ML20113A084
| ML20113A084 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/20/1996 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20113A046 | List: |
| References | |
| NUC-PI-15, NUDOCS 9606240053 | |
| Download: ML20113A084 (25) | |
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MILLSTONE NUCLEAR POWER STATION VENDOR PROCEDURE i
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Sciected MillstoneThit 3 System Reviews
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I Revision 1 PROJECTINSTRUCTION NUCPI15 SELECTED MILLSTONE UNIT 3 SYSTEM REVIEWS 1.0 Introduction
-bl 1.1 Purpose Provide a consistent review and evaluation approach for selected Millstone Unit 3 (MP3) systems in order to develey a basis for assessing the effectiveness of design controls and configurstion controls. This activity is a vertical slice review.
1.2 Objectives 1.2.1 Provide guidance to the review team participants when evaluating systems for effective implementation of design and configuration controls.
1.2.2 Provide guidance for documenting the system evaluations and the results of these evaluations.
1.3 Scope I
1.3.1 This PI will be used to evaluate the following systems:
- Service Water j
- Quench Spray and Containment Recirculation
- Reactor Trip Breakers
- Auxiliary Feedwater including ESFAS and AMSAC Initiation
- Emergency AC Power System
- Station Blackout Diesel Generator Rl
- 120V Vital AC
- Control Building Filtration and Ventilation
- Residual Heat Removal (S1 mode)
- Pressurizer Safety and Relief Valves i
Reference 6.1 provides the rationale for selecting the systems listed above.
1.3.2 This PI provides guidance for evaluating system configuration controls as they apply to plant documents. This PI also describes associated walkdown activities.
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l 1.4 Applicability This PI will be used to review the effectiveness with which design controls and configuration management controls have been applied to selected MP3 Systems.
2.0 Prerequisites and Administrative Requirements l
2.1 Quality Requirements This review will be performed in accordance with the NU Appendix B Quality Assurance Program.
Project Instruction users will be trained in accordance with NGP 2.26 in the goals and objectives of this review.
System reviewers must have broad experience and a sound t'echnical background in 1
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systems similar to those which they review.
Any discrepancies or adverse conditions identified by these system reviews will be l
brought to NU's attention for resolution in accordance with NUC PI-5 Millstone Unit 3 g
l System Readiness Review.
2.2 Definitions 2.2.1 Configuration Management
- An integrated management process to ensure that a nuclear unit's physical and functional characteristics are maintained in conformance with the unit's design and licensing bases.
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- nat operating, training, modification and maintenance processes are i
consistent with the design and licensing basis.
- That the plant is operated and maintained within these bases.
l AI 2.2.2 Licensing Basis (')
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- The set of applicable NRC requirements I
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- Written commitments that are docketed and in effect
- The design bases f
(1) Definition from CMP gg 2
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2.2.3 Discrepancy A finding generated as the result of an activity performed in accordance with this PI which indicates a potential need for process improvement or remedial action and for which an Unresolved Item Report (UIR) has been prepared but which has not yet been reviewed by the Plant Verification and Readiness Team (PVRI) in
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accordance with PI 5 to determine the significance of the UIR and its priority for resolution.
2.2.4 Design Bases (DB)")
- Information which identifies the specific functions to be performed by a structure, system or component 1
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- The specific values or range of values chosen for controlling parameters as l
reference bounds for design l
l 2.2.5 Design Control l
A process defined in 10CFR50, Appendix B, which satisfies the following requirements:
- The design shall be defined, controlled and verified.
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- Applicable design inputs shall be appropriately specified on a timely l
basis and correctly translated into design documents.
- Design interfaces shall be identified and controlled.
- Design adequacy shall be verified by persons other than those who designed the item.
i 2.2.6 Engineering Design Bases (')
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- Information which describes a system, structure, or component
- Operating values or parameters which are not reference bounds for design
- Information which identifies functions important for economic, maintenance, install! tion, or other nonsafety function of design basis systems, structures, or components l
l R1 (1) DeAnition from CMP 3
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-Information and operating values describing the functions of nonsafety systems j
- Calculations, descriptions, and other " outputs" 2.2.7 Configuration Management Plan (CMP)
The overall plan developed by NU to define the overall process and each Key Project j
Activity necessary to meet the following Mission Statement:
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/I The project m% be able to provide reasonable assurance that the future operation of each unit will be conducted in accordance with the terms and conditions of the unit's operating license, NRC regulations, and the unit's UFSAR.
l 2.2.8 Procedure 4
f A set of formal instructions used to implement a process or activity.
i) 2.2.9 Program j
Programs that address generic solutions for nuclear units and evolving industry issues in i
accordance with NGP 2.32, Engineering Programs.
