ML19060A298
| ML19060A298 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/01/2019 |
| From: | Lacal M Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19064B267 | List: |
| References | |
| 102-07869- MLL/MDD | |
| Download: ML19060A298 (54) | |
Text
Attachment 4 contains PROPRIETARY information To be withheld under 10 CFR 2.390 10 CFR 50.90 10 CFR 50.12 MARIA L. LACAL O aps Senior Vi ce Pres id ent , Nuclear Reg ula~ory & Oversight Palo Verde Nuclear Generating Station 102-07869- MLL/MDD P.O. Box 52034 Ph oe ni x, AZ 85072 March 1, 2019 Mail Station 7605 Tel 623 .393 .6491 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Renewed Operating License Nos. NPF-41, NPF-51, NPF-74 Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP' Fuel By letter dated July 6, 2018 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML18187A417], as supplemented by letter dated October 18, 2018 (ADAMS Accession No. ML18296A466), Arizona Public Service Company (APS) requested changes to the Technical Specifications, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90, to support the implementation of Framatome Advanced Combustion Engineering (CE16HTP') fuel design with MS as a fuel rod cladding material and gadolinia as a burnable absorber for Palo Verde Nuclear Generating Station (PVNGS),
Units 1, 2, and 3. In addition to this license amendment request (LAR), APS is requesting an exemption, pursuant to 10 CFR 50.12, from certain requirements of 10 CFR 50.46, Acceptance criteria for emergency core cooling systems [ECCSJ for light-water nuclear power reactors, and 10 CFR Part 50, Appendix K, ECCS Evaluation Models, to allow the use of Framatome MS alloy as a fuel cladding material.
This amendment will adapt the approved PVNGS reload analysis methodology to address both Westinghouse and Framatome fuel, including the implementation of selected Framatome methodologies, parameters, and correlations. The ability to use either Westinghouse or Framatome fuel will ensure security of the PVNGS fuel supply by providing for multiple fuel vendors with reliable fuel designs and geographically diverse manufacturing facilities.
By letter dated January 15, 2019 (ADAMS Accession No. ML19011A108), the NRC staff published an audit plan to facilitate the NRC staff review of the LAR. The audit was held in Rockv ille, Maryland, on January 22 and 23, 2019 . This letter transmits the presentation slides that were provided on January 22, 2019, during the audit.
The letter includes four attachments. Attachment 1 is an affidavit signed by APS that sets forth the basis on which the proprietary information in Attachment 4 may be withheld from Attachment 4 transmitted herewith contains PROPRIETARY information.
When separated from Attachment 4, this transmittal is decontrolled.
A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
102-07869-MLL/MDD ATIN: Document Control Desk U. S. Nuclear Regulatory Commission Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP' Fuel Page 2 public disclosure by the Commission and addresses with specificity the considerations listed in 10 CFR 2.390(b)(4). Correspondence with respect to the proprietary aspects of regarding APS information or the supporting APS affidavit should be addressed to Mr. Bruce Rash, APS Vice President, Nuclear Engineering. is an affidavit signed by Framatome that set forth the basis on which the proprietary information in Attachment 4 may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in 10 CFR 2.390(b)(4).
Correspondence with respect to the proprietary aspects of Attachment 4 regarding Framatome information or the supporting Framatome affidavit should be addressed to Mr.
Philip A. Opsal, Framatome Manager, Product Licensing. is a non-proprietary version of the audit presentation slides, which reflects the redaction of proprietary information. Attachment 4 is the proprietary version of the audit presentation slides.
No new commitments are being made in this submittal. By copy of this letter, this information is being forwarded to the Arizona Department of Health Services in accordance with 10 CFR 50.91(b)(1).
Should you have any questions concerning the content of this letter, please contact Matthew S. Cox, Licensing Section Leader, Nuclear Regulatory Affairs, at (623) 393-5753.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: March 1, 2019 (Date)
Sincerely, MLL/MDD/CJS/mg - Arizona Public Service Company (APS) Affidavit - Framatome Affidavit - Non-Proprietary Audit Presentation Slides - Proprietary Audit Presentation Slides cc: S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS B. Goretzki Arizona Department of Health Services (ADHS)
Attachment 1 Arizona Public Service Company (APS) Affidavit Submitted in Accordance with 10 CFR 2.390 to Consider Attachment 4 as a Proprietary Document
) ss.
