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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23094A1252023-03-31031 March 2023 Talen Part 21 Final Notification P21-03032023-FN R0 Re Defect Identified in Automatic Transfer Switch ML23094A1242023-03-31031 March 2023 EN 56387 Update - Paragon Energy Solutions Final Notification of Defect of Automatic Transfer Switch ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 ML20073G4572020-03-0909 March 2020 Carrier Corporation - Final Report Notification of Defect Pursuant to 10 CFR Part 21 for 17FA999-1200-107 Oil Pump ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19120A1062019-04-17017 April 2019 Interim Report of Potential 10 CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML18087A0022018-03-21021 March 2018 Crane Nuclear, Inc. - Final Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem ML18078A5362018-01-31031 January 2018 Crane Nuclear, Inc. - Interim Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem (Update) ML17311A9092017-10-31031 October 2017 Interim Report for Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem ML17223A1982017-07-21021 July 2017 Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter ML17206A0402017-07-14014 July 2017 Part 21 - Defective Safety Related Valves PLA-7613, Interim Report of a Deviation, Units 1 & 2 - (PLA-7613)2017-06-0909 June 2017 Interim Report of a Deviation, Units 1 & 2 - (PLA-7613) ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna ML15034A5662015-01-23023 January 2015 Notification of Potential Part 21 for Event #50703 ML15030A0332015-01-20020 January 2015 Letter from James Thigpen Notification of Potential Part 21 Nuclear Nonconformance Event Number 50703 ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14329A0632014-11-19019 November 2014 Notification of Potential Part 21 Re Lack of Proper Power Supply Indication ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14169A0302014-06-15015 June 2014 Update to Interim Report - 10CFR 21 Evaluation Regarding Potential Deficiencies in Seismic Qualifications for PV-62 ML14303A5262014-03-28028 March 2014 Interim Part 21 Report - Misaligned Separators in LCR-25 Standby Batteries ML13340A3822013-12-0505 December 2013 Part 21 Reportable Condition Notification: Failure of Relay Logic Card Modules in 2 Out of 4 Voters ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML12038A0282012-02-0202 February 2012 Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12032A2402012-02-0101 February 2012 Notification of Potential Part 21 - 60-Day Interim Report Notification: Failure of CRD Collet Retainer Tube/Outer Tube Weld ML11340A1002011-12-0505 December 2011 Letter 10 CFR Part 21 Notification Report, CON2000 and RTD2100 Spring Clips ML11341A0602011-12-0505 December 2011 Notification of Potential Part 21 Involving Defective Spring Clips Used as Seismic Restraints on Two Scientific Modules ML11363A1882011-12-0202 December 2011 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0098, Rev. 3, Amot Thermostatic Valve Element P/N: 9760X ML11336A3692011-12-0101 December 2011 Notification of Potential Part 21 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1122401422011-08-11011 August 2011 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal 2023-09-06
[Table view] Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
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Text
APPLIED ANALYSIS CORP.
C ICK September 23, 2008 NRC Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
10CFR21 Reporting of Defects andNom-Compliance - PipeFlo Software
Dear Sir:
Pursuant to the requirements of 10CFR21.21, the attached report documents an apparent reportable error in Version 10.00 of the Pipe-FloProfessional 2007 software (herein referred to as Pipe-Flo Version 10.00). The Pipe-Flo software is commercial software available through the Engineered Software Co. in Lacey, WA.
Pipe-Flo Version 10.0 was dedicated for nuclear quality applications (with restrictions) by Applied Analysis Corp. (AAC) under AAC's NQA program. After dedication and use of the code in a commercial nuclear safety related application, a code error was discovered. The code error was determined to be essentially inconsequential for the AAC nuclear safety related application. However, AAC is aware that Pipe-Flo Version 10.00 has been purchased by other consultants and/or utilities for commercial nuclear applications. To date, AAC is not aware of any 10CFR21 reporting on the Pipe-Flo Version 10.00 software error documented in the attachment. Therefore, AAC is submitting this report in accordance with 10CFR21 requirements. It should be noted that the subject error has since been corrected (and such correction verified by AAC) in Version 10.01 of the code.