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'$l 2.2.10 Vertical Slice Review Team (VSRT)
The team assigned to perform the vertical slice review described in this Pl.
2.3 Team Responsibilities 2.3.1 The VSRT Project Manager reports to the NU Director of Nuclear Design Engineering and Program Services and has overall responsibility for the quality, schedule, and l
administrative aspects of this review. The team leaders report to the Project Manager and have responsibility for the systems reviews assigned to their teams by the Project j
- Manager, 3.0 Instructions I
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3.1 System Reviews 3.1.1 For each system listed in Section 1.3.1, the assigned systems review ter.m shall complete a matrix of system attributes to be reviewed against plant documents and programs for the
$I following three (3) areas: Design Bases Consistency, Licensing Basis Consistency, and Plant Documentation. Attachment 5.1 is an example of the form used for these matrices and illustrates the plant documents and program areas included in each vertical slice j
system review When completed, these matrices provide the summary basis for a vertical
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slice system review.
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The review team will select key system attributes appropriate to the specific system being reviewed on the basis ofimportance to the safety-related system design bases. Attributes will be selected from the following parts of the Design Control Manual NUC DCM:
- Design Inputs, Attachment 4-1 i
- Interdiscipline Review Engineering Evaluations, i
FORMS 4-1C through 4-1F l
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- Interdiscipline Review Evaluations for Engineering Programs, FORMS 4-1G through 4-1M
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- The Management Quality Committee (MQC) must approve the attributes l
selected by the VSRT prior to commencing the system reviews.
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The following activities are associated with completing these matrices.
i 3.1.2 Document retrieval: For each system attribute to be evaluated, request the retrieval of the i
necessary documents by completing the "1996 MPR Assessment-MP3" form, i.2.- Attachment 5.3 is an example of a completed document request form.
l These forms are input to an NU computerized database for future retrieval, if necessary.
g, A completed, computer generated form will be retumed to the requester when the 3
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documentation is retrieved.
j 3.1.3 System attribute evaluation: For each system attribute the systems review team member assigned will document positive and negative comments and/or observations of the i
evaluation on an Attachment 5.2 form. An example of a completed system attribute i
evaluation is shown in Attachment 5.4. Potential discrepancies which require safety significance screening shall be indicated on this form as shown and processed in accordance with Section 3.3 of this Project Instruction.
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3.1.4 The NU team coordinator shall prepare and update a database of all MPR Assessment Request Forms prepared in accordance with subsections 3.1.2 and 3.1.3 above.
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j 3.1.5 Each system review team shall update the appropriate system review matrix as the j
evaluation process continues.
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3.2 Information Sources
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Information sources and data bases should be queried to obtain information on past and i
present status of the system attributes being reviewed. This information will be part of (l
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what is used to make ajudgment on design basis validity, configuration management and 5
I ultimately for readiness-for-startup. Information can be e%ined on Adverse Condition l
Reports (ACRs), Non-Conformance Reports (NCRs), outstuding maintenance and engineering work items on two Network-based data bases. Examples ofinformation sources are below, but additional sources may be used.
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3.2.1 Action Item Tracking and Trending System (AITTS)
An overview and description of this data base can be accessed via the Network Navigator.
CAUTION: This database is mostly complete and in-use, but in some cases (sub-categories) may be in the process of startup.
The AITIS contains historical and up-to-date information or. : ACRs, Bypass & Juniper Logs, LERs, DCNs, Engineering Work Requests (EWRs), Set Point Change Requests, and QA records, and may be sorted by system, date, etc.
l fi 3.2.2 Plant Maintenance Management System (PMMS)
This data base is a separate data base containing maintenance issues and is accessed via the Network.
3.2.3 Non-Conformance Reports (NCRs)
This historical and real-time database is accessed via the Network, but is on the mainfmme database system; it contains historical NCRs, dispositions and current outstanding requests.
3.2.4 Plant Design Change Records (PDCRs)
This is a hard-copy system maintained by MP-3 staff.
3.2.5 Plant Operational Records This data is contened in both the AITTS and on hard copy records contained in the i s control room.