CITY OF PHOENIX )
- 1. My name is Bruce Rash. I am employed by Arizona Public Service Company ("APS"). My present capacity is Vice President, Nuclear Engineering, for the Palo Verde Nuclear Generating Station ("PVNGS"), and in that capacity I am authorized to execute this Affidavit.
- 2. APS is the operating agent for PVNGS. I am familiar with the policies established by APS to determine whether certain APS information is proprietary and confidential, and to ensure the proper application of these policies.
- 3. I am familiar with APS information in the following document: Attachment 4 to APS Correspondence 102-07869, "Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP' Fuel," referred to herein as "Document." Information contained in this Document has been classified by APS as proprietary in accordance with the policies established by APS for the control and protection of proprietary and confidential information.
- 4. The information contained in this Document is proprietary and confidential in natures and of the type customarily held in confidence by Framatome (formerly Areva, Inc.),
Westinghouse, and APS, and not made available to the public. Based on my experience in the nuclear industry, I am aware that other companies also regard the type of information contained in the Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding proprietary information from public 1
disclosure is made in accordance with 10 CFR 2.390. The information qualifies for withholding from public disclosure under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. APS applied the following criteria to determine that the information contained in the Document should be classified as proprietary and confidential:
(a) APS has a non-disclosure agreement with Westinghouse Electric Company LLC
("Westinghouse"), Framatome, and Structural Integrity Associates, Inc. (SI),
under which Westinghouse and Framatome have provided to APS certain proprietary and confidential information contained in the Document.
(b) The information reveals details of Westinghouse's, AP S's, and/or Framatome's research and development plans and programs, or the results of these plans and programs.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive commercial advantage for Westinghouse, APS, and/or Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive commercial advantage for Westinghouse, APS, and/or Framatome on product optimization or marketability.
(e) The unauthorized use of the information by one of Westinghouse's, APS's, and/or Framatome's competitors would permit the offending party to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(f) The information contained in the Document is vital to a competitive commercial advantage held by Westinghouse, APS, and/or Framatome, would be helpful to 2
their competitors, and would likely cause substantial harm to the competitive position of Westinghouse, APS, and/or Framatome.
(g) It reveals aspects of past, present, or future Westinghouse, Framatome, or APS funded development plans and programs of potential commercial value.
- 7. In accordance with APS's policies governing the protection and control of proprietary and confidential information, the information contained in this Document has been made available, on a limited basis, to others outside APS only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. APS's policies require that proprietary and confidential information be kept in a secured file or area and distributed on a need-to-know basis. The information contained in the Document has been kept in accordance with these policies.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief, and if called as a witness I would competently testify thereto. I declare under penalty of perjury under the laws of the State of Arizona that the above is true and correct.
1 SUBSCRIBED before me this D. 8 7 1--
dayof G~ ,2019.
NOTARY PUBLIC, STATE OF ~Rl~O~
MY COMMISSION EXPIRES: ~ 9 2 0~ / 1 Reg.#:
3
Attachment 2 Fra matome Affidavit Submitted in Accordance with 10 CFR 2.390 to Consider Attachment 4 as a Proprietary Document
AFFIDAVIT COMMONWEALTH OF VIRGINIA )
) ss.
CITY OF LYNCHBURG )
- 1. My name is Philip A Opsal. I am Manager, Product Licensing, for Framatome Inc., (formally known as AREVA Inc.), and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome Inc., to determine whether certain Framatome Inc. information is proprietary. I am familiar with the policies established by Framatome Inc. to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome Inc. (formally AREVA Inc.) information contained in the following presentation slides which supported an NRG audit of Palo Verde (herein referred to as Documents):
a) Thermal-Hydraulics (T-H) - Core Pressure Drop Profile b) Non-LOCA Analyses - Gas Gap Conductance and Peak Fuel Centerline Temperature.
