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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 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 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248D6011998-03-31031 March 1998 Suppl 9 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20203H6701998-01-31031 January 1998 Rev 0 to non-proprietary Version of BAW-10232, OTSG Repair Roll Qualification Rept (Including Hydraulic Expansion Evaluation) ML20199G9531998-01-31031 January 1998 Non-proprietary Alternate Repair Criteria for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once- Through Sgs ML20211N4921997-09-30030 September 1997 Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements ML20135F3681996-11-30030 November 1996 Non-proprietary Final Rept Repair of 3/4 O.D. SG Tubes Using Leak Tight Sleeves ML20112E8491996-02-28028 February 1996 Suppl 7 to Annual Rept of Abb C-E ECCS Performance Evaluation Models ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20083Q9261995-05-30030 May 1995 Joint Applications Rept for Safety Injection Tank Aot/Sti Extension ML20083Q9861995-05-30030 May 1995 Joint Applications Rept for Emergency Diesel Generators AOT Extension ML20085H3221995-02-28028 February 1995 Suppl 6 to Topical Rept CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models,Final Rept,Ceog Task 865, Dtd Feb 1995 ML20073D4561994-09-30030 September 1994 Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys ML20069D4261994-02-28028 February 1994 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20063C7571993-12-31031 December 1993 Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys ML20081K9821991-05-31031 May 1991 Final Rept on Reactor Vessel App G Pressure-Temp Limits for Arkansas Nuclear One Unit 2 for 21 Efpys ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3391990-04-30030 April 1990 Suppl 1 to Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16X16 PWR Fuel.' ML20059M4481990-03-31031 March 1990 Unit 1 Pressure-Temp Limits for 15 Efpy ML20247E3231989-06-30030 June 1989 Nonproprietary Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16x16 PWR Fuel ML20245G7121989-05-31031 May 1989 Submittal in Response to NRC Bulletin 88-11, 'Pressurizer Surge Line Thermal Stratification' ML20246N3841989-04-30030 April 1989 Analysis of Capsule ANI-C,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program ML20211A1031986-09-30030 September 1986 Small Break LOCA Analysis for B&W 177FA Lowered Loop Plants in Response to NUREG-0737,Item II.K.3.31 ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20202B1131986-04-30030 April 1986 Nonproprietary Suppl 1,Rev 3, CPC Protection Algorithm Software Change Procedure ML20151Z0521986-01-31031 January 1986 Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure ML20151Z0641986-01-31031 January 1986 Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines ML20135A5571985-08-31031 August 1985 B&W Owners Group Cavity Dosimetry Program ML20134N3021985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Core Protection Calculator ML20134N2941985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Control Element Assembly Calculator ML20129F9301985-07-31031 July 1985 Cycle 5 Shoulder Gap Evaluation ML20100J1551985-03-31031 March 1985 Nonproprietary Typical Data Base Constants for Arkansas Nuclear One Unit 2 ML20100J1801985-03-31031 March 1985 Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator Sys Phase I Design Qualification Test Rept ML20100J1991985-03-31031 March 1985 Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing ML20100J2221985-03-31031 March 1985 Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept ML20101U3551984-12-31031 December 1984 Nonproprietary Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2 ML20106E3251984-10-31031 October 1984 Nonproprietary Once-Through Steam Generator Mechanical Sleeve Qualification ML20107N0221984-10-31031 October 1984 Nonproprietary CPC Methodology Changes for Arkansas Nuclear One Unit 2 Cycle 5 ML20094J7101984-07-31031 July 1984 Analyses of Capsule AN1-A,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program ML20098F1361984-04-30030 April 1984 Thermal-Hydraulic Crossflow Applications ML20083G5321983-11-30030 November 1983 Cycle 4 Shoulder Gap Evaluation ML20087N2541983-11-30030 November 1983 Nonproprietary Shoulder Gap Data Taken on Batch D Assemblies After Cycle 3. Info Deleted ML20066D2241982-03-31031 March 1982 Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss. Portions Intentionally Deleted Due to Lack of Relevancy to NUREG-0737,Item II.K.2.17.Util Did Not Participate in Development of Deleted Sections ML20039F8681981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for AR Nuclear One- Unit 2 Reactor Vessel. ML20009F2021981-07-31031 July 1981 Nonproprietary Version of Response to Questions on Documents Supporting ANO-2,Cycle 2,License Submittal, Amend 2-NP 1999-07-29
[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] |
Text
_ _
Docket No. 50-368 .
CEN-288( A)-NP -
CPC Methodology Changes for Arkansas Nuclear One Unit 2 Cycle 5 October, 1984 Combustion Engineering, Inc.