Sincerely, Juan M. Cajigas President cc: Richard M. Centenaro, PPL Services Attachment P.O. BOX 518
- SHILLINGTON,.PA 19607-0518 °PHONE (610) 775-0272 ° FAX (610)-777-3718
Pipe-Flo Problem Report Number: 01 Page 1 of I Pipe-Flo Problem Report Pipe-Flo Version: 2007 10.00 Computer Type/Operating System: Pentium/Windows Reported By: J. M. Cajigas Date: 08/15/08 Organization: AAC Telephone: (610) 775-0272 Problem or Requested Change: The Pipe-Flo 2007 Version 10.00 contains an error in the pressure drop calculations for Flow Control Valve (FCV) components with a specified valve position. Additional details are provided in AAC CAR No. 6 attached to the SVVR section of the Pipe-Flo SQAP.
Evaluation: This error results in Pipe-Flo FCV pressure drops and consequential flow rates that are incorrect for highly throttled FCV's. See AAC CAR No. 6.
Disposition: AAC has obtained Pipe-Flo 2007 Version 10.01 which corrects this problem. All current Pipe-Flo Version 10.00 based calculations will be revised. Future Pipe-Flo calculations will use Version 10.01 which has been validated in SVVR R1.
Applied Analysis Corp. Corrective Action Report CAR No. 006 (CAR) Date: 08/15/08 Page 1 of 4 PartA : Defwiciecy i~
- 1. To: A. W. Grammes 2. Project: PPL UHS EPU 3. Project Number: 3120
- 4. Originator: J. M. Cajigas 5. Date Issued: 08/15/08
- 6. Reference / Requirement: EP-03, Control of Software Quality, Section 5.6
- 7. Deficiency / Apparent Cause: In accordance with EP-03, AAC computer programs used in safety related applications shall be controlled in accordance Section 5.6 of the procedure and, by reference, follow the guidelines in ANSI/ANS-10.4-1987 and NUREG/CR-4640 as appropriate.
The computer code Pipe-Flo, Version 2007, was verified and validated (V&V) in accordance with EP-03 on July 20, 2007 and documented in the AAC Software Quality Assurance Plan (SQAP) for Pipe-Flo. Verification of the code was accomplished via a comparison to a spreadsheet based fluid network solution to the Susquehanna Steam Electric Station (SSES) RHRSW/ESW system. The validation was documented in the Software Verification and Validation Report (SVVR) of the Pipe-Flo SQAP. This validation was deemed particularly useful because it tested the same code components and for the same plant, SSES, as the code was about to be used for.
The verified Pipe-Flo code was then used in SSES safety related calculations EC-054-1027 and EC-054-1028 in July of 2007.
In July of 2008, PPL informed AAC that they could not reproduce all the flow configuration cases documented in EC-054-1027 with their own version of Pipe-Flo. PPL could reproduce Case 1 but not Cases 2 through 4. Case I is the same case used in the Pipe-Flo SQAP. Further investigation indicated that PPL had purchased Pipe-Flo 2007, Version 10.01 whereas AAC used and verified Pipe-Flo 2007 Version 10.0.
In the SQAP Case 1, AAC used data contained in PPL calculation EC-054-1020 in which the system's flow control valve flow coefficient (Cv) was specified. AAC then specified the same Cv for the system's Pipe-Flo flow control valves as well as matched all the other inputs for pipes, fittings, and pumps. The Pipe-Flo results matched the benchmark problem within less than 1%.
Given that an almost identical benchmark was achieved, AAC proceeded to set all the system flow control valves (FCV's) using a Pipe-Flo "FCV model" that allows the simulation of the valve pressure drop in accordance with a specified valve position. Use of this model is required to easily simulate different system configurations as well as allow easy benchmarking with field flow data. The Pipe-Flo FCV model interpolates from a user provided Cv vs. valve position table to calculate the valve Cv at a user chosen valve position.
In Cases 2-4 of EC-054-1027, AAC used SSES field valve positions and the Pipe-Flo FCV model as a starting point to generate a "design case" flow balance consistent with Extended Power Uprate (EPU) design configurations and proposed system design changes. Inspection of Pipe-Flo output indicated that Pipe-Flo was correctly interpolating from the user provided Cv vs. valve position curves.
Re-execution of the EC-054-1027 cases on a PPL computer using both AAC's Version 10.0 and PPL's Version 10.01 of the code confirmed that the two versions matched on Case 1 but not for Cases 2-4. PPL contacted the code vendor, Engineered Software (ES) and provided some of the input files. ES subsequently informed PPL that a problem with the FCV pressure drop model was discovered and corrected in Version 10.01. The problem, according to ES, was deemed minor and was only pronounced when valves were highly throttled.
