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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20248J9901998-05-26026 May 1998 Rev 0 to SIR-98-055, Risk Evaluation & Element Selection in Support of ASME Code Case N-560 ANO-1 ML20217N9101998-03-27027 March 1998 Rev 0 to SIR-98-026, Svc History & Susceptibility Review, Risk Evaluation & Element Selection for Svc Water Sys at ANO-2 ML20217N8771998-03-27027 March 1998 Rev 0 to SIR-98-011, Evaluation of Damage Mechanisms for Svc Water Sys at ANO-2 ML20236J1331998-02-16016 February 1998 Rev 1 to 97-R-2015-01, PPS Response to Failure of DC Bus ML20203D9841997-11-30030 November 1997 ANO Commitment Change Summary Rept for Sept 1995-Nov 1997 ML20211N4631997-10-0707 October 1997 SG Tube Integrity Evaluation ML20154B7501996-11-30030 November 1996 Rev 0, Review of Degradation Mechanisms in EPRI Risk- Informed Inservice Evaluation Procedure ML20135E8141996-11-30030 November 1996 Pressure-Temp Limits for 32 Efpy ML20135D2431996-10-16016 October 1996 Rev 1 to ANO Unit 2 Leak Rate Model for Circumferential Cracks in SG Tubes ML20135D2591996-10-16016 October 1996 Rev 0 to ANO Unit 2 Projected End of Cycle 12 Circumferential Crack Population ML20135D2481996-10-16016 October 1996 Rev 1 to Probability of Burst Model for ANO-2 Tts Circumferential Cracks ML20133M1641996-09-0909 September 1996 Revised OTSG Iga Sizing Technique App H Qualification ML20116F3021996-07-31031 July 1996 Steam Generator Operational Assessment ML20135D2551996-04-11011 April 1996 ANO Unit 2 SG Tubes Evaluation of Bursh Pressures W/Circumferential Flaws Present ML20135D2621996-03-31031 March 1996 ANO Unit 2 SG Tubes:95/95 Mechanical Properties ML20101R5381996-02-28028 February 1996 LTOP for 21 Efpy ML20101H1111996-02-28028 February 1996 Input to Items 2A & 2C of NRC Question on Relief Request for Insp of Transition Piece to Bottom Head Weld of Reactor Vessel at Arkansas Nuclear One - Unit 1 ML20101H1261996-02-22022 February 1996 Flaw Acceptance Stds for Arkansas Nuclear One Unit 1 Reactor Pressure Vessel Weld Insps ML20095C2431995-10-31031 October 1995 ANO Unit 2 Simulator Performance Testing Rept ML20091R6571995-08-31031 August 1995 ANO Unit 2 SG Tube Circumferential Cracking Repair Limit Evaluation ML20082E7541995-03-24024 March 1995 Failure Analysis Rept 3707R MSSV Valve Serial Number BM-02978 Nonconforming Matl - Lower Adjusting Ring Pin at Wyle Lab ML20080H6631995-02-28028 February 1995 ANO Unit 2 SG Circumferential Cracking Evaluation ML20077S0081995-01-17017 January 1995 Simulator Performance Testing Rept ML20063L7551994-02-0101 February 1994 Rev 0 to Twentieth Yr Physical Surveillance of ANO Unit 1 Containment Bldg ML20057D0741993-09-21021 September 1993 ANO Unit 2 Cycle 10,Proposed Changes to Incore Detector Ts ML20057D0711993-09-21021 September 1993 Cycle 10,COLSS & Cpcs Addressable Constants for Reduction of Operable Incore Detectors ML20056E2331993-08-31031 August 1993 Evaluation of Thermal Stratification Effects on Shutdown Cooling Line for Ano,Unit 2 ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML20056E2291993-08-17017 August 1993 SG Degraded Tube Analysis Per Reg Guide 1.121 ML20056D3111993-01-29029 January 1993 Analysis Allowing Extended Operation W/One PPS Channel in Bypass for ANO Unit 2 ML20101K9861992-06-23023 June 1992 Response to NRC Generic Ltr 92-01 for Arkansas Nuclear One - Unit 2 ML20097G0851992-06-0808 June 1992 Rev 0 to ASME Code Case N-481 Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps ML20092C9851991-12-31031 December 1991 Technical Rept, Monitoring Hydrogen Gas in Containment During Early Phases of Severe Accident ML20087A4731991-12-20020 December 1991 Rev 0 to Summary of Entergy Position Re Deferral of Permanent Nozzle Repair for Arkansas Nuclear One,Unit 1 Pressurizer Level Tap Nozzle, Engineering Rept ML20081K9331991-05-31031 May 1991 Final Rept on Low-Temperature Overpressure Protection Analysis for ANO 2 for 21 Effective Full Power Years ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20028H6441991-01-17017 January 1991 ANO Unit 1 Simulator Certification. ML20076B3501990-12-31031 December 1990 Criticality Analysis of Arkansas Nuclear One,Unit 1 Fresh Fuel Rack ML20235N6101989-02-14014 February 1989 Summary of Engineering Evaluation of ANO-1 High Pressure Injection Sys Backflow Condition ML20235T2121989-02-14014 February 1989 Addendum to Amend 6 to SAR for Arkansas Nuclear One Unit 2 ML20206F4041988-10-31031 October 1988 Request for Exemption from ATWS Rule 10CFR50.62 for Arkansas Nuclear One Unit 2 ML20207B2901988-07-0101 July 1988 Vols I & II of Rept, Fifteenth Yr Physical Surveillance of Arkansas Nuclear 1 - Unit 1 Primary Reactor Contatinment Bldg ML20154F6091988-07-0101 July 1988 Ten-Yr Visual Tendon Surveillance of Arkansas Nuclear One, Unit 2 Primary Reactor Containment Bldg,Surveillance Rept ML20151N3001988-04-30030 April 1988 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20147C6491987-12-0303 December 1987 One,Unit-II,Simulator Operability Test ML20147C6291987-11-18018 November 1987 Revised Abstract:Performance Test Development,Conduct & Evaluation ML20238C3071987-08-28028 August 1987 Justification for Continued Operation 1999-05-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO 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 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 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 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 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
[Table view] |
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Enclosure 1 to A-93-026 Page 1 of 5 -
ANO-2 CYCLE 10 COLSS and CPCS Addressable Constants for Reduction of Operable Incore Detectors i
PREPARED BY:
l &% N1.' 9Itil93 Signature / Date S. Etemadi Author VERIFICATION STATUS The information contained in this document has been verified in accordance with the ABB Combustion Engineering Nuclear Fuel ouality Assurance Program.
/ Yes No ABB Combustion Engineering Nuclear Fuel A EDID pggggy 9310010063 930924 P PDR ADOCK 05000368
p PDR i;M
i j .
)
! l i
j Enclosure 1 to l i A-93-026 Page 2 of 5 l ,
i J
I As proposed by CE (Reference 1) and approved by Entergy/ANO, an analysis was
- performed to determine the impact of a reduction in the number of operable- .
incore detectors on the ANO-2 Cycle 10 COLSS and CPCS addressable constants !
transmitted in References 2 and 3. Reference 2 transmitted the original Cycle i 10 00LSS and CPCS addressable constants and Reference 3 provided the revised j BERR1 and BERR3 constants for reduced inlet temperature.
i l
! The analysis considered Technical Specification incore detector failure limits i j of up to 50% along with a bounding 1% increase in the CECOR Fxy measurement !
i uncertainty which is consistent with the analysis performed at Entergy !
(Reference 4). The only addressable constants affected by this analysis are l j the COLSS EPOL2/4 and UNCERT constants and the CPCS BERR1 and BERR3 constants.
All of the other addressable constants transmitted in Reference 2 remain :
unchanged.
l The values of revised COLSS and CPCS addressable constants are given in Tables [
j 1 and 2, respectively. ;
! As stated in Reference 1, the COLSS database constant K09 must be modified to !
j incorporate the revised minimum number of operable incore detectors. It e i
! value of K09 for the 50% failure limit is 110. 1 J
- The COLSS addressable constants listed in Table 1 are appropriate for use with !
l the COLSS algorithms and database constants described in ANO-2 COLSS !
! Functional Design Requirements (References S and 6) and the COLSS Database :
1 Document for ANO-2 Cycle 10 (Reference 7), provided the appropriate value of '
- ! K09 is incorporated. ;
The CPCS addressable constants listed in Table 2 are consistent with the Functional Design Requirements described in References 8 and 9, and the l
- database constants listed in Reference 10.