Nuclear Power Systems Power Systems Group Windsor, Connecticut 8411140376 841109 PDR ADOCK 05000 P
LEGAL NOTICE THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED RY COMBUSTION ENGINEERING, INC. NEITHER COMBUSTION ENGINEERING NOR ANY PERSON ACTING ON ITS BEHALF:
A. MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPUED INCLUDING THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPOSE OR MERCHANTA81UTY, WITH RESPECT TO THE ACCURACY, COMPLETENESS, OR USEFULNESS OF THE INFORMATION CONTAINED IN THl3 REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHOO, OR PROCESS DISCLOSED IN THIS REPORT MAY NOT INFRINGE PRIVATELY OWNED RIGHTS;OR
- 8. ASSUMES ANY UA81UTIES WITH RESPECT TO THE USE OF, OR FOR DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, APPARATUS, METHOD OR PROCESS DISCLOSED IN TH13 REPORT.
7-
- 1.
SUMMARY
Combustion Engineering on behalf of Arkansas Power & Light Company (AP&L) will implement a number of CPC algorithm and constant changes for Arkansas Nuclear One Unit 2 (ANO-2) Cycle 5. A brief review of each CPC change is provided here. All of the changes are evolutionary in nature and represent small differences in the algorithms themselves. These changes are presently being implemented for San Onofre Unit 2 Cycle 2 (Reference 3.1) . A schedule for implementation of the changes at ANO-2 is provided in Table 1.
Detailed algorithm descriptions in the form of functional specifications and discussions of methodology changes are provided in Reference 3.2.
TABLE 1 ANO-2 CYCLE 5 MILESTONES DATE MILESTONE ACTIVITY 10/31/84 Submit CPC Software Change Document to NRC 2/1/85 Submit Reload License Amendment Request to NRC (including the Reload Analysis Report) 3/1/85 End of Cycle 4 3/15/85 Submit CPC Phase I/ Phase II Test Reports to URC 5/1/85 Startup of Cycle 5 1
1 ---- _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ .
- 2.
SUMMARY
OF CPC ALGORITHM AND CONSTANT CHANGES 2.1 Corrected LPD Penaltv Factor The Cycle 5 algorithms include correct implementation of the Local Power Density (LPD) Penalty Factor which AP&L committed to implement for Cycle 5 in their letter of October 18, 1983 (2CAN108307). The correction consists of modification of the CPC software to be consistent with the functional specification. This correction was first implemented in the Palo Verde Nuclear Generating Station Unit 1 (PVNGS-1) Cycle 1 software (Reference 3.3) and has been reviewed and approved by the NRC.
2.2 Hot Pin to Hot Channel Conversion Presently, POWER provides a hot pin power distribution in the form of an axial power distribution and appropriate radial peaking factors. This information is used in STATIC as if it were a hot channel power distribu-tion. CETOP-D (the design code) makes the conversion from hot pin to hot channel power directly and thus comparisons between CETOP-D and STATIC (the CPC calculation) in the CPC uncertainty analysis implicitly account for the difference.
For Cycle 5, constants will be inserted into the heat flux equations in STATIC to convert from hot pin to hot channel heat flux distribution explicitly in CPC. This change will provide a more physical approcch to the DNBR calculation. It involves minor algorithm adjustments in the CPC software and updates to the functional specification. The explicit conversion from hot pin to hot channel power was first implemented in the PVNGS-1 Cycle 1 software (Reference 3.3) and has been reviewed and approved by the NRC.
2.3 Non-Uniform Heating (F,) Correction Factor Modification Prasently, the calculation of the non-uniform heating correction factor (Fk) in the CE-1 correlation in UPDATE does not differentiate between small changes about steady state and larger changes during transients.
This results in a larger DNBR penalty than necessary during steady state operation.
2
For Cycle 5, the Ek_ algorithm will be modified to provide variable Fk factor adjustments , As a result, more accurate calculations of F will be made for small changes in operating conditions (i.e., near steady state) while calculating more conservative values of F f r large changes in operating conditions k
(i.e., transients). This change was first implemented in the PVNGS-1 Cycle 1 software (Reference 3.3) and has been reviewed and approved by the NRC.
2.4 PFMLTD and PFMLTL Range Limits The positive range limit on the CEAC penalty factor multipliers,
., will be shifted from to . This change is in anticipation of the need for a different range of values in the future and has no impact on the calculational logic. This change was first implemented in the PVNGS-1 Cycle 1 software (Reference 3.3) and has been reviewed and approved by the NRC.
2.5 Reactor Coolant Pump Pressure Rise Calculation l
The calculation of pressure rise across the reactor coolant pump in the FLOW algorithm will be modified to account for forward flow through the pump when the pump rotor is locked at or near zero RPM. This change was first implemented in the PVNGS-1 Cycle 1 software (Reference 3.3) and has been reviewed and approved by the hRC.