3.2.6 Generation Records Information Tracking System (GRITS)
This system includes information on drawings, DCNs, etc.
l 3.3 Screening of Discrepancies l
l 3.3.1 All discrepancies identified during the review process shall be tagged during the data collection and evaluation process by indicating in the checkoff box on the data collection form that there is a " DISCREPANCY IDENTIFIED". This will trigger the (I
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process to ensure this item gets further review by the Team Leader for that system.
3.3.2 For each assessment item that indicates " DISCREPANCY IDENTIFIED", the cognizant i
Team Leader shall complete a Discrepancy Screening Form (see Attachment 5.5).
i The purpose of the screening is to identify those items that have potential safety p;
significance for expedited turnover as described in 3.3.3 below.
NOTE: The term " potential safety significance"is intended only to expedite review by NU, and is not intended to imply a level of safety significance.
3.3.3 Upon completion, the Discrepancy Screening Form shall be forwarded to the ANSI Lead Auditor for a review of document consistency and completeness and, agreement with the Team Leader's determination. The Lead Auditor shall initial on the form to indicate concurrence and the form shall be provided to the NU Unit Project Manager for gI preparation of an Unresolved item Report in accordance with PI 5.
4 3.4 Scope Expansion If NU determines that the vertical slice review has identified safety / operability significant discrepancies, or if other problems symptomatic of new process weaknesses not
$l previously identified are found, the reviews will be expanded to include additional vertical and/or horizontal reviews, as appropriate, to further test the process weakness l
identified by the discrepancy. For example, these areas could include FSAR updating, drawing control,50.59 process, etc. The specific criteria for the expansion are dependent on the nature of the finding and will be determined by the review team leaders and approved by the Project Manager and the MQC. If no additional significant discrepancies are found in the expanded reviews, the initial discrepancy will be considered an isolated error.
3.5 Characteristics of Review Results.
In order to facilitate evaluation of review results, general guidance for sorting these p
results is provided in Attachment 5.6.
3.6 Walkdowns 3.6.1 General For the systems listed in subsection 1.3.1, the System Reviewer shall perform a system general area walkdown and/or one or more directed system walkdowns b
A system general area walkdown is performed by VSRT members assisted as necessary by a team of qualified designers. These walkdowns do not require advance preparationof l
attribute check lists but are based on the VSRT reviewers' general system knowledge (see 7
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l section 2.1) and on MP3 specific knowledge derived from the VSRT review of design, l
licensing, and operations and maintenance documents.
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Directed system walkdowns are performed by a team of qualified designeriin l
accordance with written direction from VSRT members to verify specific physical plant l
characteristics, data and attributes. The objective of this walkdown is to verify the design l
basis and licensing basis linkage to the as-built configuration. The System Reviewer will l
select key system attributes appropriate to the specific system and appropriate for field l
verification on the basis ofimportance to the safety-related system design bases. For example, component nameplate data and serial number would be appropriate for field verification, but system flow rate could not be verified by field walkdown. Attributes will be selected from the following parts of the Design Control Manual NUC DCM:
- Design Inputs, Attachment 4-1 4
- Interdiscipline Review Engineering Evaluations, FORMS 4-lC through 4-lF
- Interdiscipline Review Evaluations for Engineering Programs, FORMS 4-1G through 4-1M The required characteristics and data will be summarized on a "1996 MPR Assessment -
MP3" form (Attachment 5.2). The form will be provided to the team of qualified gl designers for performance of the directed walkdown(s).
If safety / operability significant discrepancies are found by the walkdowns, the number of key attributes for field verification will be expanded for the systems listed in subsection 1.3.1. If additional scope expansion is considered necessary by the review team leaders, the guidelines of Section 3.4 will apply.
3.6.2 A review will be performed to confirm the as-designed-to-as-built linkage. Under the supervision of the Project Manager of the VSRT, a team of qualified designers will walkdown PDCRs selected as part of the system readiness review performed in accordance with PI 5 down to the component level (such as solenoids, limit switches, g[
instrument hook-ups, wiring configuration, etc.) to confirm the as-designed-to-as built linkage. The MQC must approve the list of selected PDCRs prior to the walkdowns. (It I
is noted that the SRT will be confirming the as-desianed confieuration and the FSAR linkage in accordance with PI 4.)
l 3.6.3 The "1996 MPR Assessment - MP3"(Attachment 5.2) form shall be used to record i
the results of the walkdowns. Walkdown results will also be summarized in the VSRT
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Report (see 3.8) and presented to the MQC for approval to ensure that the completed
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i walkdown scopes are sufficient to satisfy the objectives of the vertical slice review.