1 i Please note that all the assumptions, requirements, and guidelines specified in References 2 and 3 remain effective.
I J
J Y
l
,n. ,
,e -rw- ~- a m- w e
l
. Enclosure 1 to '
A-93-026 l Page 3 of 5 ..
l
{
l i l 1
Table 1 l ANO-2 Cycle 10 Current and Revised COLSS Addressable Constants j for a Reduced Number of Operable incore Detectors ;
I i
Constant Description Value Current" 1 50 % i Failed j i
UNCERT Uncertainty Factor for 1.09 1.11 .
LHR POL f EPOL2/4 Uncertainty Factor for 0.11 0.12 !
DNBR POL f
- Values come from Page A2-2 of Reference 2. ;
i I
Table 2 ANO-2 Cycle 10 Current and Revised CPC Addressable Constants ;
for a Reduced Number of Operable incore Detectors t Constant Description Value (
Current
FaHed P
l 6
BERR1 Power Uncertainty Factor Used in 1.21 1.22 }
DNBR Calculation i BERR3 Power Uncertainty Factor Used in Local 1.25 1.26 i Power Density Calculation !
1
- Values come from Page 2 of Reference 3.
I
~
Enclosure 1 to A-93-02G Page 4 of 5 .
iferences:
- 1. D. R. Earles to F T. Philpott, " Proposal to Support Reduction of Operable Incore Detectors for ANO-2 Cycle 10 and Beyond," A-93-025, September 8, 1993.
- 2. D. R. Earles to F. T. Philpott, "ANO-2 Cycle 10 Final CPC/CEAC, COLSS and CEFAST Information," A-92-050, October 8, 1992.
- 3. D. R. Earles to F. T. Philpott, "ANO-2 Cycle 10 Revised BERR1 and BERR3 Values in CPC and Revised Planar Radial Peaks in CPC and COLSS,"
A-92-065, December 23, 1992.
- 4. R. B. Lang, "ANO-2 Cycle 10 CECOR Reliability Factors," 041-01;QR-220-18, CE0-93/00367, September 17, 1993.
- 5. " Functional Design Requirements for a Core Operating Limit Supervisory System (COLSS), "CE-NPSD-344-P, Revision 01-P, December 1986.
- 6. " Arkansas Nuclear ONE Unit 2 COLSS Functional Design Specification -
Plant Specific Supplement," CE-NPSD-352-P, Rev. 00-P, July 1986.
- 7. "ANO-2 COLSS Database Document," CE-NPSD-315, Rev. 05-P, October 1992.
- 8. " Functional Design Requirements for a Core Protection Calculator,"
CE-NPSD-335-P, Rev. 02-P, April 1988.
- 9. " Functional Design Requirements for a Control Element Assembly Calculator," CE-NPSD-336-P, Rev. 01-P, April 1988.
- 10. "AN0-2 CIP CPC and CEAC Database Listing," CE-NPSD-351-P, Revision 01-P, April 1988.
l
^
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Enclosure 1 to A-93-026 Page 5 of 5 Software Media Transfer Form f ACCL NO. 127 l
CORE PROTECTION CALCULATOR SYSTEM '
ADDRESSABLE CONSTANTS AND 53FTWARE MEDIA TRANSFER FORM .
l l
A. Originator S. Etemaai Plant ANO-2 Cycle 10 Date September 21. 1993 i
I B. Package Contents (C-E Windsor):
Revised BERR1 and BERR3 values for reduction of operable incore l detectors ;
I l
l C. Receipt of Change (NSSS Site):
- 1. Receipt of CPC Addressable Constants / Software media is acknowledged.
Name Date
- 2. The change has been reviewed and found acceptable, except as noted:
- 3. Please return to: Mr. M. A. Book CEP: 5318-GC28 1000 Prospect Hill Road Post Office Box 500 Windsor, CT 06095-0500 D. Acknowledgement of Receipt of Change (C-E Windsor):
- 1. ACCL Entries Completed Date NOTE: Originator to send copies of completed forms to all concerned C-E Engineering groups.
- _ _}}