GO2-12-105, Submittal of Phase 2 Information in Support of License Amendment Request to Change Technical Specifications in Support of Prnm /Arts/Mellla Implementation; NEDO-33750, NEDO-33753; NEDO-33754: NEDO-33755; & NEDO-33758
| ML12219A255 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/31/2012 |
| From: | Sawatzke B Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-12-105 NEDO-33750, NEDO-33753, Letter GE-MS-CT-1 06244-JC14, NEDO-33696, NEDO-33754, NEDO-33755, NEDO-33758 | |
| Download: ML12219A255 (142) | |
Text
ENEY 7\\Bradley J. Sawatzke ENERGY Columbia Generating Station P.O. Box 968, PE08 ERichland, WA 99352-0968 Ph. 509.377.43001 F. 509.377.4150 bjsawatzke @ energy-northwest.com Proprietary - Withhold under 10 CFR 2.390. Attachments 1 through 6, 13, and of Attachment 12 contain PROPRIETARY information.
July 31, 2012 G02-12-105 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SUBMI'TAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM / ARTS / MELLLA IMPLEMENTATION
References:
- 1) BJ Sawatzke (Energy Northwest) to NRC, "License Amendment Request to Change Technical Specifications in Support of PRNM / ARTS /
MELLLA Implementation," January 31, 2012 (ADAMS Accession No. ML1120400144)
- 2) Digital I&C-ISG-06, "Task Working Group #6: Licensing Process Interim Staff Guidance," January 19, 2011 (ADAMS Accession No. ML110140103)
- 3) Letter GNRO-2011/00039 Entergy Operations, Inc. to NRC, "Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531)," May 26, 2011 (ADAMS Accession No. ML111460590)
Dear Sir or Madam:
In Reference 1, Energy Northwest submitted to the Nuclear Regulatory Commission (NRC) a license amendment request (LAR) which proposes to revise the Columbia Generating Station (CGS) Technical Specifications (TS) to reflect the installation of the digital General Electric - Hitachi (GEH) Power Range Neutron Monitoring (PRNM) system. Included in this submittal was a commitment to provide the remainder of the Phase 2 information to support a Reference 2 defined Tier 2 review. Enclosed herein is the requisite Phase 2 information.
The following table provides a roadmap to the Phase 2 information as identified in Enclosure B, "Information to be Provided in Support of a Digital I&C Upgrade License Amendment Request," of Reference 2:
When Attachments 1 through 6, 13, and Enclosure 1 of Attachment 12 are removed from this letter, the letter and remaining Attachments and Enclosures are NON-PROPRIETARY.
,-c'(
/0 IL44C
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION Page 2 Table - CGS PRNM ISG-06 Conformance Documentation Roadmap ISG-06 End B Title Phase 2 Document Item #
The Technical Design Reviews as delineated by GEH procedure CP-03-04 are being performed as part of the software development process as described in Sections 4.4.1.9 and 4.4.2.1 of NEDC-33685P, "Digital I&C-ISG-06 Compliance for Columbia Generating Station NUMAC Power 2.1 Safety Analysis Range Neutron Monitoring Retrofit Plus Option III Stability (D.4.4.2.1)
Trip Function," Revision 1, January 2012. NEDC-33685P was previously provided in Reference 1 as Attachment 2 of.
As identified in NEDC-33685P, the review summary reports are available for NRC review at the GEH office.
2.2 V&V Reports (D.4.4.2.2) 2 The information provided in this document has previously As-Manufactured, been reviewed by the NRC as part of a response to a Grand 2.3 System Configuration Gulf Nuclear Station request for additional information Documentation regarding the PRNM (Reference 3).
(D.4.4.2.3)
Test Design Specification (D.4.4.2.4)
Summary Test Reports 2.5 (Including FAT)
(D.4.4.2.4)
Summary of Test 2.6 Results (Including FAT)
(D.4.4.2.4)
Requirement 2.7 Traceability Matrix (D.9.4.2) 2.8 FMEA (D.9.4.2.1.1)
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION Page 3 Table (continued) - CGS PRNM ISG-06 Conformance Documentation Roadmap ISG-06 End B Title Phase 2 Document Item # 2 2.9 System Build The information provided in this document has previously Documents (D.4.4.3.5) been reviewed by the NRC as part of a response to a Grand Gulf Nuclear Station request for additional information regarding the PRNM (Reference 3).
2.10 Intentionally Blank N/A Qualification Test Methodologies (D.5.2)
Previously provided in Reference 1 as Attachment 2 of Summary of Digital EMI,.
2.12 Temp., Humidity, and Seismic Testing Results (D.5.2) 213 As-Manufactured Logic Previously provided in Reference 1 as Attachment 5 of Diagrams (D.9.2).
System Response Time 2.14 Confirmation Report (D.9.4.2.4) 2.15 Reliability Analyses (D.9.4.2.15, D.10.4.2.15) 2.16 Setpoint Calculations - for Average Power Range Monitor, and (D.9.4.3.8) - for Rod Block Monitor 2.17 Software Tool Analysis 0 Report (D.10.4.2.3.2)
Commercial Grade Not applicable as described in Section 10.3.4.2 of Dedication Report(s)
Reference 1 Attachment 2 of Enclosure 2.
(D.10.4.2.4.2)
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION Page 4 In addition to the Phase 2 information described above, this letter also contains a revision to one of the documents which was provided as part of the Phase 1 information in Reference 1. In Reference 1, as Attachment 5 to Enclosure 2, GEH document NEDC-33696P had been identified as being entirely proprietary. Upon further review, GEH has identified portions of this document that do not contain proprietary information.
Included with this letter, as Attachment 13, is a revised proprietary version of this document with the only changes being the demarcations as to which information is considered proprietary information. Attachment 14 is the non-proprietary version (NEDO-33696) of this report.
The No Significance Hazards Determination and the Environmental Consideration provided in Reference 1 are not impacted by this supplemental submittal.
There are no new commitments identified in this letter.
The following documents are included as Attachments to this letter:
- 1. NEDC-33750P, Revision 0, "Columbia Generating Station Power Range Neutron Monitoring System Failure Mode and Effects Analysis," June 2012 - (Proprietary)
- 2. NEDC-33751 P, Revision 2, "Columbia Generating Station Power Range Neutron Monitoring System Reliability Analysis," June 2012 - (Proprietary)
- 3. NEDC-33753P, Revision 0, "Columbia Generating Station Instrument Limits Calculation Average Power Range Monitor (NUMAC ARTS-MELLLA)," June 2012 - (Proprietary)
- 4. NEDC-33754P, Revision 0, "Columbia Generating Station Instrument Limits Calculation Rod Block Monitor (NUMAC ARTS-MELLLA)," June 2012 -
(Proprietary)
- 5. NEDC-33756P, Revision 1, "Columbia Generating Station Power Range Neutron Monitor V&V Test Summary Report," June 2012 - (Proprietary)
- 6. NEDC-33758P, Revision 0, "Columbia Generating Station Power Range Neutron Monitoring System Response Time Confirmation Report," June 2012 -
(Proprietary)
- 7. NEDO-33750, Revision 0, "Columbia Generating Station Power Range Neutron Monitoring System Failure Mode and Effects Analysis," June 2012 - (Non-Proprietary)
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION Page 5
- 8. NEDO-33753, Revision 0, "Columbia Generating Station Instrument Limits Calculation Average Power Range Monitor (NUMAC ARTS-MELLLA)," June 2012 - (Non-Proprietary)
- 9. NEDO-33754, Revision 0, "Columbia Generating Station Instrument Limits Calculation Rod Block Monitor (NUMAC ARTS-MELLLA)," June 2012 - (Non-Proprietary)
- 10. NEDO-33755, Revision 0, "Columbia Generating Station Power Range Neutron Monitoring System Software Tools Summary Report," June 2012 - (Non-Proprietary)
- 11. NEDO-33758, Revision 0, "Columbia Generating Station Power Range Neutron Monitoring System Response Time Confirmation Report," June 2012 - (Non-Proprietary)
- 12. Letter GE-MS-CT-1 06244-JC1 4 from Jamie Creech (GEH) to James Snyder (Energy Northwest), "CGS DI&C-ISG-06 Enclosure B, Phase 2 Items 2.2, 2.3, and 2.9," dated June 12, 2012. Included with this letter are the following
Enclosures:
- 1. DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station - (Proprietary)
- 2. DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station - (Non-Proprietary)
- 3. Affidavit
- 13. NEDC-33696P, Revision 1, "Columbia Generating Station Power Range Neutron Monitoring System Architecture & Theory of Operations Report," July 2012 -
(Proprietary)
- 14. NEDO-33696, Revision 1, "Columbia Generating Station Power Range Neutron Monitoring System Architecture & Theory of Operations Report," July 2012 -
(Non-Proprietary)
GEH considers certain information contained in Attachments 1 through 6, 13, and to Attachment 12 to be proprietary and, therefore, requests that these be withheld from public disclosure in accordance with 10 CFR 2.390. Non-proprietary versions of Attachments 1, 3, 4, 6 and 13 are provided as Attachments 7, 8, 9, 11 and 14 respectively.
A non-proprietary version of Attachment 12 Enclosure 1 is included as Attachment 12. Because the vast majority of information provided in Attachments 2 and 5 are considered proprietary, non-proprietary versions would be of no value; therefore, redacted versions of these documents are not being provided.
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION Page 6 Attachments 1 through 6, and 13, also contain the associated affidavits, within the first few pages of each document, for the requests to be withheld from public disclosure. The affidavit for Attachment 12 Enclosure 1 is provided in Enclosure 3 of Attachment 12.
In Reference 1 Energy Northwest identified the intent to install the PRNM and ARTS /
MELLLA improvements during the next planned refueling outage after NRC approval is received (with the earliest opportunity being in the spring 2013). Based on outage schedules and resource loading, the scheduled implementation of PRNM and ARTS /
MELLLA improvements has been moved to the subsequent refueling outage (spring 2015). As such, approval of the LAR is requested by January 30, 2014 to support the proposed installation schedule.
In accordance with 10 CFR 50.91, a copy of this supplemental submittal, with attachments, is being provided to the designated Washington State Official.
Should you have any questions or require additional information regarding this matter, please contact Mr. ZK Dunham, Licensing Supervisor, at (509) 377-4735.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.
Respectfully, BJ g'awatzke Vice President, Nuclear Generation & Chief Nuclear Officer Attachments and
Enclosures:
As described herein cc: Regional Administrator - NRC RIV Project Manager - NRC NRR NRC Senior Resident Inspector/988C A.J. Rapacz-BPA/1399 W.A. Horin - Winston & Strawn J.O. Luce - EFSEC R.R. Cowley - WDOH
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM /
ARTS / MELLLA IMPLEMENTATION NEDO-33750, Revision 0 Columbia Generating Station Power Range Neutron Monitoring System Failure Mode and Effects Analysis June 2012 (Non-Proprietary)
HITACHI GE Hitachi Nuclear Energy NEDO-33750 Revision 0 DRF Section 0000-0144-7420 R1 June 2012 Non-Proprietary Information - Class I (Public)
COLUMBIA GENERATING STATION POWER RANGE NEUTRON MONITORING SYSTEM FAILURE MODE AND EFFECTS ANALYSIS Copyright 2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33750 Revision 0 INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33750P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a license amendment request by Energy Northwest for a power range neutron monitoring system upgrade in proceedings before the U.S. Nuclear Regulatory Commission. The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
ii
NEDO-33750 Revision 0 Table of Contents 1.
Introduction.............................................................................................................................
1
- 2.
Overview.................................................................................................................................
1
- 3.
Technical Evaluation..........................................................................................................
1
- 4.
Sum m ary and Conclusion..................................................................................
...................... 3
- 5.
References...............................................................................................................................
3 iii
NEDO-33750 Revision 0 APRM CGS CP D3 DI&C FMEA GEH IEEE ISG LAR LPRM LTR NRC NUMAC OPRM PRNMS RBM RG RPS SE Acronyms and Abbreviations Defihiitionf Average Power Range Monitor Columbia Generating Station Common Procedure Diversity and Defense-in-Depth Digital Instrumentation and Control Failure Mode and Effects Analysis GE Hitachi Nuclear Energy Institute of Electrical and Electronics Engineers Interim Staff Guidance License Amendment Request Local Power Range Monitor Licensing Topical Report Nuclear Regulatory Commission Nuclear Measurement Analysis and Control Oscillation Power Range Monitor Power Range Neutron Monitoring System Rod Block Monitor Regulatory Guide Reactor Protection System Safety Evaluation iv
NEDO-33750 Revision 0
- 1. Introduction This report addresses Digital Instrumentation and Control (DI&C) Interim Staff Guidance (ISG)-06 (Reference 1) Section D.9.4.2.1.1 and provides an assessment of the effects of single failures.
- 2. Overview The Nuclear Regulatory Commission (NRC) previously reviewed the design of the Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitoring System (PRNMS) retrofit design against Institute of Electrical and Electronics Engineers (IEEE)
Standard 279-1971, "Criteria for Protection S~'stemis for Nuclear Power Generating Stations" (Reference 2), and the NRC staff found that "(the PRNMS design) provides the required isolation and physical independence to ensure acceptable defense against Single-Failures." See Section 3.1 of the NRC Safety Evaluation (SE) (Reference 3). The present discussion reviews and reaffirms the basis for concluding the design is adequate.
More recent regulatory guidance and industry standards updated the definition of the Single-Failure Criterion.
Namely, Regulatory Guide (RG) 1.153, "Criteria for Safety Systems" (Reference 4) endorses IEEE Standard 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations" (Reference 5), and RG 1.53, "Application of the Single-Failure Criterion to Safety Systems" (Reference 6) endorses IEEE Standard 379-2000, "IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems" (Reference 7). These two IEEE standards provide an updated Single-Failure Criterion that is somewhat different from the one in IEEE Standard 279-1971 (Reference 2) because they include some additional considerations in three sub-clauses. The present discussion evaluates the NUMAC PRNMS design against the updated definition of the Single-Failure Criterion, and explains why the design is adequate.
