ML16141A368
| ML16141A368 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/2016 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Plant Licensing Branch 1 |
| Parker C, NRR/DORL/LPLI-II, 415-1603 | |
| References | |
| CAC MF6768, DOC-0006-2118 R2 | |
| Download: ML16141A368 (37) | |
Text
Updated Issues List for April 19, 2016 Public Teleconference between PSEG LLC and the Nuclear Regulatory Commission Hope Creek Generating Station (HCGS)
Power Range Neutron Monitoring (PRNM) System Digital Upgrade License Amendment Request HCGS NUMAC Upgrade - Open Items DOC-0006-2118 R2
HCGS NUMAC Upgrade - Open Items No.
Resp.
Issue Description
- 1.
EICB
System Description
Appendix R provides responses to plant specific responses to the NUMAC LTR.
The response to L TR 2.3.4 identifies the configuration for HCGS to be 4 APRM channels with one APRM chassis and one LPRM chassis. However the L TR and Appendix A system architecture do not describe this.
Appendix A describes a master/slave APRM instrument, but the L TR describes a LPRM unit not clear how these two concepts relate, if they do.
Provide a figure showing the system architecture for the HCGS PRNMS.
- 2.
EICB
System Description
Appendix A seems to describe the generic PRNM system architecture and not the architecture for HCGS. What is different between this description and the one provided in the L TR?
Also there are system differences, which are described in Appendix J. How do these modules work and fit in the system architecture for HCGS?
- 3.
EICB
System Description
Appendix J identifies Hope Creek deviations from the approved generic Status RAI No.
Close No Close No Close No 1
PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 L TR 5.3.1 first bullet discusses APRM chassis and (for large cores) LPRM chassis.
NEDC-33864P Appendix A refers to these two chassis as APRM-Master and Slave.
Master refers to the APRM chassis and Slave refers to the LPRM chassis. These terms are used interchangeably.
NEDC-33864P Appendix A page A-11 shows the system level architecture.
The LTR describes variants of PRNM system architecture, depending on whether the target application (plant) has a large or small core, and whether it is BWR6 or non-BWR6. Appendix A provides additional details about large core, non-BWR6, such as Hope Creek.
The differences described in Appendix J are not architectural differences.
NRC update 03022016: NRC will identify the documents to be placed in the portal.
a)
No.
Resp.
Issue Description NUMAC PRNM system. This is required in ISG-06 Section D.8.
a) Table 1 lists these deviations and provide justifications for such.
Please provide additional information for the following items:
Column Reference Document -
what are these documents?
Item 2 - Why the modification for time to calculate flow-biased trip setpoint is a clarification? It seems that the total time for the Hope Creek Design has changed.
Item 5 - What higher level of security was applied and to what activities?
b) Section 4.2 describes the relay logic for HCGS. Please clarify how the improved relay logic module relates to the new relay logic card to be included in the Hope Creek PRNM system.
- 4.
EICB Software Development Plans The plans submitted describe GEH processes, but they do not include the activities to be performed by the licensee, such as oversight. Please describe the activities and processes for which PSEG is responsible.
Status RAI No.
Close No 2
DOC-0006-2118 R2 NRC Update 3-28-16 PSEG Response
- These are GEH references pointing to where the support for the justification is stored in the GEH document system.
The following two referenced documents can be placed in reading room upon request.
Item 2 - 001 N5637 PRNM Time to Calculate Flow-biased Trip Setpoint Item 5 - 001 N5640 PRNM Increased Instrument Security b)
"Relay Logic Module" and "Relay Logic Card" refer to the same thing. Hope Creek will receive the new design.
NRC update 03022016: NRC will identify the documents to be placed in the portal.
PSEG is required to create or acquire a number of documents from vendors providing safety related equipment per IT-AA-101. The purpose of many of these documents is to ensure the vendor has a aualitv orocess in olace for software and
No.
Resp.
Issue Description Status RAI No.
3 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 product design and that the process and design are accurately documented and tested. The required documents include a configuration management plan, a problem management and reporting process, a disaster recovery process, documented functional requirements, a documented technical design, a verification and validation plan, testing reports, user documentation, code review process and documentation and a traceability matrix to ensure all requirements are tested.
In addition, CC-AA-103-1007 responsibilities state:
Lead Responsible Engineers (LREs) are responsible for ensuring DCPs with digital devices are provided to DTS Design Engineer for review. DTS Design Engineers are responsible for reviewing Design Change Packages (DCP) with digital devices ensuring an adequate Critical Digital Review (CDR) is performed and documented. The DTS Engineer determines the scope and breadth of the CDR for the particular application.
A critical digital review is a review of a vendor's software QA processes and a technical review (EMl/RFI, failure analysis) of the design, documentation, and testing of a digital device determining the software/hardware's suitability for purchase and installation at PSEG Nuclear facilities.
No.
Resp.
Issue Description Status RAI No.
4 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 PSEG personnel participated in critical digital review that was led by ProDesCon on the GEH Power Range Neutron Monitoring System (also refer to LAR Attachment 1 Section 3). The CDR report pointed out that GEH has an established regulatory approved Appendix B quality program and that they're processes are suitable to ensure the quality of the design, configuration control, Part 21 reportability and the system maintenance throughout the life cycle. The CDR included a high-level review of the overall system design, focusing on the safety functions of the system and how digital design principles indicative of highly reliable digital systems were applied to the PRNM system.
PSEG has reviewed and commented on software lifecycle documentation produced by GEH throughout the project.
In addition PSEG has performed two audits (reference Survey numbers NOV2116-014 and NOD-15-038) thus far on GEH to help ensure product reliability. These audits focused on GEH audits performed on subcontractor Gavial, the GEH actions and process to correct identified issues, QA hold points placed on the purchase order, overall test plans and completed testing, restrictions placed on the Gavial subcontractor, cyber security aspects of the project and the GEH engineering change
No.
Resp.
Issue Description
- 5.
EICB Software Development Plans The proprietary markings in the appendices are inconsistent. For example, information in Sections 4.2 and 4.3 in Appendix B is not marked proprietary, but this same information is also provided in Sections 4.2 and 4.3 of Appendix D, where is marked as proprietary.
- 6.
EICB Appendix E, PRNM System Management Plan a) Section 2.3 describes how project management will be performed.
This section refers to critical-to-quality features to be part of the management process. However, this plan does no define these features. Since these features are part of project oversight, please describe these features and in which document will they be recorded?
Status RAI No.
Open Close RAI 5
PSEG Response process.
DOC-0006-2118 R2 NRC Update 3-28-16 PSEG also plans to witness continued factory testing with the quality assurance department.
