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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]
Category:TOPICAL REPORT EVALUATION
MONTHYEARML20055H0921990-06-25025 June 1990
Topical Rept Evaluation of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation
ML20236D2621987-10-21021 October 1987
Topical Rept Evaluation of CEN-348(B)-P, Extended Statistical Combination of Uncertainties. Rept Acceptable
ML20239A5461987-09-0909 September 1987
Safety Evaluation Supporting A-85-11, Retran Computer Code Reactor Sys Transient Analysis Model Qualification for Use in Performing plant-specific best-estimate Transient Analyses at Plant
ML20210N7331987-02-0404 February 1987
Safety Evaluation Supporting CEN-161(B)-P,Suppl 1-P, Improvements to Fuel Evaluation Model. Mods to Fission Gas Release & Fuel Thermal Expansion Models Acceptable
1990-06-25
[Table view] |
Text
.. . . . _ -
. [pm Rf Cgh i [',m i UNITED STATES
, r,, . NUCLEAR REGULATORY COMMISSION l WASHINGTON, D. C. 20655
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SAFETY EVALUATION BY TPE OFFICE OF NUCLEAR REACT BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET N05. 50-327 AND 50-318 RELATING TO THE USE OF RETRAN COMPUTER CODE FOR BEST-ESTIMATE TRANS]ENT ANALYSES
1.0 INTRODUCTION
The BG&E Topical Report A-85-11. "RETRAN Computer Code Reactor Syst Transient Analysis Model Qualification", was submitted to demonstrate BG&
capability the RETRAN 02/to perform MOD best 03 Computer Code.estimate thermal-hydraulic transient analysis NRC Generic Letter 83-11. This submittal was made in response to to evaluate Power Plant, Unitsproposed 1 and 2 changes to operating procedures c ear for Calv The 1986 subject topical report was submitted by BG&E in a letter dated Ja In response to staff requests for information, additional supporting ,
materials February 24,were 1987, submitted in BG&E letters dated March 7,1986, and June 9, 1987. December 31
, 1986, BG&E submittals Technical Services, Inc. with technical assistance from its contractors onal at 2.0 COMPUTER MODELING BG&E Topical Re configurations, for Calvert Cliffs as follows: port A-85-11 briefly describes primary and 1
analyze synnetrical transients.RETRAN One Loop Model of Calvert The one loop model explicitly uses a single hot leg, cold leg and reactor coolant pump (RCP) to represent the the Calvert Cliffsofdesign.
combination the two hot legs, four cold legs and four RCPs actually i 2.
analyze loop asymmetric transients.RETRAN Two Loop Model of cold legs are modeled, one for each steam gene representing two cold legs and two RCPs.
Two N) A P
. 3. RETPAN Four Loop Model of Calvert Cliffs - This model was developed to analyze individual cold leg /RCP transients. The four loop model explicitly simulates the two hot legs and four cold legs geometry of the Calvert Cliffs design.
One of the above three models will be selected for analyzing each transient depending upon the expected plant thermal hydraulic behavior during the specific transient.
In response to staff requests, BG&E has provided sufficient information to demonstrate its understanding of the details and limitations of those models.
BG&E utilized the RETRAN 02/ MOD 03 computer code which was a modification of RETRAN 02/ MOD 02. More than two hundred changes were made in this modification.
These changes were a result of 1) user reported errors, 2) changes requested by the Utility Group for Regulatory Application (UGRA) Design Review Team, and 3) changes requested by NRC after the staff review of the RETRAN 02/ MOD 02 for error corrections. In a letter to NRC dated February 4,1985, Mr. T. W.
Schnatz of UGRA stated that the total effect of all those changes made in RETRAN modification as measured by sampling problems used to test each RETRAN version was insignificant in that the differences were well within the uncertainties in the original calculations. This corrected version of the code has not been approved by the staff. Nevertheless, we believe that there is reasonable assurance that this version of the code was adequate for use in this topical report. Unless some future NRC review of RETRAN 02/M0D 03 contradicts this assumption, its use shall be acceptable in the BG&E's best-estimate model.
3.0 VERIFICATION OF RETRAN MODELS FOR CALVERT CLIFFS BG&E has compared the results from analyses using the RETRAN models developed for Calvert Cliffs with actual plant operating data, results from analyses using the TRAC code, and the results from the LOFT tests.
BG&E performed comparisons of the RETRAN model analysis results with actual pisnt operating data for the following scenarios: 1) multiple secondary side malfunction event, 2) four pump coastdown from 20% rower, 3) reactor coolant operation pump combination flow tests at hot zero power, 4) one pump coastdown from 80% pcwer, and 5) total loss of flow / natural circulation test from 40%
power. Various RETRAN models were used in the comparison with the results of the analysis being reasonably close. Sensitivity studies were conducted by BG&E to determine which parameters would affect the transient results.
In comparing the results of the RETRAN model analyses developed for Calvert ;
Cliffs with the results obtained from analyses performed by Los Alamos l National Laboratory using TRAC-PF1 nodalization of the Calvert Cliffs plant, the following cases were reviewed: 1) cooldown to residual heat removal entry using atmospheric steam dump valves and auxiliary pressurizer spray system, and
- 2) runaway main feedwater to one steam generator. Overall, these analyses exhibited similar trends despite large differences in the computer code models
and the degree of detail and capabilities in plant nodalization. BG&E has provided sufficient explanation to demonstrate its understanding of the results from its RETRAN models and of the reasons for differences from the TRAC-PF1 analyses results.
EG&E also compared RETRAN calculations with the data from LOFT Tests L6-1 and L6-3. In the LOFT Test L6-1 comparison the BCEE RETRAN model calculated a primary and secondary pressure transient behavior that did not precisely follow the test results. However, calculated results by RETRAN, with respect to both I
the general trends and the relative magnitudes of the data, are within accep-table bounds. In the LOTT Test L6-3 comparison, there was good agreement in the primary side parameter 3 of the test data and the RETRAN results. Also, the over611 RETRAN model results, calculated with respect to both the general trends and the relative magnitudes of the data, are within acceptable bounds.
4.0 CONCLUSION
The staff has determined that BG&E has demonstrated the capability to properly develop RETRAN models of Calvert Cliffs and perform best-estimate simulation of reactor system non-LOCA transient using these models. Therefore, the staff concludes that BG&E is cualified to use the RETRAN models documented in the BG&E Topical Report A-85-11 for performing system transient calculations to support the evaluations of proposed changes and revisions to operating procedures.
It is noted that BG&E used RETRAN 02/ MOD 03 which was developed as a result of making corrections necessitated after the NRC staff review of the RETRAN 02/ MOD 02 computer code. This corrected version of the code has not been approved by the staff. Nevertheless, we believe that there is reasonable assurance that this version of the code was adequate for use in this topical report and we accept its use in the BG8E's best-estimate model, unless some future NRC review of RETRAN 02/ MOD 03 contradicts this assumption.
PRINCIPAL CONTRIBUTOR:
l C. Liang Dated:
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