- 3. Technical Evaluation As discussed in the original NUMAC PRNMS licensing topical report (LTR, Reference 8)
Section 4.4.1.1.2, ((
1
NEDO-33750 Revision 0 The updated definition of the Single-Failure Criterion, as found in IEEE Standard 379-2000 (Reference 7) and IEEE Standard 603-1991 (Reference 5), includes additional considerations in three sub-clauses. The following discussion addresses each of these sub-clauses and shows that the PRNMS design satisfies them.
The first sub-clause requires that the system perform its safety functions in the presence of a single failure concurrent with all identifiable but non-detectable failures. As discussed above, in connection with IEEE Standard 279-1971 Clause 4.2, the NUMAC PRNMS continues to perform its safety function in the presence of a single failure.
The system also meets the additional consideration of "identifiable but non-detectable failures" mainly through self-testing.
As explained in Section 6.3.5 of the PRNMS LTR (Reference 8), ((
)) See Section 3.6.2 of the NRC SE (Reference 3).
As discussed in Section 2.4.11 of Reference 9, a Technical Design Review was conducted in accordance with GE Hitachi Nuclear Energy (GEH) Common Procedure (CP)-03-04, Technical Reviews (Reference 10). These reviews require a Failure Mode and Effects Analysis (FMEA) as one of the deliverables. During the CGS PRNMS project, the findings in the NUMAC PRNMS LTR and SE were confirmed. Specifically, identified failure modes that could impair a trip function were detectable.
Additionally, it should be noted that the NUMAC PRNMS will continue to perform its safety function even in the presence of a second random failure. ((
)) The PRNMS design meets the first sub-clause.
The second sub-clause requires that the system perform its safety function in the presence of all failures caused by the single failure.
As discussed above in connection with IEEE Standard 279-1971, the redundant channels are independent and isolated. Other clauses in the industry standards address this aspect of system design, and were included as attachments to of the License Amendment Request (LAR, Reference 11) demonstrating that the PRNMS design is acceptable. See Section 4.4.1.1.6 of the NUMAC LTR (Reference 8), Section 3.5 of the NRC SE (Reference 3), and Section 9.2.6 of the NEDC-33685P (Reference 9).
Besides physical and electrical isolation, another related aspect is inter-division communication.
The PRNMS inter-division communication is discussed in NEDC-33697P (Reference 12), which 2
NEDO-33750 Revision 0 addresses D.7.2 of DI&C-ISG-06 (Reference 1) and includes the DI&C-ISG-04 (Reference 13) compliance matrix.
Collectively, the PRNMS isolation and the acceptable inter-division communication ensure that a credible fault or failure in one channel will not cascade to and impair another channel. Therefore, the effects of the Single-Failure are confined to that single channel, and with only one channel impaired, a scram occurs when any two of the remaining three APRM channels detect a trip condition. The PRNMS design meets the second sub-clause.
The third sub-clause requires that the system perform its safety functions for a design basis event in the presence of all failures and spurious system actions that cause or are caused by the design basis events requiring the safety function. The CGS PRNMS Diversity and Defense-in-Depth (D3) Analysis (Reference 14) Section 4.2 tabulates all the CGS design basis events and identifies the credited trip signal. Based on a review of these events, those that require a PRNMS trip signal clear'ly will not also impair the PRNMS. Additionally, the NUMAC PRNMS equipment is qualified, as discussed in Sections 4.4.1.1.5 and 4.4.2 in the NUMAC LTR (Reference 8) and Section 5 of NEDC-33685P (Reference 9). Thus, the design meets the third sub-clause.
- 4. Summary and Conclusion In summary, the retrofit NUMAC PRNMS system satisfies the Single-Failure Criterion, as it is defined in References 2, 5, and 7.
- 5. References
- 1. DI&C-ISG-06, "Task Working Group #6: Licensing Process," Revision 1, January 19, 2011 (ADAMS Accession No. MLl110140103).
- 2. IEEE Standard 279, "Criteria for Protection Systems for Nuclear Power Generating Stations," 1971.
- 3. Letter, NRC to Mr. David W. Reigel (GE), "Acceptance of Licensing Topical Report NEDC-32410-P, Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNMS) Retrofit Plus Option III Stability Trip Function (TAC No. M90616),"
September 5, 1995.
- 4. NRC RG 1.153, "Criteria for Safety Systems," Revision 1, June 1996.
- 5. IEEE Standard 603, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," 1991.
- 6. NRC RG 1.53, "Application of the Single-Failure Criterion to Safety Systems," Revision 2, November 2003.
- 7. IEEE Standard 379, "IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems," 2000.
- 8. GE Nuclear Energy, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNMS) Retrofit Plus Option III Stability Trip Function," NEDC-32410P-A, Volume 1, October 1995.
- 9. GE Hitachi Nuclear Energy, "Digital I&C-ISG-06 Compliance for Columbia Generating Station NUMAC Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function,"
NEDC-33685P, Revision 1,
January 2012 (ADAMS Accession No. ML12040A074).
- 10. CP-03-04, Technical Reviews.
3
NEDO-33750 Revision 0
- 11. Letter, B.J. Sawatzke (CGS) to NRC Document Control Desk, "Columbia Generating Station, Docket No. 50-397, License Amendment Request to Change Technical Specifications in Support of PRNM/ARTS/MELLLA Implementation," G02-12-017, January 31, 2012 (ADAMS Accession No. ML12040A072).
- 12. GE Hitachi Nuclear Energy, "Columbia Generating Station Power Range Neutron Monitoring System Design Analysis Report," NEDC-33697P, Revision 1, January, 2012 (ADAMS Accession No. ML12040A077).
- 13. DI&C-ISG-04, "Task Working Group
- 4:
Highly Integrated Control Rooms-Communications Issues,"
Revision 1, March 6,
2009 (ADAMS Accession No. ML083310185).
- 14. GE Hitachi Nuclear Energy, "Columbia Generating Station Power Range Neutron Monitoring System Diversity and Defense-in-Depth (D3) Analysis," NEDC-33694P, Revision 0, November 2011 (ADAMS Accession No. ML12040A076).
4
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM /
ARTS / MELLLA IMPLEMENTATION NEDO-33753, Revision 0 Columbia Generating Station Instrument Limits Calculation Average Power Range Monitor (NUMAC ARTS-MELLLA)
June 2012 (Non-Proprietary)
Qý HITACHI GE Hitachi Nuclear Energy NEDO-33753 Revision 0 DRF Section 0000-0148-3954 RO June 2012 Non Proprietary Information - Class I (Public)
COLUMBIA GENERATING STATION INSTRUMENT LIMITS CALCULATION AVERAGE POWER RANGE MONITOR (NUMAC ARTS-MELLLA)
Copyright 2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33753 Revision 0 INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33753P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a license amendment request by Energy Northwest, for a power range neutron monitoring system upgrade in proceedings before the U.S. Nuclear Regulatory Commission. The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
ii
NEDO-33753 Revision 0 Table of Contents Acronyms and Abbreviations............................................................................................................
iv E xecutive Sum m ary...............................................................................................................................
vi
- 1.
Function:
APRM Flow Biased Simulated Thermal Power Scrams and Rod Withdrawal B lo ck s...........................................................................................................................................
1 1.1 APRM Flow Biased "Simulated Thermal Power - High" (Scram) Two-loop Operation.....
3 1.2 APRM Flow Biased "Simulated Thermal Power - High" (Scram) Single-loop Operation......... 3 1.3 APRM Flow Biased Simulated Thermal Power - High (Rod Block) Two-loop Operation........ 4 1.4 APRM Flow Biased Simulated Thermal Power - High (Rod Block) Single-loop Operation..... 4 1.5 APRM STP Scram Clamp.......................................................................................................
4 1.6 APRM STP Rod Block Clamp................................................................................................
5 2.
C om p on ents.................................................................................................................................
6 2.1 F low T ransm itter.........................................................................................................................
6 2.2 Flow Electronics (Recirculation Flow Monitor System)......................................................
10 2.3 Power Electronics (LPRM, APRM, Trip Circuit).................................................................
13
- 3.
Sum m ary R esults.......................................................................................................................
16
- 4.
Comments and Recommendations..........................................................................................
17
- 5.
R eferen ces..................................................................................................................................
2 0 iii
NEDO-33753 Revision 0 AGAF AL ALT APEA APRM ARTS AV CGS CLTP CP D3 DI&C dP DPEA EMI FMEA FS FT GEH HP IEEE LAT LER LP LPRM M&TE MELLLA NIST NTSP NUMAC OL ACRONYMS AND ABBREVIATIONS
~Definition APRM Gain Adjustment Factor Analytical Limit As Left Tolerance Primary Element Accuracy-Accuracy Error Average Power Range Monitor Average Power Range Monitor, Rod Block Monitor Technical Specification Improvement Program Allowable Value Columbia Generating Station Current Licensed Thermal Power Common Procedure Diversity and Defense-in-Depth Digital Instrumentation & Control Differential Pressure Primary Element Accuracy-Drift Error Electromagnetic Interference Failure Mode and Effects Analysis Full Scale Flow Transmitter GE Hitachi Nuclear Energy High Pressure Institute of Electrical and Electronics Engineers Leave Alone Tolerance Licensing Event Report Low Pressure Local Power Range Monitor Maintenance and Testing Equipment Maximum Extended Load Line Limit Analysis National Institute of Standards and Technology Nominal Trip Setpoint Nuclear Measurement Analysis and Control Operational Limit iv
NEDO-33753 Revision 0 P/C Process Computer PEA Primary Element Accuracy PMA Process Measurement Accuracy RB Rod Block RFI Radio Frequency Interference RTP Rated Thermal Power SLO Single-Loop Operation SP Calibrated Span STA Spurious Trip Avoidance STP Simulated Thermal Power TID Total Integrated Dose TLO Two-Loop Operation TS Technical Specifications URL Upper Range Limit VA Vendor Accuracy VD Vendor Drift V
NEDO-33753 Revision 0 EXECUTIVE
SUMMARY
This document is a supplement analysis data sheet to Reference 1. Included in this document in sequential order are:
the setpoint functions for the system,
- the setpoint function analyses inputs and the source reference of the inputs,
- the devices in the setpoint function instrument loop,
- the component analysis inputs and input sources,
" the calculated results, input comments and result recommendations, references.
System: Average Power Range Monitor (APRM)
The following setpoint functions are included in this document:
Flow Biased "Simulated Thermal Power - High" (Scram) (two-loop operation (TLO) and single-loop operation(SLO))
Note: The titles from the Technical Specifications (TS) are shown above within quotation marks.
vi
NEDO-33753 Revision 0
- 1. FUNCTION: APRM FLOW BIASED SIMULATED THERMAL POWER SCRAMS AND ROD WITHDRAWAL BLOCKS Setpoint Characteristics:
Definition Reftrence(s)
Event Protection:
Limiting event for the setpoint Scram: This function is not credited in any plant Safety Ref. 3.1 Bases Analyses. The TS identify that this function is required for Section B 3.3.1.1 Mode 1.
Rod Block: This function avoids conditions that would require Reactor Protection System action if allowed to Ref. 3.1 Bases proceed. The APRM High RB is set below the APRM Flow Section B 3.3.1.1, Biased Thermal Power - High Scram, and as an operational Ref. 3.2 Section safeguard, initiates a RB before the APRM Fixed Neutron 7.7.1.2.2.2.b.2(a)
Flux-High Scram. This function is not a TS limit.
Function After Earthquake
[]
Required Z
Not Required Comment 18 for Flow Transmitter Setpoint Direction
" Flow Biased Simulated
[
Increasing Decreasing Thermal Power (STP) Scram (TLO and SLO)
" Flow Biased STP Rod Block (TLO and SLO)
Z Increasing E
Decreasing Single or Multiple Channel EZ Single Z
Multiple Licensing Event Report (LER)
Standard (Conservative) LER Calculation
[], or Ref. 1 Section Calculation Basis if Multiple Configuration Specific LER Calculation El 5.3, Ref. 2 Channel Section 1.2.3 Trip Logic for Configuration N/A Specific LER Calculation Plant Data:
____alue__
Sigma if not2 Rleference(s):
Flow Element Primary Element
" Accuracy (APEA)
+ 3.3% FS loop flow;
" Drift (DPEA) n/a Flow Process Measurement Accuracy (PMA)
" PMA (Flow noise)
+/- 1% rated Recirc flow
" PMA (Flow transmitter (FT) 0.0%
taps-static head)
I
NEDO-33753 Revision 0
- 1.
Function: APRM Flow Biased Simulated Thermal Power Scrams and Rod Withdrawal Blocks (cont'd)
Plant Data:
I
',[Sigma if not 2 Reference(s)
Local Power Range Monitor (LPRM) Detector (APRM PEA)
(% power)
APEAAccuracy 1%; bias 0.49%
APEAPowerSupplyEffect negligible Ref. 2, Comment 6 DPEA
+ 0.2% / 7 days; bias 0.33% / 7 days LPRM Detector (APRM PMA)
(% power)
" Tracking
+ 1.11%
" Noise (STP flow-biased n/a setpoints)
Components (or Devices) in Setpoint Function Instrument Loop:
Flow Element LPRM Detector Flow Transmitter NUMAC Chassis:
Instrument Loop Flow Electronics (Recirculation Flow Monitor System)
" Instrument Loop Power Electronics (LPRM, APRM, Trip Circuit) 2
NEDO-33753 Revision 0 1.1 APRM Flow Biased "Simulated Thermal Power - High" (Scram) Two-loop Operation Current Function Limits:
Analytical Limit (AL) n/a n/a n/a n/a TS Allowable Value (AV) 0.58Wd + 62%
0.6 3Wd + 64%
Nominal Trip Setpoint 0.5 8Wd + 59%
Results provided in (NTSP)
Section 3 Operational Limit (OL)
None provided 0.6 3 Wd + 58.1%
Ref. 1, Ref. 2, Comment 14 1.2 APRM Flow Biased "Simulated Thermal Power - High" (Scram) Single-loop Operation Current Function Limits:
Analytical Limit n/a n/a n/a n/a TS Allowable Value 0.58Wd + 62%
0.63(Wd-AW) + 64.0%
(Same as TLO) 0.6 3 Wd + 60.8%
Nominal Trip Setpoint 0.58Wd + 59%
Results provided in (Same as TLO)
Section 3 Operational Limit None provided n/a Ref. 1, Ref. 2, Comment S11
- AW =5.