4/19/2016 A complete replacement of Appendix B proprietary and non-proprietary with the corrected pages will be provided.
2/16/2016 Appendix B Sections 4.2 and 4.3 should be marked proprietary to match Appendix D.
Updated copies of Appendix B proprietary and non-proprietary can be provided.
A Project Work Plan (PWP) is required by GEH policies and procedures. As stated in Appendix B Section 3.1.1.5, the PWP contains personnel and commercial information, including project budgetary information that is classified as GEH Proprietary Class Ill (confidential). The PWP is created and maintained by the Project Manager to manage the commercial aspects of the project. Critical to quality features are project specific and are listed in the PWP. For Hope Creek, these are listed in Appendix C3 of the Hope Creek PRNM Upgrade PWP.
No.
Resp.
Issue Description Status RAI No.
b) Section 2.4.1 describes the secure development environment. This section states the control employs in the system development should be in accordance with GEH established procedures, consistent with guidance provided in RG 1.152. Please describe the GEH procedures to be followed for secure development environment.
c) Section 3.1 describes the need to establish project quality metrics.
However, this section does not identify the project quality metrics.
6 DOC-0006-2118 R2 NRG Update 3-28-16 PSEG Response A collection of administrative procedures covers specific topics related to the secure development environment:
Asset Identification Secure Development Network Physical Security Malicious Code Protection Patch Management Server and Computer Hardening Threat Analysis Software Usage Electronic Access Control Log Management Personnel Security and Segregation of Duties Production Deployment Product Handling and Delivery Incident Response Contingency Planning Security Control Review Changes to Physical, Logical, or Programmatic Controls 3/15/2016 Sugglemental Resgonse NRG Clarification BTP 7-14 requires the applicant identify the metrics to track progress and determine appropriateness of its software development process. The NRG staff needs a clear description on how the licensee is using configuration reviews and technical reviews to measure success or failure of the
No.
Resp.
Issue Description Status RAI No.
7 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 software development process.
This item is identified in open items: 6c, 7g, Ba, and 11e
Response
The software development process includes a series of technical design reviews and baseline reviews. At the end of each of these reviews, a review report and a scorecard will be issued by the review chair.
The review report summarizes the results of the review. The scorecard evaluates the content of the review material and the performance of the design team based on pre-established criteria also known as metrics, e.g., "Did the design team resolve action items assigned at previous reviews, or are acceptable plans in place?" A successful review will require a passing grade of 75%. However, any grade below 90% would result in action items to correct the deficiency in the design or in the compliance with the design process.
Condition reports will be issued in accordance with GEH problem reporting procedure should a design fail any of the reviews.
2/16/2016 The Design Review Summary Report and Design Review Scorecard provide a record of quality metrics applied by the Chief Engineer's Office. A copy of a scorecard can be placed in the ReadinQ Room upon
No.
Resp.
Issue Description
- 7.
EICB Appendix B, PRNM Systems Engineering Development Plan a) Section 2.4.1 of Appendix K states the verification of the design documents is performed by the design team prior to IVV activities.
But section 2.3 seems to imply that these reviews are performed by a team independent of the design team. In addition, section 4.2 of Appendix B also describes an independent review team who perform the technical design review. Please clarify what group (in the GEH organization) performs these independent reviews.
b) Section 2.4.1 describes the technical design reviews. This section states the design team is responsible for resolving issues identified during these reviews.
How are these issues being recorded and tracked? Section 4.5 of this appendix describes how deficiencies or discrepancies could be tracked, and Section 7.0 states they could use engineering change order to handle problems encountered during product development. But these statements Status RAI No.
Ciose RAi 8
PSEG Response request.
DOC-0006-2118 R2 NRG Update 3-28-16 When the design team prepares and releases design artifacts, GEH procedures require the Design team to perform verification of documents prior to the document release. The released document is then provided to the IVV team who conducts the independent verification in accordance with the SylVVP. Conducting the IVV activities defined in the SylVVP (Section 3.0) constitutes the Technical Design Review, which is performed by the IVV team and is supervised by the Chief Engineers Office.
3/15/2016 Sugglemental Resgonse NRG Clarification BTP 7-14 requires the applicant identify how anomalies are identified, documented, tracked and resolved. The staff needs a clear description on how PSEG and GEH are performing these activities during the design and development, V&V, and testing, and then after the system is installed in HCGS. This item is identified in open items:
7b, Ba, Bb, and 11 f GEH Resoonse
No.
Resp.
Issue Description Status RAI No.
are not specific. In addition, it seems that these options are used after delivery of the NUMAC system. Please explain what method will be used to identify and track problems identified during the technical design reviews. Also, explain the process to approve the resolution of these problems.
9 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 During design & development of the PRNM system for PSEG, the IVV Team would review and provide comments about design artifacts at each phase. The comments and resolutions are archived in the design records in accordance with GEH procedures. The comments, resolutions and any open items are also reported and tracked in Appendix A of the SyVV Task Report or SySA Task Report for each phase as discussed in Section 4.4 of the SyEDP, SylVVP and SyQAP.
During IVV team testing, when anomalies are observed, they are recorded in the control copy of the test datasheets. The anomalies and the resolutions, which may include changes or corrections to the design, are discussed in the test reports. An independent engineer is responsible to verify that the content of test report is consistent with the test data sheets. The technical design reviews and baseline reviews will confirm that the acceptance of the resolution and the closure of the anomalies or open items. Resolution of all anomalies and closure of all open items are required before the system can be delivered to PSEG.
After GEH delivers the system to PSEG, if an anomaly is discovered it would be tracked in the GEH Corrective Action ProQram.
No.
Resp.
Issue Description Status RAI No.
c) Section 4.3 states the baseline review team would also review and 10 PSEG Response PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 As discussed in the response to Open Item (01) #4, PSEG will continue oversight and audit activities during the design, development, V&V, and testing of the PRNM system. The processes discussed in 01#4 will disposition any anomalies identified. This will include, as appropriate, resolution in the PSEG Corrective Action Program (CAP) -LS-AA-125 - and in the Engineer of Choice (EOC) corrective action program (for the vendor performing the design change package for the PRNM upgrade - Sargent and Lundy).
During installation and acceptance testing, and after installation, both the PSEG CAP and EOC CAP will be used to identify, document, track and resolve anomalies.
2/16/2016 Project specific issues that remain open across project phases are tracked in the task reports. See Section 4.4.2 of the NUMAC Systems Engineering Development Plan. Closure of open items is reviewed as part of subsequent Baseline reviews; open items are resolved and closed prior to completion of the final Baseline review.