Applied Analysis Corp. Corrective Action Report CAR No. 006 (CAR) Date: 08/15/08 Page 2 of 4 Following PPL's communication with ES, AAC contacted ES on this issue. Mr. Juan Cajigas from AAC contacted ES owner Ray Hardee and both spoke for nearly an hour on July 25, 2008. Mr. Hardee indicated that the FCV pressure drop problem was discovered in March 29, 2007 and corrected in Version 10.01. Mr. Hardee added that the problem was discovered when a client was comparing the code results to "other" calculations. Mr. Hardee also clarified that the FCV pressure drop model is different than that used when the user specifies the Cv for a valve on the code PIPELINE component, the latter using standard "CRANE" Cv/dP formulae. He indicated that the pressure drop models used in the FCV model correspond to those in ANSI/ISA-S75.01-1985 as described in the CONTROL VALVE SELECTION chapter of the code manual. It turns out that the Version 10.0 algorithms used to solve for pressure drop in the FCV model were "failing" on cases where valves were highly throttled. Upon AAC questioning Mr. Hardee indicated that ES did not informed its Pipe-Flo clients of this problem, including those in the nuclear industry, and that a "planned" note on this issue in the company monthly E-bulletin "never made it" to the bulletin. AAC discussed the I OCFR21 implications of this issue with Mr. Hardee and recommended he contact PPL's Rich Centenaro for further information.
The Pipe-Flo manual, version B-708U-1006, included with version 10.0 describes FCV's in the PIPING SYSTEM ANALYSIS section of the program. FCVs are described in pages 41 through 42. On page 42, the manual indicates that control valve data (including FCVs) can be imported from code vendor catalog data or manually set (as done in EC-054-1027). It then indicates, "Calculations for control valves with catalog data are performed using the same equations outlined in the Control Valve Selection section." Later on page 42, the manual indicates, "Valve data can also be manually entered or imported from manufacturer's valve selection programs when the programs have export capability. The calculations for these valves are performed using the same equations that are used for catalog valves." In other words, this last sentence is the only indication that FCV's pressure drops are calculated via the ANSI methodology described in the valve selection section (a valve "catalog" section) vs. the CRANE pressure drop equations described in the PIPING SYSTEM ANALYSIS section. In any event, since the pressure drop calculations from the ANSI standard are deemed more accurate than those based in the CRANE formulae, significant difference between the two methods are not expected.
Attachment A contains the Pipe-Flo Version 10.0 FCV Summary Report for an updated validation test in the AAC SQAP for Pipe-Flo in which two highly throttled valves at Node Connecting Elements (NCE) 238 and 254 were replaced with FCV models with valve positions set at the corresponding SQA Case 1 valve positions. The calculated flow results for NCE's 238 and 254 are 343.7 and 829.5 gpm respectively vs. 296.9 and 707 gpm respectively indicating an error in the Version 10.0 FCV calculations using the "set valve position" option of the FCV model. As a result of this condition, the calculations in EC-054-1027 and EC-054-1028 contain an error in the calculated flow for highly throttled FCV's since they were performed using the FCV model in Pipe-Flo 2007 Version 10.0. Both calculations represent a projected design condition using assumed FCV valve positions. The FCV's affected by the error are highly throttled and thus returning to the desired flows will only require a larger assumed valve opening. With a less throttled system, the system pumps should adequately supply the required flows as they "run-out" on their pump curve. Ultimately, the system has been field flow balanced and adequate flows have been measured.
Although the code vendor neglected to inform its users of this problem, AAC was responsible for the QA dedication of this code under its QA program. AAC personnel assumed that the FCV pressure drop models were the same and/or equivalent than those used when valve Cv are input instead of valve Cv vs. position curves. As a result, the SQAP test problem did not provide the fidelity required to discover this problem.