3
NEDO-33753 Revision 0 1.3 APRM Flow Biased Simulated Thermal Power - High (Rod Block) Two-loop Operation Current Function Limits: [I Vaie/Eqationr I
r*!:
P Ros-nItEonLLA, Condition ~~
Reference(s)
Analytical Limit n/a n/a na n/a TS Allowable Value 0.58Wd + 53%
- 0. 63Wd + 60.1%
Nominal Trip Setpoint 0.58Wd + 50%
Results provided in Section 3 Operational Limit None provided n/a Ref. 1, Ref.
2, Comment 14 1.4 APRM Flow Biased Simulated Thermal Power - High (Rod Block) Single-loop Operation Current Function Limits: I'
-aUq u ano n, I
i I.
CLTPv
(-0 I V)
ARTS-MEELLA Condition' Refe~rencu(s)*
Analytical Limit n/a n/a n/a TS Allowable Value 0.58Wd + 53%
- 0. 6 3(Wd -AW) + 60.1%
(Same as TLO) 0.63Wd + 56.9%
Nominal Trip Setpoint 0.58Wd-+ 50%
Results provided in (Same as TLO)
Section 3 Operational Limit None provided n/a Ref. 1, Ref. 2, Comment
- AW=5.
1.5 APRM STP Scram Clamp Current Function Limits:
alue/Equation, CLT 111
.ARTS-MELILLARfe.ces Analytical Limit 117%
n/a n/a Allowable Value 114.90%
114.9%
Nominal Trip Setpoint 113.50%
Results provided in Section 3 Operational Limit n/a 109.0%
Ref 1, Ref 2, Comment 14, Comment 23 4
NEDO-33753 Revision 0 1.6 APRM STP Rod Block Clamp Current Function Limits:
Analytical Limit n/a n/a n/a n/a Allowable Value n/a 111%
Nominal Trip Setpoint n/a Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 14 5
NEDO-33753 Revision 0
- 2. COMPONENTS 2.1 Flow Transmitter Component Information:
N aliue/iiiiiutio
- < Reference(s)*
Plant Instrument ID No.
RRC-FT-14A (B35-NO14A)
Instrument vendor Rosemount Model ID No. (including 1153DB5PA Range Code)
Plant Location(s)
E-IR-P006, elevation 471', column 4.1/R5 Process Element Flow Element (Flow Elbow)
Inputs:
Vendor Specifications
- Value
- Euation Sigm iaf not 2 Reference s Top of Scale 362.4 inWC 20mA Bottom of Scale 0 inWC Upper Range Limit (URL) 750 inWC Accuracy 0.25% SP 3
Ref. 4.6 Temperature Effect (0.75% URL + 0.5% Span)/100F 3
Ref. 4.6 Seismic Effect 0.5% URL at 4g Ref. 4.4 Section 6, Comment 18 Radiation Effect
+/-8.0% URL during and after exposure to Ref. 4.4 Section 6, 2.2xl 0 7 rads Total Integrated Dose (TID)
Comment 17 6
NEDO-33753 Revision 0 2.1 Flow Transmitter (cont'd)
Y p
Vendor Specifications
~Value / Equation
~Sigma if not Reference(s)
Vendor Specifications Value / Equation Simaifno Reference(s)
Humidity Effect negligible Comment 4 Power Supply Effect 0.02% SP
<0.005% of output span per volt RFI/EMI Effect included in accuracy Comment 4 Insulation Resistance 0.0%
Effect Over-pressure Effect
+ 1% URL 3
Ref. 4.4, Ref. 4.6 (Maximum zero shift after 2,000 psi overpressure).
Static Pressure Effect 3
Ref. 4.4, Ref. 4.6, (psid)
Comment 16
" Zero Effect
+ 0.2% URL per 1000 psi (calibrated out)
" Range Span Effect
+/- 0.5% of input reading/I,000 psi (calibrated out)
Mounting Position Effect 3
Ref. 4.4 (page 6-5)
Zero Shift Up to 1.5 InH 20 Ref. 4.6 (calibrated out)
Span Effect None Plant Data:
7 Value KFl efiretice(s) ~
Calib Temperature Range 70 to 104 OF Normal Temperature Range 40 to 104 OF Trip Temperature range 40 to 104' °F Comment 20 Plant seismic value 0.5g Plant Radiation value 2.07 x 106 rads TID Plant Humidity value 20 to 90% RH Power Supply Variation value 24Vdc +/- 2.0 Vdc RFI/EMI value Negligible Over-pressure value 1375 psig Static Pressure value 1039 psig 7
NEDO-33753 Revision 0 2.1 Flow Transmitter (cont'd)
Drift:
Current Calib. Interval 184 days Ulncludes extra 2n%
Desired Calib. Interval 24 months lIncludes extra 25%
Drift Source
[ Vendor E'Calculated Ref. 3.1, Table 3.3.1.1-1, Item 2.b., SR 3.3.1.1.9 Comment 3 Ref. 1, Ref. 2 Ref. 4.4 Section 6, Comment 12 Drift Value
+ 0.2% URL /30 months Calibration:
Value / equatlon*
Sigma if not 3
+
Reference(s)
As Left Tolerance (ALT)
+/- 0.07% SP Leave Alone Tolerance
+/- 0.07% SP (LAT)
Input Calibration Tool:
Pressure gauge (Wallace & Tiernan or Accuracy
- 1.0 inWC Minimum Comment 10 approx. +/-- 0.28% SP Resolution / Readability approx. +/- 0.07% SP Minor Division 0.5 inWC Upper Range Temperature Effect Input Calibration NIST Standard:
Accuracy
= 1/4 Tool accuracy Comment 10
+/-0.071108% SP Resolution / Readability Minor Division Upper Range Temperature Effect 8
NEDO-33753 Revision 0 2.1 Flow Transmitter (cont'd)
I Value / equation I Sigmaifnot 3 Reference(s)
Output Calibration Tool:
Fluke 45 Accuracy
+/- 0.0 13 mAdc Comment 10
=+0.08125% SP Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard:
NIST 7
Accuracy
=1/4 Tool Accuracy Comment 10
+ 0.020313% SP Resolution / Readability Minor Division Upper Range Temperature Effect 9
NEDO-33753 Revision 0 2.2 Flow Electronics (Recirculation Flow Monitor System)
~lue/Eauation~
~Refetence(s~
Comoonent Information:
Vaiue/Edfiatio""
- Refe*enc*(si Plant Instrument ID No.
Not provided Comment 2 Instrument vendor GEH Ref. 4.2 Model ID No. (including Range NUMAC Ref. 4.2 Code)
Plant Location(s)
Control Room Process Element n/a Inputs:
Vendor Specifications
!*Value / E*quation si""ni it manot '2*<
tteferenegs)*:":*:"
Top of Scale 125% loop flow Ref. 4.2 Sections I id ',i4.3.5.3, 4.3.5.4, 4.6.2 20mAdc Bottom of Scale 0% loop flow Ref. 4.2 Sections TVdc Ref.
4.3.5.3, 4.3.5.4, 4.6.2 4 mAde c}
.I Upper Range Limit n/a includediaccurRef.
4.2 Sections 4.3.5.3, Se 4.6.2 Accuracy
+ 0.122 mAdc Comment 21 (where 16 mAdc input span from FT corresponds to 125% flow)
Temperature Effect included in accuracy Ref. 4.5, Section 4.6.2 Seismic Effect included in accuracy Ref. 4.5 Section 4.21.1 and Section 4.2.6, Comment 4 Radiation Effect Included in accuracy Ref. 4.5 Section 4.2.4, Comment 4.
Humidity Effect included in accuracy Ref, 4.5 Section 4.2.2, Comment 4 Power Supply Effect included in accuracy Comment 4 RFI/EMI Effect negligible Ref. 4.5 Section 4.2.5, Comment 4 Insulation Resistance Effect negligible Comment 4 Over-pressure Effect n/a Comment 5 Static Pressure Effect n/a Comment 5 Plant Data:
Value Sigma if not 2 Reference(s)
Calib Temperature Range 70 to 104 OF Normal Temperature Range 40 to 104 OF Trip Temperature range 40 to 104 OF Comment 20 10
NEDO-33753 Revision 0 2.2 Flow Electronics (cont'd)
Plant Data:
Plant seismic value 0.7g Plant Radiation value n/a Plant Humidity value 10 to 60% RH Power Supply Variation value Not provided RFI/EMI value Not provided Over-pressure value n/a Static Pressure value n/a Comment 2 Comment 2 Comment 5 Comment 5 Value Reference s Drift:
Value Current Calib. Interval 184 days [l"Includes extra 25%
Desired Calib. Interval 24 months ["Includes extra 25%
Drift Source
-Vendor ZCalculated Reference~s)
Ref. 3.1, Table 3.3.1.1-1, Item 2.b., SR 3.3.1.1.9 Comment 3 Ref. 1, Ref. 2 Ref. 1 Section 3.3, Ref. 2 Drift Value
(% rated drive flow)
((
))
= + 0.122 mAdc / 6 months 11
NEDO-33753 Revision 0 2.2 Flow Electronics (cont'd) 9.
Value I equation~
~Siexna ifiiot 3
~Reference(s)
Calibration:
Value / equation Sigmia if. nt :3 Reference(s)
As Left Tolerance n/a Leave Alone Tolerance n/a Input Calibration Tool:
Internal to NUMAC Accuracy
+/- (1.1)*0.192% units on 125% scale Comment 15 Resolution / Readability included in accuracy Minor Division included in accuracy Upper Range 125%
Temperature Effect included in accuracy Input Calibration Standard:
included in calibration tool Accuracy n/a Resolution / Readability n/a Minor Division n/a Upper Range n/a Temperature Effect n/a Output Calibration Tool:
n/a Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard:
n/a Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect 12
NEDO-33753 Revision 0 2.3 Power Electronics (LPRM, APRM, Trip Circuit)
F
(*nmnnnpnf lnfnrrn*flnn
- Plant Instrument ID No.
Not provided Comment 2 Instrument vendor GEH Ref. 4.2 Model ID No. (including Range NUMAC Ref. 4.2 Code)
Plant Location(s)
Control Building Process Element Neutron detector - LPRMs: NA250 and NA300 Ref. 4.2 Sections 1.5 & 3.2 Inputs:
Vendor Specifications Value IEquation Sigma ifxnt References*s Top of Scale FS = 125%
Ref 4.2 Section 4.3.2 Bottom of Scale 0%
R Section 4.3.2 Upper Range Limit n/a %
Ref. 4.2 Section 4.3.2 Accuracy ALPRM Detector -
" LPRM Detector See APRM PEA (Section 1)
" LPRM Electronics
+ 0.943% (% local power)
Temperature Effect included in accuracy Seismic Effect included in accuracy Ref. 4.5 Section 4.1.1, Comment 4 Radiation Effect Included in accuracy Ref. 4.5 Section 4.2.4, Comment 4 Humidity Effect included in accuracy Ref. 4.5 Section 4.2.2, Comment 4 Power Supply Effect (Detector)
See APRM PEA RFI/EMI Effect negligible Ref. 4.5 Section 4.2.4, Comment 4 Insulation Resistance Effect negligible Comment 4 Over-pressure Effect n/a Comment 5 Static Pressure Effect n/a Comment 5 13
NEDO-33753 Revision 0 2.3 Power Electronics (LPRM, APRM, Trip Circuit) (cont'd)
Plant Data:
Value Calib Temperature Range 70 to 104 0F Normal Temperature Range 40 to 104 'F Trip Temperature range 40 to 104 'F Comment 20 Plant seismic value 0.7g Plant Radiation value n/a Plant Humidity value 10 to 60% RH Power Supply Variation value Not provided Comment 2 RFI/EMI value Not provided Comment 2 Over-pressure value n/a Comment 5 Static Pressure value n/a Comment 5 Drift:
N
,Yalue Si* ma if n'ot 2 Reference(s)
Current Calib. Interval 7 days
[-Includes extra Ref. 3.1 25%
Table 3.3.1.1-1
_SR 3.3.1.1.2 Desired Calib. Interval 7 days
-"Includes extra Ref 3.1 25%
Table 3.3.1.1-1
~SR 3.3.1.1.2 Drift Source
[]Vendor ECalculated Ref. 1, Ref. 2 Drift Value
+ 0.5% FS / 700
+/- 0.5% SP / 8.75 Ref 4.3
(% power) hours days Section 4.3.3.3, Comment 9 14
NEDO-33753 Revision 0 2.3 Power Electronics (LPRM, APRM, Trip Circuit) (cont'd)
Calibration:
Value / equation Sigma if not 3 Reference(s)
Included in APRM calibration As Left Tolerance AGAF Comment 7 Leave Alone Tolerance
-ALT Comment 7 Input Calibration Tool:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Input Calibration Standard:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Tool:
n/a K
Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard:V n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range i
Temperature Effect Application Specific Input:
Value Sigma if not 2 Reference~s)
Minimum no. of LPRMs per Ref. 4.1 APRM Channel 20 of 43 Section 4.1.5, Comment 25 APRM Gain Adjustment Factor
+ 2% RTP 3
15
NEDO-33753 Revision 0
- 3.
SUMMARY
RESULTS Calculated Values Setpoint Function Allowable Value (AýV)
~,%ARTS-MELLLL4 P
~R111 Nominal Trip Setpoint (0,' ARTS-VIBJ.ILA RrIR)
Nleets~
LER~
Criiteria Meets Spuriouis Trip Avoidance Commnet 13)y APRM STP Scram Clamp 114.9%
112.9%
Y Y
108.0%
Y n/a (Comment 23)
Flow Biased STP-High Scram 0.6 3 Wd + 64.0%
- 0. 63 Wd + 62.0%
Y Y
- TLO Flow Biased Neutron Flux-
- 0. 63 Wd + 60.1%
- 0. 6 3Wd + 58.1%
Y n/a High RB - TLO Flow Biased STP-High Scram 0.6 3 (Wd - AW)+ 64.0%
0.6 3 (W, - AW) + 60.2%
Y n/a
- SLO (Comment 22, O.6 3Wd + 60.8%
O.63 Wd
+ 57.1%
Comment 24)
- 0. 63 (Wd - SLOsettingAdi) +
62.0%
Flow Biased Neutron Flux-
- 0. 6 3(Wd - AW) +
0.63(Wd - AW) + 56.3%
O.63Wd +53.2%
(Comment 22, Comment 24) 0.6 3 Wd + 56.9%
- 0. 63 (Wd - SLOsettingAdJ) +
58.1%
T "Wd" in the APRM flow-biased equations is defined, as the % Recirculation drive flow, where 100% drive flow is that required to achieve 100% core power and flow. The AL equations that include AW were derived as part of the ARTS-MELLLA setpoint calculation. The TLO AW is 0% and the SLO AW is 5% (Comment 8).