The SyQA Functional Configuration Audit Checklist (NUMAC System Quality
No.
Resp.
Issue Description Status RAI No.
approve development tools. Was this necessary for the HCGS PRNM system?
d) Section 5.0 describes the use of development tools. BTP 7-14, Section B.3.1.2.3 requires licensee to provide a description of software tools to be used. Please identify the software development tools.
11 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 Assurance Plan Section 4.4.1) lists tools that were approved for the associated baseline. A SyQA Functional Configuration Audit Checklist is developed for each Baseline.
Tools are approved for use via the Baseline review process for application to a specific project. Tools were used for the HCGS PRNM system development.
3/15/2016 Su1212lemental Res12onse NRC Clarification BTP 7-14 requires the applicant identify the software tools used for the development of the system. The NRC staff needs a list and reference of the software tools being used for the development of the HCS NUMAC.
During the call, the licensee noted these tools were described in previous license amendments, if this is the case, then the staff needs the references or ML numbers for the documents that described the software tools. This item is identified in open items: 7d and 9b Res12onse The Hope Creek PRNM system has similar hardware and software designs as previously approved PRNM projects, e.g.,
Grand Gulf and Columbia. Therefore, the software tools for the HCGS PRNM are the same as those previously described for Columbia in NEDC-33685P Revision 2
No.
Resp.
Issue Description e) Section 6.0 describes the secure development and operational environment. This section states access to the NUMAC lab is controlled and monitored. But it does not provide details on how these are perform. Please provide detail explanation.
f)
Section 6.0 describes the secure development and operational environment. This section states the code is maintained in the secure server. How is access qranted to this server?
g) Section B.3.1.2.2 of BTP 7-14 requires licensee to identify the indicators to determine the success or failure of the development processes. This information was not Status RAI No.
12 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 (ML12040A074) Section 4.4.6.
2/16/2016 Tools are selected and approved for use throughout the various phases of project.
The approved tools are documented in the SyQA Functional Configuration Audit Checklists (NUMAC System Quality Assurance Plan Section 4.4.1 ).
GEH provided details on software tools during previous (Grand Gulf and Columbia) projects. See RAI #3 in GNR0-2011/00038 (ML111370259) and Section 4.4.6 in NEDC-33685 (ML12040A074).
GEH has a procedure for controlling access to the NUMAC lab; see response to Open Item 6.b.
GEH has a procedure for access control of the secure server, see response to Open Item 6.b.
3/15/2016 Su1212lemental Res12onse See open item 6.c.
2/16/2016 Success or failure is indicated by the Design
No.
Resp.
Issue Description provided in the engineering development plan. In addition, Appendix A in Appendix K identifies the alignment to NUMAC documents. This table identifies that this information in SyMP (See open item 6.c). Please provide this information.
- 8.
EICB Appendix C, NUMAC Systems Quality Assurance Plan a) General comment: This plan does not cover all the activities identified in section B.3.1.3 of the BTP 7-14.
Specifically, this plan does not describe the corrective action program, description of QA procedures, and indicators to determine software quality.
b) Section 3.0 states unresolved configuration items is grounds for failure. How are these issues identified, recorded and tracked?
Who is responsible for approving resolution of these issues? (see open item 7.b)
Status RAI No.
Open RAJ 13 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 Review Summary Report and Design Review Scorecard.
3/15/2016 Su1212lemental Res12onse See open item 6.c and open item 7.b.
2/16/2016 The NUMAC plans augment and supplement the GEH QA Program. As stated in Section 1.0 of the NUMAC Systems Quality Assurance Plan, the GEH Quality Assurance Program encompasses quality assurance related activities such as audits, supplier control, and archiving of quality records. Although not explicitly mentioned, the corrective action program is a component of the GEH Quality Assurance Program.
3/15/2016 Su1212lemental Res12onse See open item 7.b.
2/16/2016 Open items are listed in the System Quality Assurance Configuration Audit Checklist and tracked in the System Confiquration
No.
Resp.
Issue Description c) Section 4.4.1 describes the oversight activity associated with quality assurance. Is the activity described in this section the only oversight activity to be performed?
(This section is marked proprietary so the specific activity is not identified in the question). What happens if problems are identified durinq this oversiqht activity?
- 9.
EICB Software Integration Plan (SlntP)
GEH did not submit a separate plan for this. However, GEH (Appendix K) identified the NUMAC documents that cover the requirements for this plan {BTP 7-14, Section B.3.1.4). Based on this information, the staff identified the followinq questions:
a) Section B.3.1.4.2 identifies the implementation characteristics of the SlntP. His section requires description of the software integration activities. GEH references SyEDp for this, but SyEDP does not provide enough information about the software integration process. Please provide Status RAI No.
Close RAJ 14 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 Management Task report (SyEDP 4.4.2).
The checklist and task report are part of the Baseline Review Records. These records are approved by the baseline review team, which is chaired by the Chief Consulting Engineer.
As discussed in response to Question 8.a, the GEH Quality Assurance Program has other activities. Problems are tracked in accordance with GEH procedures.
GEH does not have a separate software integration team, rather software integration is performed by the design team. Therefore, the characteristics described in the SyEDP for design team activities apply to integration activities as well. For explanation of how measurement is performed, see response to 6.c.
No.
Resp.
Issue Description this information.
b) Section B.3.1.4.3 identifies software tools. As mentioned in open item 7.d, these GEH document do not identify the software tools to be used. Please provide this information.
- 10.
EICB Software Safety Plan (SSP)
GEH did to submit a separate plan for this.
However, GEH (Appendix K) identified the NUMAC documents that cover the requirements for this plan (BTP 7-14, Section B.3.1.9). Based on this information, the staff identified the following question:
Appendix K refers to the IVVP and SyMP for the information required in BTP 7-14.
However, the information identified in these sources seem to address the hazard analysis required by IEEE 102, and not what is required in BTP 7-14.
The SSP should provide a general description of the software safety effort, and the intended interactions between the software safety organization and the general system safety organization.
- 11.
Appendix D, NUMAC Systems Independent Verification and Validation a) Section 2.1 describes the GEH organization. This section states the GEH Chief Engineer's office supervises independent V&V Status RAI No.
Close No Close RA!
15 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 3/15/2016 Sui;~mlemental Res1:2onse See open item 7.d.
2/16/2016 See response to open item 7.d.
The PRNM upgrade is a retrofit system. As a retrofit system, the GEH approach to software safety planning for PRNM is to ensure that the safety significance of the PRNM retrofit is consistent with the design basis of the replaced system and of the plant. GEH provided details on software safety approach during previous (Grand Gulf and Columbia) projects. See RAI #1 and 2 in GNR0-2011/00039 (ML111460590) and Section 4.4.1.9 in NEDC-33685(ML12040A074).