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3.7 Communications 3.7.1 Intemal communications are defined as team to team communications and -
communications between the teams and the assigned NU coordinator. Intemal communications will be facilitated by brief meetings at the end of each work day to highlight in-process review results and overall review progress.
3.7.2 Extemal communications are defined as communications between team members and NU provide daily briefings to NU management and oversight representatives on review team progress.
3.8 Deliverables 3.8.1 The deliverable for this system review will be a technical reports. Attachment 5.7 provides a typical outline for this report. This report will be transmitted to the Project Manager for incorporation into the final Project report.
4.0 Reviews 4.4 Internal Reviews Intemal reviews will be conducted by a qualified ANSI Lead Auditor. These reviews will provide additional assurance that team activities are conducted in accordance with thisPl.
4.5 External Reviews Extemal reviews will be conducted by NU oversight organization representatives as assigned by NU management.
5.0 Attachments 5.1 Example System Review Matrix 5.2 Example 1996 MPR Assessment - MP3 (Vertical Slice) Form 5.3 Example of Completed 1996 MPR Assessment - MP3 (Vertical Slice) Form (Document Request) l 5.4 Example of Completed 1996 MPR Assessment - MP3 (Vertical Slice) Form l
(Review Results) 9
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0 5.5 Example Discrepancy Screening Form 5.6 Categorization of Review Results 5.7 Typical System Specific Report Outline
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6.0 References 6.1 Memo NE-96-SAB-115 from S.D. Weerakkody to J.M. Vargas dated May 1, 1996.
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- .1 Example System Review Matrix l
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..2 Example 1996 MPR Assessment MP3 (Vertical Slice) Form B
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1996 MPR ASSESSMENT - MP3 (Vertical Slice)
ITEM
] Site UNIT:
1 2
3 NUMBER REVIEWER:
REVIEWER I
I (Please Print)
NUMBER TOPICS:
Document Service Water O Residua 1 Heat Removal Information QSS/RSS Q PZR '
Safety Relief Valve Meeting R ReactorTrip Breakers U Other:
CDMput U Auxiliary Feedwater including ESFAS & AMSAC for AFW On Site AC Power O walkdown DC Power D W App.B Control Bldg Filtration / Ventilation ATTRIBUTE NO. I I
ISSUE:
NARRATION:
DISCREPANCY!DENTLFIED: O DOCUMENTATION ATTACHED:
YES NOl l
RECEIVED BY:
DATE:
TIME:
AS$1GNED TO:
PoRW4eendwrinen j
e.3 Example of Completed 1996 MPR Assessment - MP3 (Vertical Slice)
Form (Document Request) d I
1996 MPR ASSESSMENT-MP3 (Vertical Slice)
] 1 ] 2 { 3 ] Site UNIT:
NUMBER EXAMLE T
/// T6 (Please Print)
NUMBER I
I REVIEWER
'IOPICS:
Doc 6 ment 3 Service Water Information QSS/RSS ResidualHeat Removal PZR Safety RelicfValve Meeting Reactor Trip Breakm Other:
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Auxiliary Feedwater including ESFAS & AMSAC for AFW DWalkdown p
O W App.B i
ControlBidsFiltrationNentilation ATTRIBUTE NO. I l
ISSUE:
YS T6/+1
/AF02n1At/on @OES*T*
NARRATION:
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I DISCREFANCYIDEN71FIED: O DOCUMENTATIONATTACMED:
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..4 Example of Completed 1996 MPR Assessment - MP3 (Vertical Slice)
Forms (Review Results)
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l 1996 MPR ASSESSMENT-MP3 (Vertical Slice)
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Site
- SAMfLL NUMBER REVIEWER (Please Print)
NUMBER SEO I I TOPICS:
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q Docament Service Water O Resid'ual, Heat Removal Information QSS/RSS QPZR SafetyRelicfValve Reactor Trip Breakers LJ Other:
)desting i
ggg Auxiliary Feedwater including ESFAS & AMSAC for AFW D Walkdown D W App.B i_) Contrp1 Bldg Filtration / Ventilation ATTRIBUTE NO. ISWP CSI ISSUE:
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&sessss AuAs.1 sis NARRATION:
D oco m s urs & / M D infa FSAR seertouS 5 7/1H0 3.'f L.
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..5 Example Discrepancy Screening Form l
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1996 MPR ASSESSMENT-MP3 (VERTICAL SLICE)
Screening Form REVIEWER NO.:
TEAM LEADER:
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. Safety Significance Review Could the lasue involve an actual or potential:
O Yes O No Personnel, environmental, or equipment safety hazard?