1Applied Analysis Corp. Corrective Action Report CAR No. 006 (CAR Date.: 08/15/08
_________Page 3 of 4
- 8. 0 CFR 21 Applicable? X YES NO ] 9 nTme'hateAciion Required 9 YES NO
- 10. Individual or Organization Assigned Corrective Action: J. M. Cajj'as 11. Response Date: 08/15/09
- 12. QA Evaluation: Date: 08/15/08 This CAR constitutes a IOCFR21 condition in that although none of the criteria specified in EP-04, Section 5.2, are applicable, the condition may result in Pipe-Flo 2007 Version 10.0 users that are not aware of the subject condition to perforn design and/or plant operability determinations that could lead to conditions adverse to plant safety. Pursuant to 10CFR.21.21 a copy of this evaluation will be submitted to PPL Susquehanna, LLC for licensee information and evaluation.
The condition does not impact the quality of any other AAC activities performed under its NQP to date.
- 13. President Concurrence: Date: 08/15/08
?"! **?;.:Par "' t C.:. Cor,,ectlive Ac- ioxn.k , .. '.::;.:- :i' :,*::* *i " <.
14.
Description:
AAG to update its copy of Pipe-Flo 2007 to version 10.01. The AAC SQAP for Pipe-Flo will be updated to include testing of the FCV pressure drop model. PPL calculations EC-054-1027 and EC-054-1028 will be revised using Pipe-Flo 2007 version 10.01. A copy of this CAR will be used as a training aid for in-house training associated with software dcdication.
- 15. Prepared by: J. M. Cajigas Date: 08-15-08 16. Implementation Date: 09/15/08 17: QA Concurrence: ______Date: 08-15-08 18: President Concurence: ___________________ - Date: 08-15-08
Applied Analysis Corp. Corrective Action Report CAR No. 006 (CAR) Date: 08/15/08 Page 4 of 4 Attachment A
I List Relwwrl Syalim: 1OZ7CASEIAOLD 08,V8AM 10.,64 am Llnwup: CASE I Comp": PP & L rev: 06~8M08 10:52amm Projbctý: EC-054-1027, Rev. 0 Alin pressure, 14.7 pal a by: PSP
-Lineup notes: PIPE-FLOVV VERSION 10,0 Total Syskemn Volumo: 462929 gallons Pi "sure drop calculations: flarcy-Weaibach method, laminar outtoh Re = 2100 Calculated: 8 iterations Avg Deviation: 2.1219-005 %
.PuLmps Pump Flow status Total head WF 8peed NPSI~a Suction~ Discharge Suction Dlischarge Ua giopi Ift rpm II psl a psi a t f EMERGENCY CWC PUMP OP-..8.39.2 (49.8) (21.53) 1 127.7 55.90 77.49 785.802 705.802 EMERGENCY CWC PUMP OP-,.--. Otf ........ ...... 784.677 784.677 ail 661 687.5 ESW PUMP OP-604A Off ESW PUMP OP-504B ... art .81 687.5 ESW PUMP OP,504C 4021 (285.3) (1233) 1 48.94 21 92 133.8 8o1 867.5 ESW PUMP OP-504D 4195 (292-9) (128.6) 1 48.94 21.92 137.1 601 687.5 RHR PUMP IP-5O0A 8401 (212.7) (91.95) 1 47.94 21.49 102.4 662 887.5 RHR PUMP 1PS06B 8757 (214.8) (92.87) 1 47.9.4 21.49 103.3 062 6087.5 RHR PUMP 2PS06A 8251 (212.5) (91.88) 1 47.94 21.49 102 4 662 887.6 RHR PUMP 2P506B 8348 (214.4) (92.68) 1 47,94 21.49 103,1 862 887,5 Conrirols Control Set Value Elev Flow status dP HL Inlot Outlet ft US gpm psi ft NCE`1`13 FCV: Fully open 650 8599 8.818 20.4 81.24 7243 Cv: 7900 Fp 0.999 0Max 25025 NGE121 FCV: Fully open 650 8507 8.634 19. 07 61.3 72.67 Cv: .2900 Fp: 0,9D9 QMax: 25034 NCE13 FCV: Fully npen (50 684 5.553 W9.78 79.28 70.71 Cv: 2900 Fp: 0.999 OMax: 25505 NCE21 FCV: Fully open 050 8186 7..995 18.49 79.08 71.08 Cv: 2900 Fp: 0.999 OMWx. 25476 NCE238 FCV: 24% 680.875 343.7 65.17 150.7 110.7 51.54 Cv: 34.9 Fp: 1 OMax. 375 4 NCE254 FCV: 22% 680.125 629.5 62.01 1434 117.6 55.58 Cv: 07.5 Fp: I QMax: 945,4 PiPE-r'L0 2007 POI