The Chief Consulting Engineer reports to the Chief Engineer's Office.
No.
Resp.
Issue Description activities. However, Appendix D, Figure 2-1 identifies the Chief Consulting Engineer as the person responsible for V&V activities.
b) Section 3.1.2 describes the safety analysis for the concept phase. It is not clear if this activity will include the preliminary hazard analysis, since it seems to only cover evaluation of the documentation.
c) Is the safety analyses described in each lifecycle phase considered to be the hazard analysis identified in IEEE Std. 1012? If so, will this also include the risk analysis identified in IEEE Std. 1012?
d) Appendix K refers to the IVVP Section 4.0 to confirm item B.3.1.10.1, risks. Section 4.0 describes the baseline process. So it is not clear how the baseline process will be used to identify and manage risks associated with the V&V process.
e) Appendix K refers to several sections in the IVVP to confirm item B.3.1.10.2, measurement.
However, the information provided does not clearly define the Status RAI No.
16 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 See response to open item 10.
Hazard analysis is performed during various lifecycle phases as indicated in Appendix K, Table 5 for cross-reference of IEEE Std 1012 to NUMAC process.
Project risk management is performed during all system life cycle development phases in accordance with the GEH Quality Assurance Proaram Project risk management is performed during all system life cycle development phases in accordance with the GEH Quality Assurance Program. SylVVP Section 4.2 describes Technical Reviews. Although not stated in the SylVVP, the GEH procedure for Technical Design Reviews requires risks management. SylVVP Section 4.3 describes Baseline Reviews, which are a process check to ensure the project plans are beina followed.
3/15/2016 SuQQlemental ResQonse See open item 6.c.
2/16/2016 See response to open item 6.c.
No.
Resp.
Issue Description indicators that will be used.
f)
Section B.3.1.10.2, procedures requires applicants to describe how anomalies are identified and reported. This information is not provide in the plan (See item 11.b above)
- 12.
EICB Software Configuration Management Plan (SCMP)
GEH did to submit a separate plan for this.
However, GEH (Appendix K) identified the NU MAC documents that cover the requirements for this plan (BTP 7-14, Section B.3.1.11 ). Based on this information, the staff identified the following question:
Appendix K refers to the SyEDP for the information required in section B.3.1.11.2, procedures. However, the information identified in these sources seem to address only configuration of documents, and not all configuration items (e.g., software tools, source code, etc.). How will GEH control these items?
- 13.
EICB EQ Testing Status RAI No.
Close RA!
Close no 17 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 3/15/2016 Sugglemental Resgonse See open item 7.b.
2/16/2016 Per section 2.2.2 and 2.2.3 of the SylVV, the System Verification Engineer and System Safety Analysis Engineer are responsible for documenting results of reviews including anomalies in their respective tasks reports. The task reports are discussed in sections 4.4.1 and 4.4.2.
SyEDP - section 3.4 specifies configuration management of source code and section 5 specifies configuration management of firmware. Tools are controlled at the baseline in which they are introduced.
Configuration Status Accounting includes all the configurable items.
4/19/2016 The Qualification Summary Report has
No.
Resp.
Issue Description Status The system equipment qualification (EQ) test plan was not submitted with the LAA.
Instead the licensee submitted an EQ program in Appendix H. This program states the EQ plans will provide the details on the system to be qualified. Also, that the EQ program provides guidance to prepare EQ plans, if they are necessary. For this amendment, GEH described design changes for the HVPS, Relay Logic Card, and UFP Display. Therefore, a qualification plan for these components should be submitted. ISG-06, Section D.5.2 describes the information to be provided for the staff to evaluate EQ of l&C systems. Section D.5.2 requires submittal of the EQ plan.
- 14.
EICB EQ Testing Requirements Close Are the EQ requirements based on the plant conditions?
18 RAI No.
no PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 been uploaded to the PRNM Reading Room portal {Phase 2 folder):
"002N9894-PRNM System Qualification Summary Report_RevO.pdf" NRC update 03022016: The qualification summary report will provide the information requested.
These items are encompassed by Appendix H. They are specifically identified in Section 3.3 and qualification approach is discussed in Section 5.
The EQ requirements are based on plant conditions:
From NEDC-33864P Appendix H Section 1.1:
The replacement NUMAC PRNM system is designed to maintain functional operability under conditions specified in the PSEG Hope Creek Generating Station Power Range Neutron Monitoring System (PRNM)
Upgrade Project H-1-SE-KDS-0494
[Reference 7.1 ]. The qualification requirements, the subject of this system qualification program, are further delineated in the NUMAC PRNM System Requirements Specification [Reference 7.2].
No.
Resp.
Issue Description Status
- 15.
APHB Section D.9.4, "Technical Evaluation, of Standby-Dl&C-ISG-06, Subsection D.9.4.2.14, awaiting "IEEE Std. 603, Clause 5.14, Human additional Factors Considerations, states, in part, information that the information provided should be from the sufficient to demonstrate that the guidance licensee contained in Standard Review Plan, Appendix 18-A, has been met.
NUREG-0800, Standard Review Plan, Appendix 18-A, "Crediting Manual Operator Actions in Diversity and Defense-in-Depth (D3) Analyses, Revision 0, states, in part, that a diversity and defense-in-depth analysis should include the justification of any operator actions that are credited for response to an Anticipated Operational Occurrence/Postulated Accident concurrent with software Common Cause Failure (CCF). It further states that credited manual operator actions and their associated interfaces (controls, displays, and alarms) should be specifically addressed in the vendor/licensee/applicant's Human Factors 19 RAI No.
PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 Reference 7.2 is provided as NEDC-33864P Appendix F Part 1 (NUMAC PRNM System Requirements Specification). Section 2.5 references Hope Creek specification H SE-KDS-0494; the qualification requirements in Appendix F Part 1 Section 9 are obtained directly from the Hope Creek specification.
An analysis, consistent with NUREG-0800, Appendix 18-A, will be provided demonstrating that the manual operator actions remain both feasible and reliable, and the ability to perform the actions reliably within the time available is maintained.
The analysis will be provided in the HCGS PRNM Electronic Reading Room portal, in the second quarter of 2016.
PSEG would like to discuss some clarifications concerning A1212endix 18-A:
- a. Phase 3 vs Phase 1 required time: If the required time (and margin to time available) has been verified via Phase 3 ISV, is it still necessary to perform the Phase 1 time required estimate?