- 4. These Documents contain information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome Inc. and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in these Documents as proprietary and confidential.
- 5. These Documents have been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in these Documents be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure
is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. The following criteria are customarily applied by Framatome Inc. to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatome lnc.'s research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome Inc.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome Inc. in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome Inc.,
would be helpful to competitors to Framatome Inc., and would likely cause substantial harm to the competitive position of Framatome Inc.
The information in these Documents is considered proprietary for the reasons set forth in paragraphs 6(b), 6(c), 6(d) and 6(e) above.
- 7. In accordance with Framatome lnc.'s policies governing the protection and control of information, proprietary information contained in these Documents has been made available, on a limited basis, to others outside Framatome Inc. only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome lnc.'s policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this /)_ di day of rrd;n1,_of1;1 ~ , 20Hl.~
~
Heidi Hamilton Elder NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 12/31/2022 Reg. # 7777873
Attachment 3 Non-Proprietary Audit Presentation Slides
NRC Audit Entrance Framatome CE16HTP Fuel License Amendmen t Palo Verde Units 1, 2, and 3 - NON-PROP RIETARY January 22, 2019
Attendees
- Palo Verde
- Tom Weber - Nuclear Regulatory Affairs Director
- Mike Dilorenzo - Nuclear Regulatory Affairs Department Leader
- Tom Remick - Nuclear Fuel Analysis Department Leader
- Ryan Lane - Operations Shift Manager
- Matthew Cox - Regulatory Affairs Section Leader
- Chuck Karlson - Reload Analysis Section Leader
- Dave Ricks - Transient Analysis Section Leader 2
Attendees
- Palo Verde
- Dave Medek - Consulting Engineer, Transient Analysis (LOCA, Ch. 15, Methodology Control)
- Robert Hicks - Sr. Engineer, Transient Analysis (LOCA, Ch. 15)
- Shawn Gill - Sr. Engineer, Reload Analysis (T-H, Setpoints)
- Calvin Meddings - Sr. Engineer, Reload Analysis (Setpoints)
- Jenying Wu - Sr. Engineer, Nuclear Analysis (Physics)
- Luke McIntyre - Engineer II, Dry Cask (Mechanical Design)
- Chris Cowdin - Engineer II, Reload Analysis (T-H)
- Hans Van de Berg - Consultant (T-H, Ch. 15, Setpoints)
- Mark Drucker - Consultant (T-H, Setpoints, Fuel Performance) 3
Attendees
- Greg Kessler (Project Manager)
- Nathan Hottle (Reg. Affairs)
- Brett Matthews (Seismic)
- Lisa Gerken (LOCA)
- Ryan Swanson (T-H)
- Miao Sun (Fuel Performance/COPERNIC)
- Chris Allison (Fuel Performance/COPERNIC) 4
Discussion Topics
- Attendees
- Opening Remarks
- Framatome Fuel Project
- Reload Design Process
- Fuel Assembly Mechanical Design
- Thermal-Hydraulics (T-H)
- T-H Code Modification Process
- Mixed Cores
- LOCA Analyses
- Non-LOCA Analyses
- Setpoints 5
Opening Remark s
- Framatome CE16HTP Fuel Licensing
- Pre-Submitta l Meeting
- License Amendment Request
- Teleconferences
- Acceptance Review Questions
- First Regulatory Audit
- Breakout Sessions
- Next Steps
- Requests for Additional Information (RAis)
- Second Regulatory Audit 6
Framatome Fuel Project