Application Specific Setpoint Adjustments TLO to SLO Setting Adjustment for NUMAC setpoints I Minimum Required Margins (% RTP)
I 2.000 3.700 I
16
NEDO-33753 Revision 0
- 4. COMMENTS AND RECOMMENDATIONS
- 1. Unless specifically identified as "bias" errors in this document, all instrument uncertainty errors will be considered to be random in nature, even when the "+/-" symbol is not shown.
- 2. Some plant specific information has not been provided in the current CGS setpoint calculation(s) and is considered unnecessary because the impact of this information is included within the instrument accuracy values, or considered negligible.
- 3. Calibration interval of 24 months is used in the analysis. The plant is on a 24 month cycle, but there is no verified input to that effect. 24 months used in the drift analysis is conservative even if the calibration is done on an 18 month cycle.
- 4. Seismic effect, radiation effect, humidity effect, power supply effect, RFI/EMI effect, and insulation resistance effect errors are marked "negligible" or "included in accuracy" and are considered to have negligible impact on the manufacturer's accuracy terms when they are not identified separately.
- 5. Per Reference 1 and Reference 2, overpressure effects are only applicable to pressure measurement devices (e.g., differential pressure transmitters), and static pressure effects are only applicable to differential pressure measurement devices. These effects are marked "n/a" for other devices.
- 6. ((
)) (Reference 2 Section 4.5.3)
- 7. The APRM subsystem is calibrated on-line weekly (Reference 3.1) using the APRM Gain Adjustment Factor (AGAF) process, where the gain of the APRMs is adjusted to read the Core Thermal Power (CTP) determined by the Process Computer (P/C), within a specified ALT. ((
Thus, the only calibration error to consider for the APRM electronics sub-loop is the As Left Tolerance specified by the AGAF process.
- 8.
"Wd" in the APRM flow-biased equations is defined as the % Recirculation drive flow, where 100% drive flow is that required to achieve 100% core power and flow. The effective drive flow correction term, AW, corresponds to the difference in percent flow between the TLO and SLO drive flow at the same core flow.
The TLO AW is 0% by definition.
For these setpoint calculations, the SLO AW is 5%.
- 9. A conservative value for the design drift value of +/- 0.5%SP/8.75 days is applied based on the equipment surveillance interval of 7 days plus 25%.
- 10. For the FTs, the Calibration Tools are used two times to calibrate the two FTs. Therefore, the calibration accuracy terms need to be considered for both uses. (Reference 1)
- 11. An spurious trip avoidance (STA) evaluation is not performed for SLO due to the rarity of plant operation in this configuration; thus, the OL is not applicable.
- 12. The current approach in GEH setpoint calculation methodology treats the Drift for this instrument to be a 2 sigma value.
)). This corresponds to a ZSTA = 1.65.
17
NEDO-33753 Revision 0
- 14. For the APRM flow-biased Scrams, the OLs for TLO are set equal to the corresponding TLO setpoints for the APRM flow-biased RBs. This is consistent with GEH setpoint methodology and with ensuring a RB occurs prior to reaching a Scram for the same function. STA evaluations were performed for Scrams, but not for Rod Blocks or permissives per GE setpoint methodology (Reference 1 and Reference 2), such as the APRM Flow-biased RBs.
- 15. Complete inputs are unavailable for the Flow Electronic calibration errors for all Maintenance and Testing Equipment (M&TE) to be used at the plant. Therefore, the Flow Electronics calibration errors are based on using errors that are 10% higher than the errors for assumed calibration tools.
- 16. The FT zero bias error is usually considered to be zero due to the installation and calibration of the differential pressure (dP) transmitter nozzle taps on the Recirculation pipes.
However the installation of the dP transmitter nozzle taps on the Recirculation flow pipe must be evaluated and a PMA bias error included if the low pressure (LP) nozzle is at a higher elevation than the high pressure (HP) nozzle, and this static head dP is not accounted for in the transmitter calibration process. This error is calibrated out, and is considered zero.
- 17. The vendor data uncertainty value is after or during an accident radiation level. In a non-accident condition, the environment in which the transmitter is located will never approach that level, and the transmitter is not required to function after an accident. Therefore, the radiation effect for the FTs does not need to be considered.
- 18. The flow-biased APRM Flow Biased STP-High (Scram) setpoint does not perform a protective function credited in the safety analysis. Therefore, the Seismic Effect for the FTs does not need to be considered.
- 19. [
)) The resulting SLO NTSP would then be 0.63 (Wd - 7.8) + 62.0%.
Because the Setting Adjustment is programmed into the NUMAC equipment to one decimal place, each calculated number is rounded up to one decimal place for conservatism.
This adjustment may be used in the implementation of the new NUMAC equipment.
- 20. The Neutron Monitoring System performs its trip functions before accident temperatures are reached, so temperatures for trip and normal conditions are assumed to be the same.
- 21. The accuracy of the flow electronics is not given in the NUMAC specifications, ((
)) The combined error for the loop flow electronics is + 0.122 mA at 2a.
- 22. For the SLO NTSPs, the results use current GEH setpoint methodology, where a higher SLO error exists because of equipment errors in the idle loop upstream of the flow electronics.
18
NEDO-33753 Revision 0
- 23. The APRM STP RB Clamp NTSP calculated NTSP is 109.0 % RTP, and this number is conservatively used as the OL for the APRM STP Scram Clamp, as it would be more restrictive.
The STA evaluation for the APRM STP Scram Clamp met the STA avoidance criteria with the higher OL. An NTSP value of 108.0 % RTP was conservatively chosen to meet RB operating margin requirements at rated power. This 108.0 % RTP reflects the original overpower design basis for this RB setpoint function, and is consistent with other ARTS-MELLLA projects.
- 24. Each of the SLO NTSP equations are equivalent to each other, but could provide slightly different results because of rounding. Each SLO NTSP equation has been rounded conservatively to one decimal place, that is, further away from the AV.
- 25. Reference 4.1 specifies that 20 LPRMs per APRM channel must be operable. Based on a total of 43 LPRMs, 23 LPRMs per LPRM channel can be bypassed.
19
NEDO-33753 Revision 0
- 5.
REFERENCES
- 1.
GE Nuclear Energy, "General Electric Methodology for Instrumentation Technical Specification and Setpoint Analysis," NEDC-32889P, Revision 3, November 2002.
- 2.
GE Nuclear Energy, "General Electric Instrument Setpoint Methodology," NEDC-31336P-A, dated September 1996.
- 3.
Columbia Generating Station Licensing and related documents:
3.1.
Columbia Generating Station Technical Specifications and Bases, as revised through Amendment 212.
3.2.
Columbia Generating Station Final Safety Analysis Report (FSAR), as revised through Amendment 57, December 2007.
- 4.
Vendor Specifications:
4.1.
GEH 24A5221TC, "PRNM Requirements Specification,"
Data Sheet, Columbia Generating Station, Revision 4, December 7, 2009.
4.2.
GEH 24A5221, "NUMAC Power Range Neutron Monitor (PRNM)," Requirements Specification, Revision 17, July 21, 2008.
4.3.
GEH 25A5916, "NUMAC Average Power Range Monitor (APRM)," Performance Specification, Revision 5, February 28, 2005.
4.4.
Rosemount Reference Manual 00809-0100-4302, Rev. BA, Model 1153 Series B Alphaline Pressure Transmitter, January 2008.
4.5.
GEH 23A5082, "NUMAC Requirements Specification," Design Spec, Revision 1, August 9, 1995.
4.6.
Facsimile from G. Hanson of Rosemount to Daniel Gould of GE, "3-Sigma Compliance,"
February 26, 1999.
20
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION NEDO-33754, Revision 0 Columbia Generating Station Instrument Limits Calculation Rod Block Monitor (NUMAC ARTS-MELLLA)
June 2012 (Non-Proprietary)
ON HITACHI GE Hitachi Nuclear Energy NEDO-33754 Revision 0 DRF Section 0000-0148-3954 RO June 2012 Non Proprietary Information - Class I (Public)
COLUMBIA GENERATING STATION INSTRUMENT LIMITS CALCULATION ROD BLOCK MONITOR (NUMAC ARTS-MELLLA)
Copyright 2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33754 Revision 0 INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33754P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a license amendment request by Energy Northwest, for a power range neutron monitoring system upgrade in proceedings before the U.S. Nuclear Regulatory Commission. The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
Ii
NEDO-33754 Revision 0 Table of Contents A cronym s and A bbreviations.....................................................................................................
iv Executive Sum m ary.........................................................
vi
- 1.
Function: RBM Rod W ithdraw al Blocks........................................................................
1 1.1 RBM Low Pow er Trip Setpoint..................................................................................
3 1.2 RB M Interm ediate Pow er Trip Setpoint......................................................................
3 1.3 RBM H igh Pow er Trip Setpoint..................................................................................
3 1.4 RBM Low Pow er Setpoint............................................................................................
4 1.5 RBM Interm ediate Pow er Setpoint..............................................................................
4 1.6 RBM H igh Pow er Setpoint.........................................................................................
4
- 2.
Com ponents:.........................................................................................................................
5 2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit).............................................
5
- 3.
Sum m ary Results:............................................................................................................
8
- 4.
Com m ents and Recom m endations:..................................................................................
9
- 5.
References:
12 iii
NEDO-33754 Revision 0 Term AL ALT APEA APRM ARTS AV CGS DPEA EMI FS GEH HPSP HTSP IEEE IPSP ITSP LAT LER LP LPRM LPSP LTSP M&TE MELLLA NIST NTSP NUMAC OL P/C PEA ACRONYMS AND ABBREVIATIONS Analytical Limit As Left Tolerance Primary Element Accuracy-Accuracy Error Average Power Range Monitor Average Power Range Monitor, Rod Block Monitor Technical Specification Improvement Program Allowable Value Columbia Generating Station Primary Element Accuracy-Drift Error Electromagnetic Interference Full Scale GE Hitachi Nuclear Energy High Power Setpoint High Power Trip Setpoint Institute of Electrical and Electronics Engineers Intermediate Power Setpoint Intermediate Power Trip Setpoint Leave Alone Tolerance Licensing Event Report Low Pressure Local Power Range Monitor Low Power Setpoint Low Power Trip Setpoint Maintenance and Testing Equipment Maximum Extended Load Line Limit Analysis National Institute of Standards and Technology Nominal Trip Setpoint Nuclear Measurement Analysis and Control Operational Limit Process Computer Primary Element Accuracy iv
NEDO-33754 Revision 0 PMA Process Measurement Accuracy RB Rod Block RFI Radio Frequency Interference RTP Rated Thermal Power SP Calibrated Span STA Spurious Trip Avoidance STP Simulated Thermal Power TS Technical Specifications V
NEDO-33754 Revision 0 EXECUTIVE
SUMMARY
This document is a supplement analysis data sheet to Reference 1. Included in this document in sequential order are:
- The setpoint functions for the system,
- The setpoint function analyses inputs and the source reference of the inputs,
- The devices in the setpoint function instrument loop,
- The component analysis inputs and input sources,
- The calculated results,
- Input comments and result recommendations,
- References.
System: Rod Block Monitor (RBM)
The following setpoint functions are included in this document:
- Low Power Trip Setpoint (LTSP)
- Intermediate Power Trip Setpoint (ITSP)
" High Power Trip Setpoint (HTSP)
- Low Power Setpoint (LPSP)
" Intermediate Power Setpoint (IPSP)
- High Power Setpoint (HPSP) vi
NEDO-33754 Revision 0
- 1. FUNCTION: RBM ROD WITHDRAWAL BLOCKS Setpoint Characteristics:
I)efinition Event Protection:
Limiting event for the setpoint:
Ref. 2, Section 3.19 The RBM is designed to prevent fuel damage Ref. 3 Bases B 3.3.2.1 during a Rod Withdrawal Error (RWE) event during high power operation.
Function After Earthquake El Required Z
Not Required Ref. 2 Section 3.19.2 Ref. 3 Bases B3.3.2.1, Comment 9 Setpoint Direction:
Ref. 3 Bases Section
" Low Power Trip Setpoint 0
Increasing E]
Decreasing 3.3.2.1 (LTSP)
Z Increasing El Decreasing
" Intermediate Power Trip Setpoint (ITSP)
Z Increasing E
Decreasing
" High Power Trip Setpoint (HTSP)
Z Increasing El Decreasing
" Low Power Setpoint (LPSP)
Z Increasing E]
Decreasing
" Intermediate Power Setpoint Z
Increasing El Decreasing (IPSP)
" High Power Setpoint (HPSP)
Single or Multiple Channel Z
Single El Multiple Ref. 3 Bases Section 3.3.2.1, Ref. 4.2 Section 4.1.6 LER Calculation Basis if Multiple Standard (Conservative) LER Calculation 0, or Ref. 1, Ref. 2 Channel Configuration Specific LER Calculation L
Trip Logic for Configuration n/a Specific LER Calculation Plant Data:
\\
Sigma Ithnio**2R Rference(s)
Power Primary Element (LPRM Detector) (% Power)
APEAAccu..cy
+ 1%; bias 0.49%
APEApowersupplyEffect negligible Ref. 2, Comment 6 DPEA Trip Setpoints negligible Power Setpoints
+/- 0.2% / 7 days; bias 0.33% / 7 days I
NEDO-33754 Revision 0 1.