- b. For the two manual operator action items from the D3 report the HCGS Operators have multiple existing indications available.
Consequently, PSEG does not need the simulator PRNM digital modification to
No.
Resp.
Issue Description Engineering (HFE) Program. The vendor/licensee/applicant should commit, in the defense-in-depth submittal, to include the proposed defense-in-depth coping actions in an HFE Program consistent with that described in NUREG-0711 and to provide the results of the HFE Program to the staff prior to implementation of the proposed action(s).
As stated in NUREG-0800, Appendix 18-A, to credit operator actions, an acceptable method would be to demonstrate that the manual actions in response to a BTP 7-19 software CCF are both feasible and reliable, given the time available, and that the ability of operators to perform credited actions reliably will be maintained for as long as the manual actions are necessary to satisfy the defense-in-depth analysis. Changes in plant design, including those that do not add, change, or delete the credited manual operator actions, may affect the ability of operators to correctly and reliably perform manual actions due to performance shaping factors (e.g., workload, time pressure) or other causes.
Provide information regarding the analysis, consistent with NUREG-0800, Appendix A, that was used to demonstrate that the manual actions remain both feasible and reliable, and the ability to perform the Status RAI No.
20 PSEG Response DOC-0006-2118 R2 NRG Update 3-28-16 support the18-A Phase 3 ISV; the existing plant/simulator configuration supports the ISV. The ISV is scheduled to be completed in March/April 2016. (Note: if simulator modifications were required before timing operator actions that could not be done until couple of months before modification implementation, ie 2018)
No.
Resp.
Issue Description actions reliably within the time available is maintained. The analysis should demonstrate that (1) the time available to perform the required manual actions is greater than the time required for the operator(s) to perform the actions, and (2) the operator(s) can perform the actions correctly and reliably in the time available. PSEG should provide sufficient information to demonstrate that the conclusions reached in the previously performed analysis regarding the feasibility and reliability of credited manual operator actions will remain valid in the post-modification environment (i.e., that the time available to perform the required manual actions and the time required to perform such actions will not be adversely affected by the proposed modification).
- 16.
RA System Requirements Appendix F defines the system requirements for the NUMAC PRNM system. It is not clear if these requirements reflect the system to be installed in HCGS.
Specifically, does appendix F include the requirements for the modified components described in Appendix J?
Status RAI No.
Close RA!
21 PSEG Response 3/15/2016 DOC-0006-2118 R2 NRC Update 3-28-16 The Hope Creek System Requirements Specification (Appendix F) is plant specific.
The following discussion elaborates on how the topics from Appendix J are addressed in the Hope Creek specifications.
L TR Deviations
NOTE: Appendix J Reference document 001 N5636 can be provided in the reading room portal, if desired. This topic was
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Issue Description Status RAI No.
~p*
22 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 discussed during previous PRNM projects.
Please see, Enclosure 1 (Section 1.5 and Appendix A) of ML12040A073, submitted for Columbia.
- 2. Time to Calculate Flow-biased Trip Setpoint. This clarifies a statement in the L TR but does not affect the NUMAC PRNM design.
NOTE: Appendix J Reference document 001 N5637 can be provided in the reading room portal, if desired. This topic was discussed during a previous PRNM project.
Please see, Enclosure 1 of ML12040A073, submitted for Columbia.
- 3. Abnormal Conditions Leading to Inoperative Status. Appendix F2, Section 4.3.4.9 reflects this L TR deviation.
NOTE: Appendix J Reference document 001 N5635 can be provided in the reading room portal, if desired. This topic was discussed during a previous PRNM project.
Please see Enclosure 1 of ML12040A073, submitted for Columbia.
NOTE: Appendix J Reference document 001 N5641 can be provided in the reading room portal, if desired. This topic was discussed during a previous PRNM project.
Please see Appendix A (page A-5) of ML101790437, submitted for Grand Gulf
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Issue Description Status RAI No.
23 PSEG Response DOC-0006-2118 R2 NRG Update 3-28-16 (DSS-CD Plant like HCGS).
- 5. Increased Instrument Security. Appendix F1 Section 4.1 (traceable item 436R) provides the higher level requirement that the system provides a means to adjust user-configurable parameters, and Appendix F2 Section 4.4.14 (traceable item 2345R) incorporates the same feature at the instrument level. That the Hope Creek design implements increased security relative to previous applications may be seen by comparing it to a previous application. Please see Section 4.4.8 of 25A5916, APRM Performance Specification for CGS (Reference 64 and included in Appendix A) - ML12040A074 submitted for Columbia. That design includes an "OPER-SET" function, a function that enables the user to adjust a small number of select parameters after entering a password but without placing the instrument in INOP.
PSEG elected to not include this feature at Hope Creek.
NOTE: Appendix J Reference document 001 N5640 can be provided in the reading room portal, if desired.
- 6. PRNM System Input Power Source. The deviation does not affect the PRNM design.
Appendix F1 Section 7.5 reflects the type of input power as described in the Hope Creek LAR Attachment 1 Section 4.1.1 page 28 of 46, which deviates from what is described in
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Issue Description Status RAI No.
DOC-0006-2118 R2 NRC Update 3-28-16 NOTE: Appendix J Reference document 002N3909 can be provided in the reading room portal, if desired.
Differences from Columbia Generating Station PRNM
- 1. OPRM Solution. Appendix F1 Section 4.1 (traceable item 225) and 4.3 reflect this difference.
- 2. Relay Logic Module. The new part is incorporated in schematics and bills of material, which may be placed in the reading room portal if desired. The design function is not changed and therefore does not affect Appendix F.
- 3. APRM High voltage Power Supply.
Appendix F2 Section 4.4.2 (traceable item 2322) reflects this difference (note that Appendix F2 Table 4.3-1 erroneously points to Section 3.3.1 vs 4.4.2 for 'Manual LPRM IN curve request').
- 4. Display of Calibration Constants for LPRM Detector and Flow Signals.
Appendix F2 Section 4.4.5 (traceable item 2287) reflects this difference.
- 5. Instrument Front Panel Display. The new part is incorporated in schematics and bills of material, which may be placed in the
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Issue Description Status RAI No.
- 17.
RA System Requirements Close No Appendix F defines the system requirements for the NUMAC PRNM system. There are requirements identified (use of the word SHALL) that do not include identifiers in brackets (e.g., Section 5.6). Then there are statements that seems more description than requirements (e.g.,
Sections 5.4 and 5.5). Clarify if all sections are requirements for the system.
- 18.
SRXB HCGS is changing the existing ABB OPRM New with the BWROG Option Ill stability solution to the GEH-OPRM with the Detect and Suppress Solution-Confirmation 25 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 reading room portal if desired. The design function is not changed and therefore does not affect Appendix F.