- 100 CE16HTP fuel assemblies to be loaded
- Essentially the same design as lead test assemblies
- Fuel manufacturing underway
Framatome Fuel Project
- Overall Goals
- Increase security of supply
- Reliable fuel designs
- Multiple fuel vendors
- Geographically diverse manufacturing
- Commercial considerations
- Implement an improved fuel design
- Maintain existing methods to the extent practical
- Utilize NRC-approved methods to the extent practical
- Use general approach the NRC has seen before (SONGS, ML11215A090)
- Build off Next Generation Fuel (NGF) approval (ML17319A103 / ML17319A107) 8
Framatome Fuel Project
- Reload Methods Addressed in the Submittal
- Update NRC-approved APS reload methods to address Framatome fuel
- Use of NRC-approved Framatome mechanical design and LOCA methods
- Use of NRC-approved Framatome COPERNIC methods for fuel behavior analysis (thermal conductivity degradation)
- Use of NRC-approved Framatome BHTP critical heat flux (CHF) correlation
- Use of NRC-approved VIPRE-01 as an alternative to VIPRE-W
- 10 CFR 50.12 permanent cladding exemption request 9
Framatome Fuel Project
- Palo Verde reload methodology licensed by NRC June 14, 1993
- Experienced staff, have done rvSQ in-house reloads
- Structural Integrity / GD Barri
- Analytical and licensing support
- CE HTP fuel in use at most CE plants (all 14x14 plants, one 15x15 plant, one 16x16 plant)
- Zachry Nuclear Engineering
- VIPRE-01 subject matter expert (code maintenance and development)
- Westinghouse
- Compatibility evaluations 10
Reload Design Process
((
))
11
Reload Design Process
- Peak fuel centerline temperature safety limit
- Design features (fuel assemblies)
- Core Operating Limits Report (COLR) analytical methods
- 10 CFR 50.12 Permanent Cladding Exemption
- TS Bases
- Non-COLR Methods 12
Fuel Assembly Mechanical Design
((
))
13
Fuel Assembly Mechanical Design
- Essentially the same design as lead test assemblies
- Mechanical Compatibility
- Fuel assemblies
- Upper tie plates
- Lower tie plates
- Guide tubes
- Instrument tubes 14
Fuel Assembly Mechanical Design
- Normal Operation & Anticipated Operational Occurrences
- Acceptance criteria per Standard Review Plan 4.2, Fuel System Design, (stress and strain limits, creep collapse, fuel rod hydriding, fatigue, etc.)
- Faulted Condition
- Structural response to externally applied forces (earthquakes and pipe breaks)
- Framatome topical report ANP-10337P-A
- Lateral and vertical analyses
- Co-resident CE16STD and CE16NGF considered
- End-of-life grid crush 15
Thermal-Hydra ulics (T-H)
((
))
16
Thermal-Hydraulics (T-H)
- Thermal-Hydraulic Compatibility
- Core Pressure Drop Profile
((
))
17
Thermal-Hydraulics (T-H)
- Thermal-Hydraulic Compatibility
- RCS loop flow
- Total bypass flow
- Crossflow velocity
- Control rod drop time
- Fuel rod bow
- Guide tube heating 18
Thermal-Hydra ulics (T-H)
- BHTP Critical Heat Flux Correlation
- VIPRE model selections
- Statistical combination of uncertainties - system parameter uncertainties, BHTP correlation uncertainty, and VIPRE-based DNBR sensitivity
- Benchmark to experimental data
- Comparison to NRC-approved Framat ome LYNXT application
- NRC Information Notice 2014-01, Fuel Safety Limit Calculation Inputs Were Inconsistent with NRC-Approved Correlation Limit Values
- DNBR Probability Distribution Function
- Probability of fuel damage as a function of DNBR
- Used in downstream analyses 19
Therm al-Hy draul ics (T-H)
- VIPRE Codes
- COLR Methodo logy TS