FUNCTION: RBM ROD WITHDRAWAL BLOCKS (CONT'D)
Plant Data:
F Value KofSigmn o2if oReference(s)
Power Process Measurement Accuracy (PMA)
" Tracking - Trip Setpoints
+ 1%
3
" Tracking - Power Setpoints
+/- 1.11%
" Noise - Trip Setpoints
+/- 2.0%
Noise-Power Setpoints 0.0%
Components (or Devices) in Setpoint Function Instrument Loop:
" LPRM Detector
NEDO-33754 Revision 0 1.1 RBM Low Power Trip Setpoint Current Function Limits:
Vali c/Equa#tion; Referen. (s)
Present Value/Equation
(% RTP)
ARTS-MELLLA Condition
(% Reference Level) unfiltered filtered Analytical Limit 0.58 Wd+ 3 8 127.0 125.8 Technical Specification (TS) 0.58 Wd+ 35.0 Results provided in Allowable Value Section 3 Nominal Trip Setpoint 0.58 Wd+ 32.0 Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 1.2 RBM Intermediate Power Trip Setpoint Current Function Limits:
Valu.'/Equaation Rt i
Reree(
Present ARTS-MELLLA Value/Equation Condition
(% RTP)
(% Reference Level) unfiltered filtered Analytical Limit 0.58 Wd+ 4 6 122.0 121.0 TS Allowable Value 0.58 W, + 43.0 Results provided in Section 3 Nominal Trip Setpoint 0.58 Wd+ 40.0 Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 1.3 RBM High Power Trip Setpoint Current Function Limits:
V
%Yniue/Equation Ref.
i*erenice(s)
Present ARTS-MELLLA Value/Equation Condition
(% RTP)
(% Reference Level) unfiltered filtered Analytical Limit 0.58 Wd+ 54 117.0 116.0 TS Allowable Value 0.58 Wd+ 51.0 Results provided in Section 3 Nominal Trip Setpoint 0.58 Wd+ 48 Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 3
NEDO-33754 Revision 0 1.4 RBM Low Power Setpoint Current Function Limits: I K:
Vlalue/Equlation Reference(s)
III II III II I I Present Value/Equation
(% RTP)
ARTS-MELLLA Condition
(% RTP) unfiltered filtered Analytical Limit n/a 30 30 TS Allowable Value n/a Results provided in Section 3 Nominal Trip Setpoint n/a Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 1.5 RBM Intermediate Power Setpoint Current Function Limits:
K Valgue/quation Reference(s)
Present ARTS-MELLLA Value/Equation Condition
(% RTP)
(% RTP) unfiltered filtered Analytical Limit n/a 65 65 TS Allowable Value n/a Results provided in Section 3 Nominal Trip Setpoint n/a Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 1.6 RBM High Power Setpoint Current Function Limits:
Value*Equation
- j.
Referre'nce(s)
! 7K Present ARTS-MELLLA Value/Equation Condition
(% RTP)
(% RTP) unfiltered filtered Analytical Limit n/a 85 85 TS Allowable Value n/a Results provided in Section 3 Nominal Trip Setpoint n/a Results provided in Section 3 Operational Limit n/a n/a Ref. 1, Ref. 2, Comment 3 4
NEDO-33754 Revision 0
- 2. COMPONENTS:
2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit)
Comnonent Information:
VaIuetEouatioiP~
Reference(s)
Plant Instrument ID No.
Undefined Comment 2 Instrument vendor GE / Reuter-Stokes Ref. 4.1 Model ID No. (including Range NUMAC Ref. 4.1 Code)
Plant Location(s)
Control Bldg Ref. 4.1 Section 4.2.1 and Appendix C Process Element LPRMs: NA250/NA300 Ref. 4.2 Sections 1.5 and 3.2 Inputs:
Vendor Specifications Value I Eqation Sigmaif~niot 2!
Reference(s)ý Top of Scale FS = 125%
n/a Ref. 4.2 Sections 4.3.2 and 4.7.2 Bottom of Scale 0%
n/a Ref. 4.2 Sections 4.3.2 and 4.7.2 Upper Range Limit n/a n/a Ref. 4.2 Sections 4.3.2 and 4.7.2 Accuracy
" LPRM Detector See Section 1 Ref. I & Ref. 2
" LPRM Electronics
_ 0.943% (% local power)
Temperature Effect included in accuracy Seismic Effect included in accuracy Ref. 4.4 Section 4.1.1, Comment 4 Radiation Effect included in accuracy Ref. 4.1 Section 5.2, Comment 4 Humidity Effect included in accuracy Ref 4.1 Section 5.2, Comment 4 Power Supply Effect (Detector)
See Section 1 RFI/EMI Effect included in accuracy Ref. 4.4 Sections 4.1.1, and 4.2.5, Comment 4 Insulation Resistance Effect Negligible Comment 4 Over-pressure Effect n/a Comment 5 Static Pressure Effect n/a Comment 5 5
NEDO-33754 Revision 0 2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit) (cont'd)
Plant Data:
IValue*#,,,
I I Referwiccts)
Calibration Temp Range 70 to 104 OF Comment 15 Normal Temperature Range 40 to 104 OF Trip Temp Range 40 to 104 OF Comment 16 Humidity Operating Range 10 to 60% RH Plant Radiation value n/a Plant seismic value 0.7g Comment 9 Power Supply Variation value Negligible Comment 4 RFI/EMI value n/a Comment 4 Over-pressure value n/a Comment 5 Static Pressure value n/a Comment 5 Drift:
aluAI
/
Sigmaif not 2i Refeeinic(*s)>,:
Current Calib. Interval 7 days ElIncludes extra Ref. 3 Table 3.3.1.1-1 25%
SR 3.3.1.1.2 Desired Calib. Interval 7 days E Includes extra Ref. 3 Table 3.3.1.1-1 25%
SR 3.3.1.1.3 Drift Source
[Vendor
[Calculated Ref. 1, Ref. 2 Trip Setpts Power Setpts Drift Value (Trip Setpoints)
+/- 0.3% FS / 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ref. 4.2 Section
(% RBM power) 4.7.2.9, Comment 8 Drift Value (Power Setpoints)
+/-0.5% FS / 700
+ 0.5% SP / 8.75 Ref. 4.3 Section
(% power) hours days 4.3.3.3.5, Comment 14 6
NEDO-33754 Revision 0 2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit) (cont'd)
Calibration:
Value Legtfltion I
[Sgaiit37~Rfi~~)
Included in APRM calibration As Left Tolerance Trip setpoints: 0 Power setpoints: AGAF Comment 7 Leave Alone Tolerance Trip setpoints: = ALT Comment 7 Power setpoints: = ALT Input Calibration Tool:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Input Calibration Standard:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Tool:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard:
n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Application Specific Input:
Value Sigma if not 2 Reference(s)
Minimum no. of LPRMs per RBM 4 of 8 Ref. 4.2 Section Channel (Trip Setpoints) 4.7.9.4.2, 4.8.2 Minimum no. of LPRMs per Ref. 4.1 Section APRM Channel (Power Setpoints) 20 of 43 4.1.5, and Section 3.1.1.
Comment 13 APRM Gain Adjustment Factor
+/- 2% RTP 3
(AGAF)
I I
7
NEDO-33754 Revision 0
- 3.
SUMMARY
RESULTS:
Calculated Values Setpoint Function I
Meets N
Meets Analytic Limnit Allowable Value Nominal Trip LER
'Spurious (from Section t)(%RTP)
Setpoint Avoid-Trip (0%
RT P)
(/oWJP) >
anc2 Avoidanice.
~Criteria' Criteria Unfiltered Filtered Unfiltered Filtered Unfiltered Filtered Low Power Setpoint 30 30 28.0 28.0 26.0 26.0 Y
n/a (LPSP)
Intermediate Power 65 65 63.0 63.0 61.0 61.0 Y
n/a Setpoint (IPSP)
High Power Setpoint 85 85 83.0 83.0 81.0 81.0 Y
n/a (HPSP)
Mleets Meects Analytic Limit Allowvablc Výalue>
0 Nomina Trip LER Sphriouý Setpoiat Function'>
(from Section 1)
(% Reference Level)
Setpo mt
"'Avoid-I'Trip
(%,' Referenice Level)
(%Reference Level) ance Avoid1ance, Unfiltered Filtered Unfiltered Filtered Unfiltered Filtered Low Power Trip 127.0 125.8 124.6 123.4 124.2 123.0 Y
n/a Setpoint (LTSP)
Intermediate Power 122.0 121.0 119.6 118.6 119.2 118.2 Y
n/a Trip Setpoint (ITSP)
I I
I High Power Trip 117.0 116.0 114.6 113.6 114.2 113.2 Y
n/a Setpoint (HTSP)
I Application Specific Setpoint Adiustments 8
NEDO-33754 Revision 0
- 4. COMMENTS AND RECOMMENDATIONS:
- 1. Unless specifically identified as "bias" errors in this document, all instrument uncertainty errors will be considered to be random in nature, even when the "+/-" symbol is not shown.
- 2. Some plant specific information has not been provided or is not currently available in the current plant setpoint document, but is considered unnecessary because the effects of this information are included within the instrument accuracy values or are not necessary for setpoint evaluation.
- 3. Spurious trip avoidance (STA) evaluations are not performed for rod blocks or permissives per GEH setpoint methodology (Reference 1 and Reference 2), such as the RBM Rod Blocks. Therefore, the Operational Limits are not applicable.
- 4. Seismic effect, radiation effect, humidity effect, power supply effect, Radio Frequency Interference/ Electromagnetic Interference (RFI/EMI) effect, and insulation resistance effect errors are marked "negligible" or "included in accuracy" and are considered to have negligible impact on the manufacturer's accuracy terms when they are not identified separately.
- 5. Per Reference 1 and Reference 2, overpressure effects are only applicable to pressure measurement devices (e.g., differential pressure transmitters), and static pressure effects are only applicable to differential pressure measurement devices.
These effects are marked "n/a" for other devices.
- 6. ((
)) (Reference 2 Section 4.5.3)
- 7. The APRM subsystem is calibrated on-line weekly (Reference 3, SR 3.3.1.1) using the AGAF process, where the gain of the APRMs is adjusted to read the Core Thermal Power (CTP) determined by the Process Computer (P/C), within a specified As Left Tolerance. ((
)) Thus, the only calibration error to consider for the APRM electronics sub-loop is the As Left Tolerance specified by the AGAF process.
- 8. The Power Electronics Drift for the RBM Trip setpoints uses the 4-hour drift error specification. The only drift error would be the drift in the several hours after control rod selection and nulling, and before the control rod is motion. This is estimated to be a few hours, so the 4-hour drift interval is used.
9
NEDO-33754 Revision 0
- 9. The RBM Rod Block limits control rod withdrawal if localized neutron flux exceeds a pre-determined setpoint during control rod manipulations.
However, the RBM system is not essential for the safety of the plant.
Hence, the RBM rod withdrawal block setpoint does not perform a protective function. Therefore, the Seismic Effect for the RBM does not need to be considered.
- 10. As described in the Technical Specifications (Reference 3 Section 3.3.2.1), the LPSP is considered as an automatic "enable" feature when thermal power is above the LPSP, and the AV and NTSP are calculated accordingly.
The enable feature occurs as Reactor power increases past the LPSP.
The vendor documents for the RBM equipment treat the LPSP as an automatic "bypass" feature (Reference 4.2, Section 4.8.2.4) when below the LPSP.
The bypass feature occurs as Reactor Power decreases below the LPSP.
These two descriptions are not interchangeable/equivalent; there is a need in the equipment logic for an instrument setting "deadband".
Therefore, the equipment instrument setting for the LPSP NTSP must include the 1.1% Rated Thermal power deadband (i.e., hysteresis of 1.0% and an accuracy of 0.1%).
The deadband does not apply to the AV. The equipment instrument setting is equal to the NTSP for the other RBM setpoint functions.
Choice of this setpoint is an operational issue to be decided by the plant.
There is no AL for this setpoint. A value of 95% is recommended, but it can be lowered if operational problems are encountered.
- 12. Per Reference 1 and Reference 2, the difference between the AL and AV and the difference between the AL and NTSP are independent of the number for the AL.
This applies for all of the Power and Trip setpoint functions.
- 13. Reference 4.1 specifies that up to 23 LPRMs per APRM channel can be bypassed. Based on a total of 43 LPRMs, this is the basis for a minimum of 20 LPRMs per LPRM channel.
- 14. A conservative value for the design drift value of 4 0.5%SP/8.75 days is applied based on the equipment surveillance interval of 7 days plus 25%.
- 15. Calibration temperature range is conservatively chosen to be between 70'F and 104'F.
Energy Northwest's setpoint calculation provided a calibration temperature of 70°F; a max temperature of 104'F, which corresponds to the maximum normal temperature is assumed.
- 16. The Trip temperature range was chosen to be between 40°F to 104 0F, which is equal to the normal temperature range. This is because the RBM is used for transient states, and not for accident trips. The temperature range is expected to be normal when the trip is required.
- 17. Transfer functions used in this calculation:
10
NEDO-33754 Revision 0 RBM Power Electronics:
APRM Power Electronics:
Output is proportional to the average of the inputs, and multiplied by a gain adjustment, calculated relative to a constant arbitrary reference equivalent to 100%
RTP.
Output is proportional to the average of the inputs.
11
NEDO-33754 Revision 0
- 5.
REFERENCES:
- 1. GE Nuclear Energy, "General Electric Methodology for Instrumentation Technical Specification and Setpoint Analysis," NEDC-32889P, Revision 3, November 2002.
- 2. GE Nuclear
- Energy, "General Electric Instrument Setpoint Methodology,"
NEDC-31336P-A, September 1996.
- 3. Columbia Generating Station Technical Specifications and Bases, as revised through Amendment 212.
- 4. Vendor Specifications:
4.1. GE 24A5221TC, "PRNM Requirements Specification," Data Sheet, Columbia Generating Station, Revision 4, December 7, 2009.
4.2. GE 24A5221, "NUMAC Power Range Neutron Monitor (PRNM)," Requirements Specification, Revision 17, July 21, 2008.
4.3. GE 25A5916, "NIUMAC Average Power Range Monitor (APRM)," Performance Specification, Revision 5, February 28, 2005.
4.4. GE
- 23A5082, "NUMAC Requirements Specification,"
Design Specification, Revision 1, August 9, 1995.