3/15/2016 The requirements marked with brackets in Appendix F are identified for traceability purposes. Appendix F also includes several sections that are written in support of the requirements marked with brackets for traceability. Section 4 of Appendix F1 states "The primary system functions of the integrated NUMAC PRNM replacement system are summarized below, followed by a specific identification of the safety functions of the system. See Sections 5 and 6 for more details on the input and output requirements discussed in this section." Therefore, Sections 5 and 6 are also considered as requirements although these requirements would not be explicitly traced in downstream documents. For example, it would be cumbersome to establish traceability for the LPRM assignments in Section 5.1. However, each LPRM assignment will be verified and validated in the V&V activities. The bases for the V&V would be Section 5.1 of Appendix F.
4/19/2016 PSEG can supply a representative power/flow map with BSP regions identified.
However, PSEG would like clarification on
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Issue Description Status Density (DSS-CD) stability solution.
Submit the HCGS power/flow map identifying Scram (Region I} and Controlled Entry (Region II). A plant-specific power/flow map is required for the review of DSS-CD setpoint evaluation given in Appendix T, "HCGS Thermal Hydraulic Stability, DSS-CD Evaluation" of NEDC-33864P.
- 19.
SRXB TS Change Sa, Table 3.3.6-2, Page 3/4 3-New 59, Control Rod Block Instrumentation set points:
The proposed new notes a, b, c, and d identify a low power set point of 28% rated thermal power and a high power set point of 83% rated thermal power. In the proposed addition to the Applicability section for Rod Block Monitor in TS 3.1.4.3 (PaQe 3/4 1-18), 30% and 90% are 26 RAI No.
PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 the purpose/value of providing such a map.
The Amplitude Discriminator Setpoint (SAD) and minimum time period limit (Tmin) are not dependent on the BSP regions as described in Section 2.1 of NEDC-33864P, Appendix T. The ABSP setpoints are developed based on the BSP Region I; however, the methodology described in the DSS-CD L TR is applied to establish or validate the ABSP setpoints (NEDC-33075P, Section 7.4 details ABSP region generation, Section 7.5.4 details ABSP implementation). This methodology will be applied on a cycle specific basis as required by Section 7.5.3 of the DSS-CD L TR.
Section 7.2 of the DSS-CD LTR describes the methodology for the generation of the manual BSP regions. With the implementation of DSS-CD there are no changes to the process to determine the cycle-specific manual BSP regions and the existing BSP methodology.
4/19/2016 The values provided in TS 3.1.4.3 are for determination of the operating region where the RSM is required to be operable. The 30% and 90% values are not associated with the power setpoints. The RSM is required to be operable above 30% RTP if the MCPR value is below the MCPR value provided in the COLR. There will be two MCPR values provided in the COLR; one that is applicable with power less than 90%
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Issue Description Status RAI No.
proposed. Provide a justification for the margins of 2% for the low set point and 7% for the high set point.
- 20.
SRXB (a) TS 6.9.1.9, Page 6-20, Core New Operating Limits Report:
Add or provide justification for not including the following staff-approved 27 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 RTP and one applicable at or above 90%
RTP. Unlike the power setpoints described below, the operability requirements are administrative. The operability requirements were determined by the analysis detailed in Section 3.5 of NEDC-33864P, Appendix S.
TS Table 3.3.6-2 has the added notes a, b, c, and d which identify the LPSP, IPSP, and HPSP. These setpoints are used to distinguish rated thermal power ranges that apply to the power trip setpoints. Section 3.3.1 of NEDC-33864P, Appendix S details the analysis completed for the determination of these values. Analytical Limits for the LPSP, IPSP, and HPSP are provided in Tables 5 and 6 of Appendix S while the Allowable Values and Nominal Trip Setpoints are provided in Section 3 of Appendix P2. Allowable Values are used in TS for the power setpoints; the analytical limit for the LPSP is 30%.
The RBM is automatically bypassed below the LPSP in accordance with the 30%
operability criteria described above. The HPSP does not represent an automatic bypass and is not associated with the 90%
operability criteria.
4/19/2016 (a) NEDC-33075P-A, Revision 8 (DSS-CD L TR) is incorporated by reference: Section 3.2 of Appendix T (NEDC-33864P) includes the disposition of Limitation and Condition
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Issue Description L TRs as references:
NEDC-33075P-A, Revision 8, "GE Hitachi Boiling Water Reactor Detect and Suppress Solution-Confirmation Density," November 2013.
NEDC-3241 OP-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option Ill Stability Trip Function," November 1997.
NEDC-3241 OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option Ill Stability Trip Function," October 1995.
(b) TS 6.9.1.9, Page 6-20, Core Operating Limits Report:
The following is provided in the DSS-CD L TR NEDC-33075P-A, Revision 8, Appendix A, Example of Changes to BWR/4 Standard Technical Specifications, TS Section 5.6.3, which is not included in the proposed Administrative Controls section of the technical specifications, Page 6-20, 6.9.1.9, Core Operating Limit Report:
"[For DSS-CD, the following is required in Status RAI No.
28 PSEG Response DOC-0006-2118 R2 NRG Update 3-28-16 5.2 which indicates that GESTAR (Global Nuclear Fuel, "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-22 and NEDE-24011-P-A-22-US.),
which includes reference to the DSS-CD L TR, is referenced in TS 6.9.1.9.
NEDC-3241 OP-A (PRNM L TR) is not required, or appropriate, to include in the COLR list of references. The PRNM L TR does not provide any analytical methodology for determining operating limits contained in the COLR. The PRNM L TR references were also not included in the approved changes to TS 5.6.3 (COLR) for the Columbia Generating Station PRNM upgrade (ADAMS ML13317B623).
(b) Appendix A of NEDC-33075P-A provides DSS-CD changes to the GE improved standard TS and Bases; PSEG has included appropriate language for the HCGS TS Bases. The limits in question are applicable to HCGS and are provided in the proposed changes to TS 6.9.1.9. This is indicated in mark-up of TS 6.9.1.9 by the addition of TS 2.2 (Reactor Protection System Instrumentation Setpoints) and TS 3/4.3.1 (Reactor Protection System Instrumentation) to the list of applicable TS.
The proposed changes to TS 2.2 and 3/4 3.1 indicate COLR provided values for the indicated limits. The proposed changes to HCGS TS 6.9.1.9 are similar to the approved chanaes to TS 5.6.3 (COLR) for
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Issue Description addition to the normal list of limits.]"