2.6 Reactor Power Cutback Algorithms will be added to the CPC and CEAC (Control Element Assembly Calculator) for detecting the actuation of a Reactor Power Cutback (RPC) event, for using off-line calculated RFC penalty factors, and for allow-ing the CPC calculation to more closely model core conditions without generating an inadvertent trip in the event of a RPC. Since ANO-2 does not have a RPC system, the effect of these algorithms will be nullified through the appropriate data base constants. Addressable constarts were also added to the CPC and CEAC to define the duration that the RPC flags can remain set. For ANO-2 these addressable constants will be set to zero.
, 3 1
The RPC algorithm' change was implemented in the PVNGS-1 Cycle 1 software (Reference 3.3) and has been reviewed and approved by the NRC.
2.7 Modification of Heat Flux Distribution Extrapolation in STATIC For certain CEA configurations, radial peaking factor assignments, and/or radial peaking factor multipliers, it is possible _
This _
, which results in a CPC channel trip.
Experience has shown that this condition occurs only at low power with a partially rodded core. This change ~
]inthetopofthecore.
[ ^
]Acheckis
)
~
performed for If any are detected, "
This change will result in a reduction
].
in the probability of unnecessary reactor trips. This change is being implemented in the San Onofre Nuclear Generating Station Unit 2 (SONGS-2)
Cycle 2 software (Reference 3.2) and is currently being reviewed by the NRC.
2.8 UPDATE Algorithm Improvement The UPDATE algorithm of CPC provides rapid and conservative recalculation of DNBR based upon the detailed DNBR calculation contained in the STATIC algorithm, updated state parameter measurement's, and derivatives of the DNBR. As part of the overall CPC uncertainty analysis, comparisons of UPDATE and STATIC-predicted DNBRs based on --
are used to quantify this conservatism. Presently, the UPDATE algorithm of CPC applies a penalty to the updated DNBR at all times.
4
r
- AnalgorithmchangewillbeimplementedinCycle5whichwill{
). In essence, this change minimizes excess conservatisms at normal operating conditions, but retains these conser-vatisms during transient operation.
TheCPCUPDATEalgorithmisbasedon{
]
I Thenewmethoduses{)).
]
For planned changes in plant operating conditions the change in state parameters will be relatively slow, thus causing -
~
For this type of operation )totheUPDATE
~
algorithm which will ensure the conservatism of the calculated DNBR.
This penalty factor along with the rest of the CPC calculations and 5
{ - - _ _ _ _ _ _ _ _ _ _ _ __
penalty factors en'sures that the DNBRs calculated during transients and accidents will generate a trip signal when needed.
The UPDATE penalty factor modification therefore ensures that the safety margin of the CPCs is maintained for all modes of operation. It will increasethesteadystateoperatingmargin}
which will reduce the possibility of spurious trips and increase plant operational flexibility. This change is being implemented in the SONGS-2 Cycle 2 sof tware (Reference 3.2) and is currently being reviewed by the NRC.
2.9 Power Uncertainty As a Function of Core Power Level Addressable penalty bias constants are used to adjust the thermal power and neutron-flux power level in the CPCs. Present methodology implements values of these penalty biases to bound the power level range set by CPC design requirements.
~
For Cycle 5, This change is being implemented in the SONGS-2 Cycle 2 software (Reference 3.2) and is currently being reviewed by the NRC.
2.10 Temperature Shadowing Factor Modification The temperature shadowing factor (TSF) is used to correct the CPC neutron flux power for decalibration effects resulting from changes in coolant density. A multiplier is applied to the neutron flux power calculation to correct ex-core detector response for inlet moderator temperature _
~
changes. In the current algorithm, the TSF is a ,
~
of moderator temperature change which is measured at start-up. The uncertainty in the measurement of the TSF is accommodated in the overall uncertainty term ,
6
~
the TSF on moderator temperature using a
{ex-core detector)temperaturewillbeimplementedforCycle5.
The calibration procedures will be modified accordingly.
[
]ThischangewillallowtheTSFuncertaintytobe included directly in the factor itself. This ensures a conservative correction to TSF at temperatures different from the calibration temper-ature without requiring unnecessary uncertainty allowance near the calibration temperature (which should be near nominal conditions). This change is being implemented in the SONGS-2 Cycle 2 software (Reference 3.2) and is currently being reviewed by the NRC.
- 3. REFERENCES i
k 3.1 CEN-284(S)-P, " Safety Analysis and CPC Methodology Changes for San Onofre Nuclear Generating Station Unit 9 No. 2 and 3," Dockets 50-361 and 50-362, June 1984.
I 3.2 CEN-281(S)-P, "CPC/CEAC Software Modifications for San Onofre Nuclear Generating Station Units 2 and 3," June 1984.
3.3 Enclosure 1-P to LD-82-039, "CPC/CEAC Software Modification for System 80," March 1982.
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