12
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM /
ARTS / MELLLA IMPLEMENTATION 0 NEDO-33755, Revision 0 Columbia Generating Station Power Range Neutron Monitoring System Software Tools Summary Report June 2012 (Non-Proprietary)
4 HITACHI GE Hitachi Nuclear Energy NEDO-33755 Revision 0 DRF Section 0000-0145-5270 RI June 2012 Non-Proprietary Information - Class I (Public)
COLUMBIA GENERATING STATION POWER RANGE NEUTRON MONITORING SYSTEM SOFTWARE TOOLS
SUMMARY
REPORT Copyright 2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33755 Revision 0 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a license amendment request by Energy Northwest for a power range neutron monitoring system upgrade in proceedings before the U.S. Nuclear Regulatory Commission.
The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GE Hitachi Nuclear Energy (GEH) makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
ii
NEDO-33755 Revision 0 TABLE OF CONTENTS A CRON YM S AN D ABBREV IA TION S..............................................................................................
iv
- 1. Introduction............................................................................................................................................
1
- 2. Tool Identification.................................................................................................................................
1
- 3. Application............................................................................................................................................
2
- 4. Tools D escription...................................................................................................................................
2
- 5. Sum m ary Report Conclusion.........................................................................................................
4
- 6. References..............................................................................................................................................
4 TABLE OF TABLES Table 1 G EH I& C Softw are D evelopm ent Softw are Tool Reports.........................................................
3 111io
NEDO-33755 Revision 0 ACRONYMS AND ABBREVIATIONS ASP Automatic Signal Processor CGS Columbia Generating Station COTS Commercial Off the Shelf CPU Central Processing Unit DI&C Digital Instrumentation and Control DSP Digital Signal Processor eDRF Electronic Design Record File GEH GE Hitachi Nuclear Energy I&C Instrumentation and Controls ICE In-Circuit Emulator IEEE Institute of Electrical and Electronics Engineers ISG Interim Staff Guidance NRC Nuclear Regulatory Commission NUMAC Nuclear Measurement Analysis and Control PDMS Product Data Management System PDS Previously Developed Software PL/M or PLM Programming Language for Microcomputers PRNM Power Range Neutron Monitor SCMP Software Configuration Management Plan VAX Virtual Address eXtension VMS Virtual Memory System iv
NEDO-33755 Revision 0
- 1. INTRODUCTION This Software Tools Summary Report identifies the target platforms, purpose, acceptance criteria, issues, methods, and results of third party Commercial Off the Shelf (COTS) tools used for software development and debugging on Columbia Generating Station (CGS) Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitor (PRNM) safety and non-safety classified software applications.
This summary defines the acceptance criteria and conclusions for tools used in the software development and debugging of CGS NUMAC PRINM software applications to evaluate and identify COTS products.
The acceptance criteria, methods used for the evaluation, and the results and conclusions are described within this report, as required per Institute of Electrical and Electronics Engineers (IEEE) Standard 7-4.3.2 (Reference 1), Section 5.3.2 and Digital Instrumentation and Control (DI&C)-Interim Staff Guidance (ISG)-06 (Reference 2), Section D. 10.4.2.3.2.
The approved tool reports (Table 1) provide assurance that the necessary features of the software tools are adequate for their intended use for both safety and non-safety classified CGS NUMAC PRNM software applications.
- 2. TOOL IDENTIFICATION The tools evaluated by this report are as follows:
- 1. Intel In-Circuit Emulator (ICE-386SX) a) Intel ICE-386SX Emulator Revision 1.0 b) ICE-376 Software Revision 1.0 (Referred collectively as the Intel ICE-386SX)
- 2. Stability Automatic Signal Processor (ASP) Developmental Tools a) Motorola Digital Signal Processor (DSP)56000 Simulator, Version 6.30 b) Motorola DSP56000 Optimizing C Compiler/Assembler, C Compiler Version 1.29 GNU 1.37.1, and Assembler Version 6.30
- 3. iSystem Z80180 Central Processing Unit (CPU) Emulation Tools a) iSystem iC1000 Power Emulator, V09.01 b) iSystem Z180 Power POD, Revision C c) winIDEA 2011 Integrated Development Environment, Build 9.11.82 2/28/2012
- 4. Intel Programming Language for Microcomputers (PLM) and C Software Tools a) Intel Virtual Address eXtension (VAX)/Virtual Memory System (VMS) iC-386 Compiler, V4.5 1
NEDO-33755 Revision 0 b) Intel VAX/VMS PL/M-386 Compiler, V3.4 c) Intel VAX/VMS 386TM Macro Assembler, V4.0 d) Intel VAXiVMS 386TM Binder, Vi.5VX e) Intel VAX/VMS 386TM System Builder, Vi.6VX f) Intel VAX/VMS 386TM Mapper, V1.3VX g) Intel 386TM Object to Hex (OH386) Converter, VI.1 h) VAX/VMS Checksum / Prom Drawings Program CHKSUM, Revision 5.3
- 5. HP64000 PASCAL Compiler, Assembler, and Linker a) HP Model 64823 Z80/NSC800 PASCAL Compiler b) HP Model 64864A/AR Version 1.01 Assembler c) HP Model 64864A/AR Version 1.01 Linker
- 3.
APPLICATION All verification tests were conducted in a controlled environment inside the Services Instrumentation and Controls (I&C) engineering department at the GE Hitachi Nuclear Energy (GEH) facilities in Wilmington, North Carolina.
- 4. TOOLS DESCRIPTION The tools identified in this report are controlled under the GEH Software Configuration Management Plan (SCMP, Reference 3) and the storage location of each tool is specifically stated within its respective tool report, as identified in Table 1. The HP64000 PASCAL Compiler, Assembler, and Linker is a stand-alone non-PC based tool and is archived via means of physical media (optical disk backup) and stored in the secured Services I&C software development lab.
Table 1 identifies each tool report relative to all individual software development and debugging tools evaluated for the CGS PRNM software applications. Each tool report is archived in eMatrix or the GEH Product Data Management System (PDMS) and is identified by title in Table 1.
Each tool report contains the following detailed description for every tool evaluated:
" Electronic Design Record File (eDRF) Section Identification
- Tool Location
- Description
- Application 2
NEDO-33755 Revision 0
- Known Issues Safety Application Classification
- Evaluation Methods
- Evaluation Results
- Conclusions The following GEH I&C software development software tool reports are available for Nuclear Regulatory Commission (NRC) review:
Table 1 GEH I&C Software Development Software Tool Reports Intel In-Circuit Emulator (ICE-386SX) Tool Intel ICE-386SX Emulator Revision 1.0 ICE-376 Software Revision 1.0 (Referred collectively as the Intel ICE-386SX) 0 Motorola DSP56000 Simulator, Version 6.30 Stability ASP Developmental Tools 0
Motorola DSP56000 Optimizing C Compiler/Assembler, C Compiler Version 1.29 GNU 1.37.1, and Assembler Version 6.30 iSystem iC 1000 Power Emulator, V09.01 iSystem Z80180 CPU Emulation Tools 0
iSystem Z180 Power POD, Revision C winIDEA 2011 Integrated Development Environment, Build 9.11.82 2/28/2012 Intel VAX/VMS iC-386 Compiler, V4.5 Intel VAX/VMS PL/M-386 Compiler, V3.4 Intel VAX/VMS 3 8 6 TM Macro Assembler, V4.0 Intel VAX/VMS 38 6 TM Binder, V1.5VX Intel PLM and C Software Tools 0
Intel VAX/VMS 3 86 TM System Builder, V1.6VX 0
Intel VAX/VMS 3 86 TM Mapper, V1.3VX Intel 3 8 6TM Object to Hex (OH386) Converter, VI.A VAX/VMS Checksum / Prom Drawings Program
- CHKSUM, Revision 5.3 HP Model 64823 Z80/NSC800 PASCAL Compiler HP 64000 PASCAL Compiler, Assembler, 0
HP Model 64864A/AR Version 1.01 Assembler and Linker 0
HP Model 64864A/AR Version 1.01 Linker 3
NEDO-33755 Revision 0
- 5.
SUMMARY
REPORT CONCLUSION All tools identified in Section 2 of this report are acceptable for use in any CGS NUMAC PRNM software development project, previously developed software (PDS) or new, safety or non-safety software application. The intended functionality and limitations of applicability for all software tools are documented within their respective tool reports.
It has been concluded from review of all of the software tool reports, issues, and their conclusions that all tools can be successfully used for software development and debugging on all CGS NUMAC PNRM software development projects to the safety level in which they were approved.
- 6. REFERENCES
- 1.
IEEE Standard 7-4.3.2, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations," 2003.
- 2.
DI&C-ISG-06, "Task Working Group #6: Licensing Process," Revision 1, January 19, 2011 (ADAMS Accession No. ML110140103).
- 3.
"Software Configuration Management Plan," 23A5161, Revision 4.
4
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION 1 NEDO-33758, Revision 0 Columbia Generating Station Power Range Neutron Monitoring System Response Time Confirmation Report June 2012 (Non-Proprietary)
0ý HITACHI GE Hitachi Nuclear Energy NEDO-33758 Revision 0 DRF Section 0000-0148-5422 RI June 2012 Non Proprietary Information - Class I (Public)
COLUMBIA GENERATING STATION POWER RANGE NEUTRON MONITORING SYSTEM RESPONSE TIME CONFIRMATION REPORT Copyright 2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33758 Revision 0 PROPRIETARY INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33758P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
)).
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a license amendment request by Energy Northwest for a power range neutron monitoring system upgrade in proceedings before the U.S. Nuclear Regulatory Commission. The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
ii
NEDO-33758 Revision 0 TABLE OF CONTENTS
- 1.
Introduction.............................................................................................................................
1
- 2.
H igh Flux Trip Test Results................................................................................................
1
- 3.
D ata Error Rate Test Results..............................................................................................
2
- 4.
Test Anom aly/Observation and D isposition......................................................................
2
- 5.
Conclusion...............................................................................................................................
2
- 6.
Applicable D ocum ents............................................................................................................
2 TABLE OF TABLES Table 1 Safety Function Response Tim es.......................................................................................
1 iii
NEDO-33758 Revision 0 Acronyms and Abbreviations APRM Average Power Range Monitor BTP Branch Technical Position CGS Columbia Generating Station DI&C Digital Instrumentation and Controls FDDI Fiber Direct Data Interface GGNS Grand Gulf Nuclear Station ISG Interim Staff Guidance LPRM Local Power Range Monitor NUMAC Nuclear Measurement Analysis and Control OPRM Oscillation Power Range Monitor PRNMS Power Range Neutron Monitoring System STP Simulated Thermal Power V&V Validation and Verification iv
NEDO-33758 Revision 0
- 1.
Introduction This report evaluates the Response Time of the Columbia Generating Station (CGS) Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitoring System (PRNMS) versus the safety analysis requirements and standard criteria for digital instrumentation and controls as per (Reference 1). This evaluation demonstrates compliance with the criteria of Branch Technical Position (BTP) 7-21 (Reference 2) and Staff Positions 1.19 and 1.20 of Digital Instrumentation and Controls (DI&C)-Interim Staff Guidance (ISG)-04 (Reference 3).
- 2.
High Flux Trip Test Results Tests were performed during PRNMS Validation and Verification (V&V) testing to confirm the CGS PRNMS configuration meets the response time requirement. All of the High Flux Trips follow the same logic path with the addition of the six second simulated thermal power (STP) filtering constant in the STP High Flux Trip path. Therefore only one test is needed to verify the High Flux Trip response times.
Testing was performed on production (non-development) equipment manufactured in accordance with the CGS design documentation.
The calculated and actual PRNMS response times presented in Table 1 meet the requirement of a response time analysis report as stated in Section D.9.4.2.4 of DI&C-ISG-06 (Reference 4).
Table 1 Safety Function Response Times I
RM Response PRNM CalcuIatedt PR.NM Actuali
~PRN1VI Safety Function Time Requirement~
Response Timie~
.Response Timie
~
(rSec)
>(mSec)
[mSec)
APRM Neutron Flux -
40 High Trip APRM STP - High Trip 40 APRM Neutron Flux -
40 High (Setdown) Trip OPRM Instability Detect-400 and-Suppress Trip I
NEDO-33758 Revision 0
- 3.
Data Error Rate Test Results Data error rate testing was performed on a similar PRNM system for Grand Gulf Nuclear Station (GGNS) during integration testing. The GGNS testing is considered applicable to CGS because the communication links from the Local Power Range Monitor (LPRM) to the Average Power Range Monitor (APRM) and from the APRM to the 2-Out-Of-4 Logic module are identical for the two systems. Therefore, the data error rates observed for the GGNS communication paths will be representative of the rates which would be observed for the CGS system. Data error rate testing monitors the number of errors on the Fiber Direct Data Interface (FDDI) link from the LPRM instrument to the APRM instrument and on the broadcaster link from the APRM instrument to the 2-Out-Of-4 Logic Module. The tests were performed for a sufficient time period to conclude that the actual data error rate is lower than the established data error rate used for the safety system response time calculations.
The communication link that supports the trip response time is a fixed message size irrespective of the application software that uses it and because the error data rate analysis depends only on the data message size and the expected bit error rate, the testing and analysis that was done for GGNS is applicable to CGS.
Data error rate testing of the GGNS PRNM software was performed and passed with no anomalies.
- 4.
Test Anomaly/Observation and Disposition No anomalies, observations, or issues were identified by the tester during testing.
- 5.
Conclusion This report confirms the evaluation of the response time of the CGS PRNMS versus the safety analysis requirements and standard criteria for DI&C. This confirmation demonstrates compliance with the criteria of References 2 and 3.
- 6.
Applicable Documents
- 1.
GE Hitachi Nuclear Energy, "Columbia Power Range Neutron Monitoring System Response Time Analysis Report," NEDC-33690P, Revision 0, November 2011 (ADAMS Accession No. ML12040A75).
- 2.
Standard Review Plan, BTP 7-21, "Guidance on Digital Computer Real-Time Performance," Revision 5, March 2007 (ADAMS Accession No. ML070550070).
- 3.
DI&C-ISG-04, "Task Working Group
- 4:
Highly-Integrated Control Rooms-Communications Issues," Revision 1, dated March 6, 2009 (ADAMS Accesssion No. ML083310185).
- 4.