"1. The Manual Backup Stability Protection (BSP) Scram Region (Region I),
the Manual BSP Controlled Entry Region (Region II), the modified APRM flow-biased set point used in the OPRM, Automatic BSP Scram Region, and the BSP Boundary) for Specification 3.3.1.1."
Explain in detail why the above requirements given in the DSS-CD L TR are not in the proposed TSs. The NRC staff acknowledges that HCGS is not using "BSP Boundary," but justification is needed as to why the other regions are not applicable.
- 21.
SRXB TS Bases Insert 1, Page 3 of 5, 2.f. OPRM Upscale:
(a) Add GDCs 1 O and 12 and revise the first sentence as follows to be consistent with Appendix A of NEDC-33075P-A:
The OPRM Upscale Function provides compliance with GDC 1 O and 12, thereby providing protection from exceeding the fuel safety limit (SL) MCPR due to anticipated thermal-hydraulic oscillations.
(b) Add the following to be consistent with Appendix A (page A-20) of NEDC-33075P-A:
Status RAI No.
New 29 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 the Columbia Generating Station PRNM upgrade.
4/19/2016 (a) The TS Bases will be revised in accordance with the Open Item.
(b) Note (m) does not reflect a 'need', rather it describes an option (to prevent spurious scrams) that that plant may or may not choose to implement, consistent with NEDC-33075P-A, Section 3.2.6.
Information on Note (m) is included in the TS Bases consistent with the level of detail in the existing HCGS TS Bases, and consistent for a 'one-time' note. Also refer to the response to 01#23.
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Issue Description Note (m) in TS page 3/4 3-5 reflects the need for plant need for data collection in order to test the DSS-CD equipment.
Testing the DSS-CD equipment ensures its proper operation and prevents spurious reactor trips. Entry into the DSS-CD Armed Region without automatic arming of DSS-CD during this initial testing phase allows for changes in plant operations to address maintenance or other operational needs.
- 22.
SRXB, NEDC-33864P, Appendix I, Diversity and Defense in Depth (D3)
Analysis:
(a) Section 1.2, Background PRNM L TR NEDC-3241 OP, Section 6.4, provides a D3 assessment using EPRI Report No. NP-2230, Part 3, "ATWS Frequency of Anticipated Transients."
Section 6.4.1 refers to Table F-1. NRC staff review of this table is required to verify that for each event for which the PRNM may be called upon to initiate scram, there is at least one other parameter processed by a different type of l&C equipment that provides a diverse means of detecting the event and initiating a scram. This table is required for the review of Table 4.1, "Assessment of HCGS AOOs." Please submit the EPRI report.
(b) Section 4.1.2, Instability, page 1-9, Status RAI No.
New 30 PSEG Response 4/19/2016 DOC-0006-2118 R2 NRC Update 3-28-16 (a) The table NEDC-3241 OP-A Section 6.4 refers to is in NEDC-30851 P-A, which references the EPRI report. NEDC-30851 P-A was reviewed and approved previously, so it does not seem necessary to submit the EPRI report.
The table from NEDC-30851 P-A was also reproduced in the Columbia PRNM LAR.
See NED0-33694 (ML12040A076),
containing the D3 analysis for the Columbia PRNM. The Hope Creek LAR supplemented this analysis with NEDC-33864 Appendix I, which includes an evaluation of each event in the Hope Creek UFSAR against the criteria in BTP 7-19.
(b) The diverse systems that provide valid indications are described in Appendix I Section 4.1.2, starting with the last paragraph on page 1-9 (2RPT scenario) and the last paraqraoh on paqe 1-1 O (LFWH
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Issue Description states:
"The postulated CCF in the PRNM system results in the system providing valid indications of plant conditions until the stability transient occurs... " Assuming the failure of PRNM due to CCF, which system will provide the valid indications during instability events?.
(c) Section 4.1.2, Instability, pages 1-9 and 1-10:
Provide the TRACG transient results plots for the limiting cases to demonstrate that the SLMCPR is not exceeded for these events.
( d) On page 1-14, the response to BTP 7-19 Criterion 7 states:
"... instability is the only AOO requiring a diverse protection method." Please provide justification for this conclusion.
Revise Table 4-2 to show that this conclusion is valid.
- 23.
SRXB, NEDC-33864P, Appendix R, Plant Responses Required by PRNM L TR:
On page R-21, the licensee provided the following response:
"Regarding the initial monitoring period, the GEH NUMAC OPRM system can be installed and activated immediately without Status RAI No.
New 31 PSEG Response scenario).
DOC-0006-2118 R2 NRC Update 3-28-16 (c) The requested plots for the limiting cases are provided in GEH Document 003N5152, Revision 0. This document has been placed in the PRNM Reading Room portal.
(d) The quoted section refers to Section 4.1, which includes Table 4.1 (not Table 4.2).
Generic and plant-specific discussions are provided in Table 4.1 for each event except instability justifying that there is no threat to the applicable limits (BTP 7-19 Criterion ( 1))
posed by a CCF in PRNM in conjunction with the event.
4/19/2016 The response is provided in GEH Document 003N5152, Revision 0, which has been placed in the PRNM Reading Room portal.
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Issue Description an initial monitoring period because: 1) The operating experience of the GEH NUMAC OPRM system in general is sufficient, 2)
The GEH NUMAC OPRM system is replacing the current Option Ill OPRM system, 3) ((... )). The DSS-CD LTR does not require an additional monitoring period."
Every plant PRNMS is unique and, therefore, a monitoring period is required.
Because only a few BWRs have implemented DSS-CD, there is insufficient operating data to justify a deviation from the staff position discussed in the approved L TR (SER Section 3.2.6, First Cycle Implementation). Please provide justification for not requiring an additional monitoring period.
- 24.
SRXB, NEDC-33864P, Appendix S, Supplemental Information for ARTS for HCGS.
The Section 3.3.1 analyses refer to a generic statistical analysis for application to all BWRs, including HCGS. Identify the staff-approved L TR section that approved the generic statistical analyses.
Status RAI No.
New 32 PSEG Response 4/19/2016 DOC-0006-2118 R2 NRC Update 3-28-16 There is no NRC approved ARTS L TR; ARTS are individually analyzed and approved for each plant. ARTS (concurrent with MELLLA) for HCGS was approved by Amendment 163 (ADAMS ML060620500).
A HCGS-specific ARTS/MELLLA safety analysis report (A/MSAR), NEDC-33066P, was submitted to support the change. As discussed in NEDC-33864P Appendix S, the implementation of the NUMAC PRNM allows for the hardware portion of ARTS to be installed thus allowing the transition to full ARTS.