O ves O No Operability or reportablilty conoem?
e' Oyes O No Adverse impact on the unit?
NOTES:
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Eased on the above information, this information O should O should not be forwarded to the plant for further review and consideration.
This bsue is determined to be:
O Potentially Significant O Not Significant QA REVIEW:
DOCUMENTATION ATTACHED: O YEs O NO ine.VDete RECEIVED BY:
DATE TIME ASS 10NED TO:
RESOLVED:
RESPONSE
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This item is considered closed.
.0 1.6 Categorization of Review Results 1
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CATEGORIZATION OF REVIEW RESULTS The results of all system reviews will be sorted in the manner described in this attachinent.
1.
The process described in this attachment applies to all system review results.. Specifically, a review result is defined as either a determination that a specific review action did not identify any potential deficiencies (i.e. a " positive" result) or a determination that the review action identified one or more potential deficiencies.
2.
The results of all system reviews performed in accordance with the matrices in Attachment 5.1 as well as reviews of previous inspection / audit results and of previously recorded open item reports such as ACRs, LERs, DCNs will be sorted into 3 major categories:
-A. Current Configuration
-B. Administrative Programs
-C. Training These categories were selected to conform to similar categories in the ACR 7007 Event Response Team Report.
3.
After sorting all review results into the 3 major categories described in paragraph 2, above, the results are fmther subdivided into subcategories. These subcategories have been selected based on the results of earlier reviews and are intended to assist in analyzing the review results. The following listing relates the appropriate subcategories for each major category.
Category A. Current Configuration A. I.
Design basis A.2.
Key document (FSAR, DBDPs, Technical Specifications, Ops critical drawings)
A.3.
Design details / Design implementation A.4.
Regulatory program compliance A.5.
Physical configuration A.6 Operations (ops, LCOs, Surveillance tests and inspections)
Category B. Administrative Programs B.1 Design Control and Configuration Management Processes (PDCRs, DCNs)
B.2.
Maintenance / resting (Open Work authorizations / backlog, Calibration program, Surveillance Testing)
B.3.
Corrective Action (ACRs, LERs)
B.4.
Licensing commitment tracking system B.5 Operations / Procedures
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c Category C. Training C.I. Industry and Internal Issues C.2. General Training l
4.
After sorting the review results into the categories and subcategories described in paragraphs 2. and 3. above, review results will be divided into those which did not identify any problems (positive results) and those which indicate a potential deficiency. Potential deficiencies within each category and subcategory will then be sorted to indicate the probable contributing factors. These contributing factors will be selected from the following list:
- a. inadequate training l
- b. attention to detail c.non retrievable information
- d. inadequate supervision
- e. material defect l
- f. insufficient resources (management)
- g. human error
- h. procedure inadequacy
- i. procedure noncompliance
- j. incomplete engineering
- k. acceptance of nonconforming condition 5.
The sorted review results will be maintained in a database for use in preparing the final report.
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NUC PI 16 s.
Rev.O This Project Instruction (PI) is part of implementation of the Configuration Management Plan (CMP) royal Effective s
Mtg. No.
Apdate Date l
Millstone SORC g.g y g 3,g CY PORC l
MP1PORC MP2 PORC i
MP3 PORC 1
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Level of Use J. Haseltine lnformation Subject Matter Expert:
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1 Licensing Basis and Design Bases Walkdowns,
i TABLE OF CONTENTS i
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- 1...
IN STRU CTI O N S..............................................
2 1.1 Establishing Walkdown Teams..............................
3 1.2 Walkdown Process........................................
4 l
1.3 Inspection Ite ms..........................................
5 l
1.4 D iscrep an cie s............................................
6 2.
R EFERE NCES................................................
7 3.
C O M M IT MENTS..............................................
7 l
4.
S UMMARY OF CHANGES.....................................
7 t
i ATTACHMENTS AND FORMS, "LB and DB Walkdown Checklist"....................
8 j, " Additional Walkdown Checklist"..................... 12 l i l
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i
- 1. INSTRUCTIONS The intent of this Project Instruction is to perform Licensing Basis (LB) and Design Bases (DB) walkdowns for systems identified in the unit-specific CMP Implementation Plans. Attachment 11 of the CMP outlines the interrelationships and interfaces among this PI and the following PIs:
NUC PI 6," Licensing Reviews" NUC PI 7," Graded System Reviews" NUC PI 8," Plant Verification and Readiness Team" NUC PI 14," Project Process Administration" NUC PI 6 and this PI function as key inputs to NUC PI 7. NUC PI 14 outlines the tracking and resolution of discrepancies noted during any of the PI-related activities. NUC PI 8 interfaces with NUC PI 7 on an iterative basis to provide a system package that documents the system LB and DB.