DI&C-ISG-06, "Task Working Group #6: Licensing Process," Revision 1, dated January 19, 2011 (ADAMS Accesssion No. ML110140103).
2
Proprietary - Withhold under 10 CFR 2.390 SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM /
ARTS / MELLLA IMPLEMENTATION 2 GE-MS-CT-106244-JC 14 CGS DI&C-ISG-06 Enclosure B, Phase 2 Items 2.2, 2.3, and 2.9 June 12, 2012
Enclosures:
DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station - (Proprietary)
DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station - (Non-Proprietary) - Affidavit
0 HITACHI Proprietary Notice This letter transmits proprietary information in accordance with 10 CFR 2.390.
Upon the removal of Enclosure 1, the balance of the letter may be considered non-proprietary.
GE Hitachi Nuclear Energy Jamie Creech Project Manager - Controls 3901 Castle Hayne Road P.O. Box 780 Wilmington, NC 28402 USA T (910) 819-4760 F (910) 341-2824 Ejames.creech@GE.com Date: June 12, 2012 GE-MS-CT-106244-JC14 Response Required? Yes D] No Z Response Requested by: N/A Contains Engineering Requirements/Design Inputs? Yes Z No E]
If Yes, Requirements/Design Inputs Verified?
Yes Z No E]i If Yes, Design Record File: 0000-0148-9680 Mr. James Snyder CGS - Energy Northwest Mail Drop PE29 PO Box 968 Richland, WA 99352-0968
Subject:
Reference:
CGS DI&C-ISG-06 Enclosure B, Phase 2 Items 2.2, 2.3, and 2.9
- 1) ENW Contract 328791 dated May 4, 2009
- 2) ENW Contract 328791 Amendment 1, May 15, 2009
- 3) ENW Purchase Order 329043 dated May 19, 2009
Dear Mr. Snyder:
This letter provides the following DI&C-ISG-06 Enclosure B deliverables in support of Columbia Generating Station's Nuclear Measurement Control and Analysis Power Range Neutron Monitor (NUMAC PRNM) upgrade:
DI&C-ISG-06 Enclosure B Item Title 2.2 Verification & Validation Reports (D 4.4.2.2) 2.3 As-Manufactured, System Configuration Documentation (D 4.4.2.3) 2.9 System Build Documents (D 4.4.3.5)
June 12, 2012 GE-MS-CT-106244-JC14 Page 2 If you have any questions concerning this transmittal, please contact me at your earliest convenience.
Sincerely yours, Jamie Creech
Enclosures:
- 1. DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station, GEH Proprietary Information-Class III (Confidential)
- 2. DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station, Non-Proprietary Information-Class I (Public)
- 3. Affidavit
ENCLOSURE 2 GE-MS-CT-106244-JC 14 DI&C-ISG-06 Phase 2 Items 2.2, 2.3, and 2.9 for Columbia Generating Station Non-Proprietary - Class I (Public)
NON-PROPRIETARY NOTICE This is a non-proprietary version of the Enclosure 1 of GE-MS-CT-106244-JC14 which has the proprietary information removed.
Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
I].
of GE-MS-CT-106244-JC 14 Page 2 of 5 In support of Columbia Generating Station's Nuclear Measurement Control and Analysis Power Range Neutron Monitor (NUMAC PRNM) upgrade, the following DI&C-ISG-06 Enclosure B deliverables are addressed:
2.2 Verification & Validation (V&V) Reports (D 4.4.2.2) 2.3 As-Manufactured, System Configuration Documentation (D 4.4.2.3) 2.9 System Build Documents (D 4.4.3.5)
The following information was previously provided to the NRC as part of a response to Grand Gulf Nuclear Station (GGNS) RAI #1 within Entergy Letter, "Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531)," GNRO-2011/000039, dated May 26, 2011 (ADAMS Accession No. ML111460590).
V&V Analysis and Reports (DI&C ISG-06 D.4.4.2.2)
((
of GE-MS-CT-106244-JC 14 Page 3 of 5 The V&V records for all baseline configuration items, as well as the baseline review records that show that verification tasks were successfully accomplished at each design phase in the life cycle, are maintained in the Product Data Management System (PDMS) where they are available for review by the NRC staff at the GEH office.
Configuration Management Activities (DI&C ISG-06 D.4.4.2.3)
The Product Data Management System is the primary configuration management tool for all engineering controlled documentation, including software for NUMAC products.
The PDMS provides unique identification of each configurable item by document identification number, title, and revision. ((
of GE-MS-CT-106244-JC 14 Page 4 of 5
)) Revision history of all baseline configuration items is tracked and reported by the PDMS.
Er I]
The configuration management records for all baseline configuration items, as well as the baseline review records that establish and document the configuration at each design phase in the life cycle, are maintained in the PDMS where they are available for review by the NRC staff at the GEH office.
System Build Documents (DI&C ISG-06 D.4.4.3.5)
Er of GE-MS-CT-106244-JC14 Page 5 of 5 The firmware release descriptions and firmware drawings are maintained in the PDMS where they are available for review by the NRC staff at the GEH office.
SUBMITTAL OF PHASE 2 INFORMATION IN SUPPORT OF LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS IN SUPPORT OF PRNM I ARTS / MELLLA IMPLEMENTATION 4 NEDO-33696, Revision 1 Columbia Generating Station Power Range Neutron Monitoring System Architecture & Theory of Operations Report July 2012 (Non-Proprietary)
(
HITACHI GE Hitachi Nuclear Energy NEDO-33696 Revision 1 DRF Section 0000-0139-4769 R2 July 2012 Non-Proprietary Information - Class I (Public)
Columbia Generating Station Power Range Neutron Monitoring System Architecture & Theory of Operations Report Copyright 2011-2012 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
NEDO-33696 Revision 1 INFORMATION NOTICE This is the non-proprietary version of the document NEDC-33696P, Revision 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
IMPORTANT NOTICE REGARDING THE CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document is furnished for the purpose of and analysis of previously developed software for the Nuclear Measurement Analysis and Control Power Range Neutron Monitoring (NUMAC PRNM) System and to demonstrate adequacy for use in the Columbia Generating Station PRNM application. The only undertakings of GEH with respect to information in this document are contained in the contract between Energy Northwest and GEH, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than Energy Northwest, or for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
11
NEDO-33696 Revision 1 Revision Summary Revision No.
Content 0
N/A Added proprietary markings to NEDC-33696P and created public version of NEDC-33696P (NEDO-33696).
iii
NEDO-33696 Revision 1 Table of Contents
- 1. Introduction..............................................................................................................................
1 1.1.
Purpose and Scope...................................................................................................
1 1.2.
System Architecture...............................................................................................
2 1.3.
Theory of Operations.............................................................................................
2 1.4.
Report Structure & Content.................................................................................
3
- 2. NUMAC Products Versus Digital I&C Platforms...........................................................
4 2.1.
Intended Purpose and Design Approach Comparison........................................ 4 2.2.
NUMAC Standard Components Versus Standard Platform Modules.............. 5 2.3.
Summary Conclusion.............................................................................................
6
- 3. NUMAC PRNM System Overview....................................................................................
7 3.1.
PRNM System Functions.......................................................................................
7 3.2.
PRNM System Interfaces......................................................................................
10 3.3.
PRNM System-Level Architecture.......................................................................
12
- 4. PRNM Sub-System Architecture Overview..................................................................
13 4.1.
NUMAC Interface Computer (Non-Safety-Related)........................................
13 4.1.1. NIC Overview Description.........................................................................
13 4.1.2. N IC Interfaces.............................................................................................
14 4.1.3. NIC Computer Layout................................................................................
14 4.2.
Rod Block Monitor (Non-Safety-Related).........................................................
15 4.2.1. RBM Overview Description.........................................................................
15 4.2.2. R BM Interfaces..........................................................................................
15 4.2.3. RBM Instrument Layout Diagram.............................................................
17 4.3.
APRM/LPRM (Safety-Related)...........................................................................
17 4.3.1. APRM/ LPRM Overview Description.......................................................
17 4.3.2. APRM/LPRM Interfaces...........................................................................
18 4.3.3. APRM/LPRMBlock Diagram...................................................................
18 4.3.4. APRM/LPRM Instrument Layout Diagram................................................ 20 4.4.
Two Out of Four Logic Module (Safety-Related)...............................................
20 4.5.
NUMAC Display Units..........................................................................................
21
- 5. APRM/LPRM.........................................................................................................................
22 5.1.
Functional CPU Module Software Architecture...............................................
23 5.2.
APRM Trip Signal Path.......................................................................................
26 5.2.1. 5-Channel LPRM Module...........................................................................
27 iv
NEDO-33696 Revision 1 5.2.2. Automatic Signal Processor (ASP) Scanning /Stability Module................ 28 5.2.3. Functional CP U M odule.............................................................................
30 5.2.4. FDDI Communication Module..................................................................
31 5.2.5. Broadcaster M odule....................................................................................
31 5.3.
APRM Anti-Aliasing............................................................................................
32 5.3.1. ASP Stability Data Processing...................................................................
33 5.3.2. Scanning ASP Module Software Architecture............................................ 34 5.3.3. Scanning ASP Module - Interrupt Service Routine.................................... 35 5.3.4. Scanning ASP Module - Main Loop............................................................
36 5.4.
APRM / LPRM Gain Adjustment.......................................................................
38 5.5.
Control Room (HICR) / NUMAC Chassis Display Interface...........................
40 5.5.1. APRM/LPRM Operator Display Interface Software Architecture............ 42 5.5.2. NUMAC Chassis - Front Panel Display & Keypad Interface................... 43 5.5.3. PRNM System (HICR) Control Room Operator Display........................... 44
- 6. Two Out of Four Logic Module.......................................................................................
46 v
NEDO-33696 Revision I Table of Figures Figure 1 NUMAC Standard 21-Slot Chassis Component.........................................................
6 Figure 2 PRN M System Functions............................................................................................
8 Figure 3 LPRM Signal Input and Data Processing....................................................................
9 Figure 4 PRNM Calculation Functions....................................................................................
10 Figure 5 PRN M System Interfaces...............................................................................................
11 Figure 6 PRNM System-Level Architecture.............................................................................
12 Figure 7 NIC Interface with PPC, RBM A, and RBM B..........................................................
14 Figure 8 N IC Com puter Layout.................................................................................................
15 Figure 9 Rod Block Monitor Subsystem Interfaces..................................................................
16 Figure 10 RBM Instrum ent Layout...........................................................................................
17 Figure 11 APRM / LPRM Subsystem Interfaces.......................................................................
18 Figure 12 APRM / LPRM Overview Block Diagram.............................................................
19 Figure 13 APRM/LPRM Instrument Layout...........................................................................
20 Figure 14 2-Out-Of-4 Logic Module and Bypass Switch........................................................
21 Figure 15 APRM Operator Display Overview........................................................................
22 Figure 16 APRM / LPRM Instrument.....................................................................................
23 Figure 17 APRM Instrument Functional CPU Software Architecture for Trip Functions.....
24 Figure 18 LPRM Instrument Functional CPU Software Architecture for Trip Functions.....
25 Figure 19 APRM Trip Signal Path Components......................................................................
27 Figure 20 5-Channel LPRM M odule........................................................................................
28 Figure 21 Automatic Signal Processor Module......................................................................
29 Figure 22 One of Two Channels of the FDDI Module............................................................
31 Figure 23 Broadcaster M odule.................................................................................................
32 Figure 24 Anti-Aliasing Filtering in APRM / LPRM Instrument.............................................
33 Figure 25 ASP Interrupt Service Routine Software Architecture.............................................
35 Figure 26 ASP Main Loop Software Architecture..................................................................
36 Figure 28. NUMAC Chassis Interface and APRM / LPRM Front Panel Display & Keypad...... 41 Figure 29 APRM / LPRM Operator Display Hardware Architecture...................................... 41 Figure 30 APRM / LPRM Operator Display and Keypad Interface Partial Software A rch itectu re..................................................................................................................
4 2 Figure 31 APRM / LPRM Front Panel Display & Keypad.....................................................
44 Figure 32 Operator Display Assembly - Control Room PRNM System HICR Console......
45 Figure 33 2-Out-Of-4 Logic Functions....................................................................................
46 Figure 34 2-Out-O f-4 Logic M odule........................................................................................
47 vi
NEDO-33696 Revision 1 Term ADC APRM ASP BTP CGS CPU CTP DI&C ISG-06 ENW FDDI FIR FSAR GEH GGNS IEEE I&C I/O ISG ISR LPRM NUMAC NIC NRC NUREG ODIO OPRM PLD PPC PRNMS RAI ACRONYMS AND ABBREVIATIONS Definition,
Analog to Digital Converter Average Power Range Monitor Automatic Signal Processor Branch Technical Position Columbia Generating Station Central Processing Unit Core Thermal Power NRC's Interim Staff Guidance, Digital I&C-ISG-06 Energy Northwest Fiber Direct Data Interface Finite Impulse Response Final Safety Analysis Report GE-Hitachi Nuclear Energy Americas LLC Grand Gulf Nuclear Station Institute of Electrical and Electronics Engineers Instrumentation & Control Input/Output Interim Staff Guidance Interrupt Service Routine Local Power Range Monitor Nuclear Measurement Analysis and Control NUMAC Interface Computer Nuclear Regulatory Commission Nuclear Regulatory Commission Regulation Open Drain Input/Output Oscillation Power Range Monitor Programmable Logic Device Primary Plant Computer Power Range Neutron Monitoring System Request for Additional Information vii
NEDO-33696 Revision 1 Term Definition.,
=
RAM Random Access Memory RMCS Reactor Manual Control System RPS Reactor Protection System STP Simulated Thermal Power T/H Track-and-Hold V&V Verification & Validation VME VERSA Module Eurocard viii
NEDO-33696 Revision 1
- 1.
Introduction This report describes the System Architecture & Theory of Operations of Nuclear Measurement Analysis and Control Power Range Neutron Monitoring (NUMAC PRNM) as specifically configured for Energy-Northwest's (ENWs) Columbia Generating Station (CGS).