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Issue Description
- 25.
SRXB, NEDC-33864P, Appendix T, HCGS Thermal Hydraulic Stability, DSS-CD Evaluation:
(a) Section 2.1 DSS-CD Set points:
"As a part of DSS-CD implementation, the applicability checklist is incorporated into the reload evaluation process and is documented in the Supplemental Reload Licensing Report (SRLR)." Submit the SRLR for GNF2 fuel to verify the DSS-CD implementation process. (Confirmatory item)
(b) HCGS plans to transition from GE-14 to GNF2 during the implementation of PRNMS. Resubmit Appendix T, HCGS Thermal Hydraulic Stability DSS-CD Evaluation and Appendix S, Supplemental Information for ARTS for HCGS, for the GNF2. RWE analysis was done for Cycle
- 13. RWE analyses are required with the GNF2 fuel. (Confirmatory item)
(c) HCGS plant-specific LPRM/APRM data was gathered during Cycle 18 and Cycle 19 at lower power/flow conditions, rather than at full power/flow conditions. Please justify why it was not necessary to collect data at full power/flow conditions.
(d) In Table 2-1, a Checklist Confirmation Status RAJ No.
New 33 PSEG Response 4/19/2016 DOC-0006-2118 R2 NRC Update 3-28-16 (a) The DSS-CD implementation at HCGS is based on GE14 fuel and is done per the DSS-CD L TR (NEDC-33075P-A, Revision 8).
The DSS-CD stability section of the SRLR is of a standard format, which includes the confirmation checklist. If required, GEH can provide the reference of a representative DSS-CD SRLR already issued for another plant.
(b) The PRNM license amendment request is based on the GE14 fuel design that is currently in operation at Hope Creek.
The DSS-CD implementation at HCGS is per the DSS-CD L TR (NEDC-33075P-A, Revision 8). Any future implementation of a new fuel design at HCGS, such as GNF2, will be addressed through the approved DSS-CD process described in Section 6.1 of the LTR. Plant-specific review and approval is not required for fuel transition as stated in Items 7 and 9 in Section 6.0 of the Safety Evaluation of the DSS-CD LTR (NEDC-33075P-A, Revision 8).
As stated in the first paragraph of Section 3.3.1 of Appendix S, "A generic statistical analysis for application to all BWRs including HCGS has been performed and is summarized in Table 2. The application of
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Issue Description Status is provided. The NRG staff may perform an audit to verify the confirmations done for all the parameters.
(e) The rated feedwater temperature reduction is provided in Table 2-1.
Historically, what has been the maximum feedwater heater temperature reduction experienced at HCGS?
(f) The TRACG confirmatory best-estimate MCPR margins to the SLMCPR were calculated and are summarized in Table 2-
- 2. Submit the detailed plots that include the important parameters for the most limiting case.
(g) Table 3-1, Disposition of Limitations and Conditions:
In the table, only Condition 9.18 is addressed. Please address all (except for MELLLA+ items) conditions and limitations identified in the SER for NEDC-33173P, "Applicability of GE Methods to Expanded Operating Domains."
34 RAI No.
PSEG Response DOC-0006-2118 R2 NRG Update 3-28-16 these results is validated for GE and GNF fuel and core design for each reload analysis in accordance with Reference 2."
(Reference 2 being GESTAR-11).
Consequently, the application of the generic statistical analysis is not dependent on plant type, specific core design, or specific GE I GNF fuel design. The application of these results will be validated on a cycle specific bases including consideration of any future new fuel designs, such as GNF2, as described in Section 1.2.6 B of GESTAR-11.
(c) Thermal-Hydraulic instabilities are not of concern at rated conditions and the DSS-CD system is not armed at rated conditions.
Therefore, data collected at rated conditions is not of interest for DSS-CD applications.
(d) No response required.
(e) Hope Creek is licensed to operate at rated thermal power with feedwater at a minimum temperature of 329.6 °F (HCGS FOL 2.C.11 ). This corresponds to a 102 °F reduction from the rated feedwater temperature of 431.6 °F. PSEG would like clarification on why the maximum historical feedwater temperature reduction value is required in support of the value indicated in Table 2-1.
(f) The requested plot for the cases listed in Table 2-2 is provided in GEH Document
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Issue Description Status
- 26.
EICB Appendix R, Section 6.6 of Reference 1, New System failure Analysis, item 1, states "a similar Table to F-1 provided in Reference 11 (NEDC-30851 P-A) of the PRNM LTR is included in the HCGS defense-in-depth and diversity analysis. However, Appendix I of the LAR does not include this table.
PRNM L TR Section 6.4.1 requires identification the diverse parameter monitored to detect symptoms of each event. This table should include each event in Chapter 15 of HCGS's SAR where an APRM-based scram trip is credited in the analysis.
- 27.
EICB Appendix I provides the defense-in-depth New and diversity analysis for HCGS. This appendix does not include analysis for the 35 RAI No.
PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 003N5152, Revision 0, which has been placed in the PSEG Reading Room portal.
(g) The DSS-CD methodology is used for the detection and suppression of thermal-hydraulic instability. Only NEDC-33173P limitation and condition 9.18 is associated with stability and therefore is the only limitation and condition discussed in Section 2.1 (Page T-5) and addressed in Table 3-1 of Appendix T.
4/19/2016 The reference to Appendix I Table F-1 is an editorial error. During the preparation and review of the content that became Appendix I, it was decided to not reproduce Table F-1 from NEDC-30851 P-A, as was done during a previous LAR. (See response to Open Item #22a.)
If a copy of the table is necessary to complete the Hope Creek PRNM review, the table was provided previously, as discussed in response to Open Item #22a. It can be provided again in the reading room portal.
Note that each event from Hope Creek UFSAR Chapter 15 was evaluated, and those that could be affected by a CCF in PRNM are discussed in Appendix I Section 4.1and4.2.
4/19/2016 Each of the BTP 7-19 criteria are addressed in Appendix I. The criteria that directly
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Issue Description Status RAI No.
potential of the PRNMS to adversely affect other echelons of defense (e.g. the control echelon). Please describe how other echelons of defense could not be adversely influenced by interfaces with the PRNMS.
36 PSEG Response DOC-0006-2118 R2 NRC Update 3-28-16 address the potential of the PRNMS to adversely affect other echelons of defense may be found in Table 4.2. For example, The discussion about the potential for PRNMS to adversely affect the control echelon is addressed in Criterion (3).
A similar discussion has been provided in previous submittals:
Refer to RAI #9 in GNR0-2011/00039 (ML111460590) for GGNS, NEDC-33694P (ML12040A076) for Columbia.