- i. of the auxiliary building exhibit substantial exceedances over the design spectrum in the range of 1 to 10 Hz.
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- Radiation Damping - The original seismic analysis of structures neglected radiation damping in the soil-structure interaction analysis.
- Embedment Effects - The original seismic analysis also neglected embedment effects in the soil-structure interaction analysis.
Masonry Wall Analysis Response Spectra Modification: The response spectra used in the masonry wall analysis were modified such that peak acceleration level was imposed at all frequencies below the peak frequency.
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- Moment Combination and Beam vs. Plate Atalysis - The external moment and maximum seismic inertial moment are combined in the masonry walls analysis as an absolute sum regardless of their location on the wall. Additionally, the walls have been analyzed as vertical strip rather than plate mechanism.
As-Built Strength of Walls - The certified material test reports indicate that the avera;ie yield strength of #5 reinforcing bar used in the auxiliary building construction is 50.4 ksi as opposed to the specified strength of 40.0 ksi.
From the list of above areas, the licensee selected only those areas for which a " generic" lower bound level of conservatism can be easily and clearly identified. For other items, a wall-by-wall reanalysis would be necessary to L qualify the amount of conservatism. The " generic" items quantified included
! the following areas:
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- Radiation Damping Use of an Improved Time History
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- Actual Versus Minimum Specified Material Strengths ,
i The use of radiation damping, within the guidelines established by the NRC Senior Review Team (Guidelines for SEP Soil-Structure Interaction, NRC letter dated December 15,1980,LS05-80-12-035) provided a peak response that was approximately 40 percent of that obtained from the original analysis. In l
t addition, employing a time history that more nearly meets the design spectra L mquirements resulted in an additional conservatism. In general, a 25 percent reduction in response occurred in the frequency range of interest due to the time history effect. Combining the effects of both the improved time
- history and radiation damping (with no other changes to the seismic analysis) and allowing some conservatism for variations in response between floor levels and directions of response, the licensee reduced the stress level to 40 percent of the original analysis results. Based on actual mill test data which indicates that the yield strength of the reinforcing steel is at least 115 percent of the minimum specified, the licensee also increased the wall capacity proportionally.
Based on the above qualification of the existing conservatism in the masonry wall analysis, the licensee has determined that all but two of the walls can be qualified on the basis of the elastic criteria (consistent with the staff acceptance criteria) when this conservatism is accounted for. The remaining two walls can also be qualified on the basis of the elastic criteria when a
" plate" analysis approach is used rather than "boam" analysis approach.
Based on the review of the above information and discussions with the licensee in the April 5, 1985 meeting, the staff concludes that Items 2(b) and 3 have teen fully implemented at Calvert Cliffs and that there is reasonable assurance that all safety-related masonry walls at the Calvert w
Cliffs facility impairment of (a)ill wall withstand integrity theorspecified design load of (b) the performance conditions the required without function.
Principal Contributor:
N. Chokshi, DE Date: July 18, 1985
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