- Current - VIPRE-W (Westingho use)
- To be added - VIPRE-01 (Electric Power Research Institute)
- Proposed Treatmen t of Codes
- Separate entities in SQA program (different vendors)
- Interchang eable for licensing applicat ions (numerical results)
((
))
20
T-H Code Modification Process
((
))
21
T-H Code Modification Process
- Existing Change Processes Cannot be Fully Used
- Generic Letter 83-11, Supplement 1, Licensee Qualification for Performing Safety Analyses
- 10 CFR 50.59, Changes, Tests, and Experiments
- 10 CFR 50.90, Application for Amendment of License, Construction Permit, or Early Site Permit
- Proposed Change Process for T-H Codes
- Based on concepts of generic letter and 10 CFR 50.59
- Applicable only to NRC-approved codes and CHF correlations already in Palo Verde TS 5.6.5 (COLR Methodology) 22
T-H Code Modification Process
- SQA Program Implementation Example 1 Limiting Infrequent Event (Loss of Flow from SAFDL) 1.3 1.2 c:r:
zm 1.1 0
1.0
((
0.9
))
0.8 ...................................................................................................................................................,................................................t 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 Time (seconds) 23
T-H Code Modification Process
- SQA Program Implementation Example 2
- CEA Ejection (BHTP)
Pre-Ejected Post-Ejected VIPRE-W VIPRE-01 Power Level Radial Peaking Factor Radial Peaking Factor mDNBR mDNBR 20% 1.1 2.4 1.341 1.341 20% 1.1 2.6 1.131 1.131 20% 1.5 2.3 1.330 1.330 20% 1.5 2.5 1.142 1.142 50% 1.3 2.6 1.360 1.360 50% 1.3 2.8 1.198 1.198 50% 1.5 2.5 1.370 1.370 50% 1.5 2.7 1.207 1.207 24
T-H Code Modification Process
- SQA Program Implementation Example 2
- CEA Ejection (BHTP)
Pre-Ejected Post-Ejected VIPRE-W VIPRE-01 Power Level Radial Peaking Factor Radial Peaking Factor mDNBR mDNBR 65% COLSS In Service 1.1 2.5 1.406 1.407 65% COLSS In Service 1.1 2.7 1.224 1.224 65% COLSS In Service 1.5 2.4 1.308 1.308 65% COLSS In Service 1.5 2.6 1.136 1.136 65% COLSS Out of Service 1.1 1.9 1.540 1.540 65% COLSS Out of Service 1.1 2.1 1.286 1.286 65% COLSS Out of Service 1.5 1.8 1.370 1.370 65% COLSS Out of Service 1.5 2.0 1.139 1.139 25
T-H Code Modification Process
- SQA Program Implementation Example 3
- CETOP-D / BHTP (preliminary results)
- Time of minimum DNBR for the limiting infrequent event (loss of flow from SAFDL)
- CE16STD (CETOP-D / CE-1) = 2.1 seconds
- CE16HTP (CETOP-D / BHTP) = 2.0 seconds
- CE16HTP (( )) = 2.05 seconds 26
T-H Code Modi ficati on Proce ss
- Sui Generis Safety Evaluat ion
- Code and CHF correlatio n must already be in TS 5.6.5
- Limit to Palo Verde, similar to safety evaluatio n for NRC approval of CENTS code applicatio n for CEA ejection at Palo Verde [ML012880473]
- Adoption by others would require prior NRC review and approval
- Specify limitation s and constrain ts
- Specify scope and content for future NRC notificatio ns 27
Mixed Cores
((
))
28
Mixed Cores
- Mechanical Compat ibility
- Thermal -Hydrau lic Compat ibility
- Thermal Margin Assessm ent
- Inlet flow distributio n
- Detailed full core model with each quarter-ass embly
- Demonstrat ion calculation includes all 3 fuel types
- Different spacer grid loss coefficients
((
))
- No generic mixed core penalty required 29
LOCA Analyses
((
))
30
LOCA Analyse s
- 10 CFR 50.46 Analysis Results UFSAR CE16STD / CE16NGF CE16HTP (pre-CE16NGF} I Large Break LOCA Evaluation Model Appendix K Appendix K Realistic PCT 2106 °F 2129.6 °F 1752 °F MLO 11.9% 15.78 % 2.37 %