The NRC's Interim Staff Guidance, Digital Instrumentation & Control-ISG-06 revision 1 (DI&C-ISG-06), identifies the following items - in the sections noted - as individual Phase 1 submittals:
- System Description (D.1.2, D.9.2, D.10.2)
- Hardware Architecture Descriptions (D. 1.2)
- Software Architecture Descriptions (D.3.2, D.4.4.3.2)
- Theory of Operations (see sub-section 1.3 for list of ISG-06 sections)
This report has been designed and structured to address these items within the context of the integrated NUMAC PRNM System Architecture'. The purpose, scope, and basis for this report are described within following sub-sections.
Sub-section 1.1, Purpose and Scope, identifies the primary objective and scope of this System Architecture & Theory of Operations Report.
Sub-section 1.2, System Architecture, discusses the basis and rationale for addressing the System Description, Hardware Architecture Description, and Software Architecture Descriptions within a single report.
Sub-section 1.3, Theory of Operations, addresses the primary function of the Theory of Operations as defined in DI&C ISG-06 Enclosure F, "Glossary," and identifies the DI&C ISG-06 sections assigned to the Theory of Operation.
Sub-section 1.4, Report Structure & Content, describes the overall structure of this report, identifies the individual sections - and their content, within the remainder of this report.
1.1.
Purpose and Scope The objective of this document is to not only describe the NUMAC Power Range Neutron Monitoring System Architecture, but more importantly, to demonstrate how the integrity of that architecture ensures that Safety Functions are reliably performed, and that faults and failures do not compromise or inhibit the actuation of safety functions.
This document addresses safety-related and non-safety-related portions of the NUMAC PRNM System including internal and external interfaces.
The scope for the safety-related portions of the NUMAC PRNM System includes detailed examinations of the sub-systems, interfaces to non-safety sub-systems, and the hardware and System Architecture, within this report, refers to the structures, interfaces, software & hardware components, and the interactions between and within those structures, interfaces and components which implement system functions.
1
NEDO-33696 Revision 1 software architectures within each sub-system. These examinations address timing, accuracy, mechanisms to address vulnerabilities, and response to faults, failures, and degraded conditions.
The scope for the non-safety-related portions of the NUMAC PRNM System is limited to the identification of sub-systems, interfaces, and examining aspects of hardware and software architectures for vulnerabilities which could potentially threaten, inhibit, or adversely affect the actuation of safety functions.
1.2.
System Architecture E[
Unlike those platform-based systems, NUMAC systems are uniquely and explicitly designed to perform specific plant functions - and only those functions. And unlike those platform-based systems, there are no distinctions between the application and the system and sub-system design and architecture. ((
1.3.
Theory of Operations The primary function of a Theory of Operations, as defined in Enclosure F of DI&C-ISG-06, is to provide a:
"Description of how systems and components work together to accomplish the specified functions."
2
NEDO-33696 Revision 1 The hierarchical structure of this report describes these interactions at the system-level, sub-system level, module level, and between the hardware and software architectures within those modules.
Particular attention has been given to addressing the specific topics identified in the following ISG-06 sections as they relate to how systems and components work together to accomplish the specified functions:
- D.9.4.2.8 IEEE Standard 603, Clause 5.8, Information Displays
- D.9.4.2.9 IEEE Standard 603, Clause 5.9, Control of Access
- D.9.4.2.14 IEEE Standard 603, Clause 5.14, Human Factors Considerations
- D.9.4.3.2 IEEE Standard 603, Clause 6.2, Manual Control
- D.9.4.3.5 IEEE Standard 603, Clause 6.5, Capability for Testing and Calibration
- D.9.4.3.6 IEEE Standard 603, Clause 6.6, Operating Bypass
- D.9.4.3.7 IEEE Standard 603, Clause 6.7, Maintenance Bypass
- D.9.4.4 IEEE Standard 603, Clause 7, Execute Features As noted above, these items are discussed within the context of the integrated CGS NUMAC PRNM System Architecture.
1.4.
Report Structure & Content This document is structured to describe the PRNM System in a hierarchical manner from the overall NUMAC Product-Line, to the PRNM System-Level Architecture, to the sub-system architecture, and finally, the modules, hardware components, software components, and the software and hardware architecture within each safety-related sub-system.
The contents of this report are divided into the following sections:
Section 1 - Introduction (this section)
Section 2 - NUMAC Products Versus Digital I&C Platforms Section 3 - NUMAC PRNM System Overview Section 4 - PRNM Sub-System Architecture Overview Section 5 - APRM/LPRM Section 6 - Two Out of Four Logic Module
[II 3
NEDO-33696 Revision 1 1]
- 2.
NUMAC Products Versus Digital I&C Platforms
((
2.1.
Intended Purpose and Design Approach Comparison Commercial Digital I&C Platform Families 1[
4
NEDO-33696 Revision 1 NUMAC Product Family 2.2.
NUMAC Standard Components Versus Standard Platform Modules
((
5
NEDO-33696 Revision 1 1]
Figure 1 NUMAC Standard 21-Slot Chassis Component 2.3.
Summary Conclusion The differences identified above have significant ramifications in terms of how the PRNM System Architecture is reviewed and evaluated.
In platform-based systems, the application is implemented and resides within the architecture of the platform itself. The platform architecture can be viewed and evaluated as an independent entity - separate and distinct from the application.
The NUMAC PRNM System Architecture has no platform which can be viewed or evaluated independent of the application. ((
6
NEDO-33696 Revision 1
- 3.
NUMAC PRNM System Overview 3.1.
PRNM System Functions This section describes the system-level safety-related functions performed by the PRNM System.
The primary safety-related function of the PRNM system is to assert a trip output upon detection of any of the following events:
Neutron flux obtained by averaging the flux values from all operative LPRMs meets or exceeds the Flux Upscale Trip Setpoint Simulated thermal power obtained by applying a six second time constant infinite impulse response filter to the average neutron flux meets or exceeds the Simulated Thermal Power Upscale Trip Setpoint.
Core power fluctuations detected by the OPRM stability function meet applicable criteria for a channel trip 7
NEDO-33696 Revision 1 Figure 2 PRNM System Functions 8
NEDO-33696 Revision I Input Processing Description 11
]I Er Figure 3 LPRM Signal Input and Data Processing 11 1]
PRNM calculation functions Er 9
NEDO-33696 Revision 1 Er Figure 4 PRNM Calculation Functions 3.2.
PRNM System Interfaces As shown in Figure 5 PRNM System Interfaces, the PRNM system has five external system interfaces:
T,PRM l'hetector*
0 0
0 0
Recirculation Flow Plant Process Computer Reactor Manual Control System Reactor Protection System (RPS)
Er 10
NEDO-33696 Revision 1
[Fy Figure 5 PRNM System Interfaces
((I 11
NEDO-33696 Revision 1 3.3.
PRNM System-Level Architecture 11 Figure 6 PRNM System-Level Architecture 11 12
NEDO-33696 Revision 1 1]
- 4.
PRNM Sub-System Architecture Overview Er
))
4.1.
NUMAC Interface Computer (Non-Safety-Related)
The NIC does not perform any safety-related functions. ((
4.1.1. NIC Overview Description Er 1]
13
NEDO-33696 Revision 1 4.1.2. NIC Interfaces Er Er]
1]
Figure 7 NIC Interface with PPC, RBM A, and RBM B NIC/PPC Communication The NIC communicates with the PPC over two ((
procession unit (CPU) module.
)) ports residing on the main central
]1 NIC/RBM Communication The NIC communicates with the RBM channels over fiber-optic links residing on a GEH-designed Fiber Optic board.
Er 4.1.3. NIC Computer Layout Er
]1 14
NEDO-33696 Revision 1 Er Figure 8 NIC Computer Layout 4.2.
Rod Block Monitor (Non-Safety-Related)
The RBM does not perform any safety-related functions. ((
4.2.1. RBM Overview Description Er 4.2.2. RBM Interfaces Er 15
NEDO-33696 Revision 1 i t]
Er Figure 9 Rod Block Monitor Subsystem Interfaces Er 16
NEDO-33696 Revision 1 4.2.3. RBM Instrument Layout Diagram Figure 10 RBM Instrument Layout 4.3.
APRM/LPRM (Safety-Related)
This section provides a high level overview of the APRM / LPRM subsystem. Details of this subsystem are discussed in Section 6.
4.3.1. APRM / LPRM Overview Description Er 17
NEDO-33696 Revision I 4.3.2. APRM / LPRM Interfaces Er Er Fu Figure 11 APRM / LPRM Subsystem Interfaces Er 4.3.3. APRM / LPRM Block Diagram Er 18
NEDO-33696 Revision 1 Figure 12 APRM / LPRM Overview Block Diagram
((E 19
NEDO-33696 Revision 1 4.3.4. APRM/LPRM Instrument Layout Diagram
((
Figure 13 APRMILPRM Instrument Layout 4.4.
Two Out of Four Logic Module (Safety-Related)
Each 2-Out-of-4 Logic module is responsible for monitoring trip state information from all four APRM channels and bypass status of the other three 2-Out-Of-4 Logic modules to determine if PRNM trip conditions exist, and if so, issue a trip signal to the RPS.
Er 20
NEDO-33696 Revision 1 Er Figure 14 2-Out-Of-4 Logic Module and Bypass Switch 4.5.
NUMAC Display Units The Operator Display Assembly (ODA) units installed in the control room are part of the HICR console for the PRNM system. The PRNM system HICR console includes APRM operator displays and RBM operator displays. ((
))I 21
NEDO-33696 Revision 1 Er Figure 15 APRM Operator Display Overview Er
- 5.
APRM/LPRM Er 2I((
II]
22
NEDO-33696 Revision 1 1r 1]
Figure 16 APRM / LPRM Instrument Er 5.1.
Functional CPU Module Software Architecture The Functional Controller software, operating on the 386SX Module, ((
I))
Three of the tasks perform the primary functions involved in generating a PRNM system trip to the RPS.
Er 1]
23
NEDO-33696 Revision 1 ig[
]II Figure 17 APRM Instrument Functional CPU Software Architecture for Trip Functions
((l 24
NEDO-33696 Revision 1 11 Figure 18 LPRM Instrument Functional CPU Software Architecture for Trip Functions
((
25
NEDO-33696 Revision 1 5.2.
APRM Trip Signal Path 11 26
NEDO-33696 Revision 1 Figure 19 APRM Trip Signal Path Components
[1 5.2.1. 5-Channel LPRM Module R[
27
NEDO-33696 Revision 1
[1 Figure 20 5-Channel LPRM Module
[1 5.2.2. Automatic Signal Processor (ASP) Scanning / Stability Module
[r 28
NEDO-33696 Revision 1 Fm]
Figure 21 Automatic Signal Processor Module I[
3((I 1
29
NEDO-33696 Revision 1 5.2.3. Functional CPU Module 1T 30
NEDO-33696 Revision 1 5.2.4. FDDI Communication Module Transfer of LPRM detector data from the LPRM instrument to its associated APRM instrument are carried by an FDDI link connecting the two instruments. ((
E))
Figure 22 One of Two Channels of the FDDI Module Er 5.2.5. Broadcaster Module 31
NEDO-33696 Revision 1 Figure 23 Broadcaster Module 11 5.3.
APRM Anti-Aliasing
[1 32
NEDO-33696 Revision 1
[r Figure 24 Anti-Aliasing Filtering in APRM / LPRM Instrument Er 5.3.1. ASP Stability Data Processing Er 33
NEDO-33696 Revision 1 5.3.2. Scanning ASP Module Software Architecture 1]
4[
34
NEDO-33696 Revision 1 5.3.3. Scanning ASP Module - Interrupt Service Routine
((
Figure 25 ASP Interrupt Service Routine Software Architecture
[1 35
NEDO-33696 Revision 1 S i 5.3.4. Scanning ASP Module - Main Loop Er 1]
Er 1]
Figure 26 ASP Main Loop Software Architecture Er 36
NEDO-33696 Revision 1 1]
37
NEDO-33696 Revision 1 5.4.
APRM / LPRM Gain Adjustment An LPRM detector signal is a current produced by a fission ion chamber. This current signal is assumed to be proportional to the neutron flux in the vicinity of the LPRM detector. However, to represent a calibrated flux value for the LPRM signal, gain factors must be applied to the measured detector current. ((
))
Individual LPRM detector signals are calibrated relative to the set of LPRM detectors using a traveling in-core probe (TIP). ((
38
NEDO-33696 Revision 1 APRM / LPRM Gain - LPRM / APRM Instrument
((
39
NEDO-33696 Revision 1 LPRM / APRM Gain Adjustment Architecture Er Figure 27 LPRM / APRM Gain Adjustment Architecture 5.5.
Control Room (HICR) / NUMAC Chassis Display Interface E[
40
NEDO-33696 Revision 1 gr Figure 28. NUMAC Chassis Interface and APRM / LPRM Front Panel Display & Keypad Er Er]
Figure 29 APRM / LPRM Operator Display Hardware Architecture 41
NEDO-33696 Revision 1 11 5.5.1.
APRM / LPRM Operator Display Interface Software Architecture Er 1]
Er Figure 30 APRM / LPRM Operator Display and Keypad Interface Partial Software Architecture Er 42
NEDO-33696 Revision 1 5.5.2.
NUMAC Chassis - Front Panel Display & Keypad Interface
[1 I]
43
NEDO-33696 Revision 1 Er Figure 31 APRM / LPRM Front Panel Display & Keypad Er 5.5.3.
PRNM System (HICR) Control Room Operator Display The Operator Display Assembly ODA is designed to provide the operator with Local Power Range Monitor (LPRM) detector signals, average neutron flux, upscale and downscale trip and alarm setpoints, recirculation flow, equipment status, and OPRM stability data, in a remote location from the APRM instruments.
The ODA in the PRNM HICR console located in the control room is depicted in Figure 32.
44
NEDO-33696 Revision 1 Figure 32 Operator Display Assembly - Control Room PRNM System HICR Console 45
NEDO-33696 Revision 1
- 6.
Two Out of Four Logic Module The 2-Out-Of-4 Logic module provides the interface for the PRNM system to the RPS divisions.
The 2-Out-Of-4 Logic functions are shown in Figure 33. ((
I'))
Figure 33 2-Out-Of-4 Logic Functions 1[
46
NEDO-33696 Revision 1 FL 1]
Figure 34 2-Out-Of-4 Logic Module Er 47
NEDO-33696 Revision 1 48