cwo 0.781 % 0.813 % 0.020 %
Small Break LOCA Evaluation Model Appendix K Appendix K Appendix K PCT 1618 °F 1678 °F 1620 °F MLO 1.28 % 4.5% 2.96 %
cwo 0.2 % 0.33 % 0.006 %
PCT - peak cladding temperature MLO - maximum local oxidation CWO - core-wide oxidation CE16HTP small break LOCA - new time limit on existing operator action 31
LOCA Analy ses
- Long-Te rm Core Cooling
- Analysis for Next Generatio n Fuel license amendm ent remains bounding
- 10 CFR 50.46 Reportin g
- Contain ment Analyse s
- Current mass/en ergy release analyses remain bounding for CE16HTP 32
Non-L OCA Analy ses
((
))
33
Non-L OCA Analy ses
- Control Elemen t Assemb ly (CEA) Ejection
- Example of Framatom e methodo logy adoption for part of analysis
- COPERNIC fuel performa nce code
- Thermal conductivit y degradation (NRC IN 2009-23)
- Corrosion model
((
))
- Apply NRC interim acceptan ce criteria of Standard Review Plan 4.2, Fuel System Design 34
Non-L OCA Analy ses
- Hot Zero Power (HZP) CEA Withdra wal
- Example of COPERNIC implicatio ns for input paramete rs
- Transien t linear heat rate > 21 kW/ft
- Evaluate deposited energy and fuel centerline melt
- Gas gap conducta nce
((
))
- Peak fuel centerlin e temperat ure
- UFSAR - 2600 °F
(( ))
35
Non-L OCA Analy ses
- 21 kW/ft Linear Heat Rate Limit
- Legacy TS
- TS 2.1.1.2, Peak Linear Heat Rate (Safety Limit)
- TS 2.2.1, Reactor Trip Setpoints (Limiting Safety System Setting)
- Current TS
- TS 2.1.1.2, Peak Fuel Centerline Temperatur e - Amendmen t 145, December 2002 [ML023040463]
- TS Table 3.3.1-1, Reactor Protective System Instrumenta tion
- CEN-372- P-A, Fuel Rod Maximum Allowable Gas Pressure, May 1990
((
))
36
Non-L OCA Analy ses
- Limiting Infrequ ent Event (Loss of Flow from SAFDL)
((
))
- CE16HTP Input Parame ters with Other Codes
- CENTS example - tuning factors for core differenti al pressure drop, RCS flow rate, flow coastdow n
- HERMITE example - cladding thermal conductiv ity, cladding specific heat 37
Non -LOC A Ana lyse s
- Main Steam Line Break
((
))
38
Setpo ints
((
))
39
Setpo ints
- CEN-35 6(V)-P- A (Rev. 1-P-A) Method ology
- Exclusive to digital COLSS/CPCS plants
- Core Operating Limits Supervisory System (COLSS)
- Core Protection Calculator System (CPCS)
- Critical heat flux correlatio n
- CETOP with CE-1 CHF correlation installed in Palo Verde COLSS/CPCS
- Same axial-indepe ndent correlation applied to CE16STD design
- Modified statistical combinat ion of uncertain ties (MSCU) process for determina tion of setpoints
- Uncertainty factors are conservativ e to at least a 95°10 probability and 95°10 confidence level
- System parameter uncertaintie s (engineering hot channel factors, CHF correlation, etc.)
- State parameter uncertaintie s (measured state parameters, COLSS and CPCS algorithms, etc.)
40
Set poi nts
- WCA P-16 500- P-A (Sup p. 1, Rev. 1) Meth odolo gy
- Augm ents CEN- 356(V )-P-A metho dolog y
- Critica l heat flux corre lation
((
))
- Metho dolog y chang es addre ss biases introd uced by differ ent CHF corre lation s
- Axial-d epende nt COLSS/CPCS consta nts serve as heat flux penalti es for on-line DNBR calcula tions
- DNB power operati ng limit (POL) error correla tion with tempe rature / pressu re/ flow 41
Setpoin ts
- Mixed Core with Framatome Fuel
- Thermal-hydr aulic analyses
- Model the actual mixed core
- Identify the potentially limiting fuel types
((
))
- COLSS/CPC setpoint overall uncertainty ana lysis
((
))
42
Questions?
43