This PI provides guidance on the attributes to be investigated during the walkdown process and the documents necessary to record the walkdown results.
Applicable system attributes provided by NUC PI 7, " Graded System Reviews,"
shall be utilized in the walkdowns.
Certain conditions may restrict accessibility for inspection. Also,it is not-expected that component disassembly would normally be required to perform the v*nikdowns required by this PI. Consideration should be given to ALARA issues, safety, und plant conditions. Any such restrictions on inspection performance are documented.
A k
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1.1 Establishing Walkdomi Teams
~
.RT Leader I
1.1.1 ASSEMBLE walkdown team that typically includes the following:
l
~
System Engineer (SRT Leader)
Design Engineer l
l Designer (as needed)
Maintenance and Operations personnel (as needed)
NOTE The SRT Leader and Design Engineer have completed initial engineering c ualifications. Based upon their current job descriation and assigned duties and responsibilities, they are generally quali5ed to perform walkdowns. Specific training in the CMP Malkdown Process will ensure their ability to meet PI objectives. Other team members, as assigned, j
require only those skill sets related to their specific job descriptions.
lUPM l
1.1.2 VERIFY walkdown team is trained and qualified in those skill sets related to their specific job descriptions for this PI.
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i 1.2 Walkdown Process i
This section outlines the general approach to the walkdown process.
l' I
Inspection items to be addressed throughout walkdowns are contained in i and Attachment 2.
l l SRT Leader
[
1.2.1 DETERMINE approach to be used to perform walkdown, either:
I Focus on where to start walkdown, considering major system components and (if applicable)long-standingissues.
Entire Walkdown Team performs preliminary walkdown to identify discrepancies.
Smaller groups within the Walkdown Team perform a series
=
of walkdowns, with each walkdown having a particular focus.
l 1.2.2 DOCUMENT results of each walkdown (including any access l
walkdown Team restrictions or other issues impacting the inspection, or any deficiencies noted) on applicable form as specified in step 1.3.2:
IE LB or DB walkdown: Attachment 1 IE additional attributes from NUC PI 7 require walkdown:
' SRT Leader l
1.2.3 REVIEW walkdown findings.
1.2.4 IE any discrepancies are identified, PERFORM the following for each discrepancy:
a.
DEVELOP recommended resolution.
b.
Refer To Section 1.4.
1.2.5 RETURN copy of completed Attachment 1 and Atta'chment 2 (with any discrepancy resolutions) to the NUC PI 7 System Team.
1.2.6 FILE original walkdown attachments in System Walkdown file.
l A
A A
A NUC PI 16 Level of USe a-- _a_._et AL_.
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1.3 Inspection Items
\\
NOTE 1.
The NUC PI 7 System Team normally determines which Attachment 1 or Attachment 2 items are to be checked by the SRT (and the the UPM or SRT Leader may appropriate acceptance criteria), but,tems.
a so designate additional mspection i There is no "R" (i,nspection required) column on Attachment 2, since 2.
inspection is required for any inspection attribute noted.
Refer To Attachment 1 and PLACE check marN in the "
{ SRT Leader l
1.3.1 column for each item required to be inspected.
IE any required inspection attribute is not shown, Refer To
- a. and RECORD attribute information.
NOTE For the purposes of this PI, any inspection item marked "Unsat" or 1.
"N/I" is treated as a discrepancy.
2.
Inspections may be performed in any order.
Reasons recorded in the " Notes" section for discrepancies are " keyed" I
3.
to the inspection item by noting the inspection category designator, followed by the specific item number. Example: On Attachment 1, a pump seal or packing discrepancy is coded "C3," and a specific reason for "Unsat" or "N/I', status is recorded.
INSPECT each required item and DOCUMENT inspection results 1.3.2 on Attachment 1 or Attachment 2 (as applicable) as follows:
Walkdown Team 1E no discrepancy is noted, CHECK " Sat."
IE a discrepancy is noted, CHECK "Unsat."
IE inspection item does not apply to the inspection in progress, CHECK "N/A."
IE inspection item is not accessible or inspected, CHECK "N/I."
IE any inspection item is checked "Unsat" or "N/I," RECORD 1.3.3 reason for discrepancy in the " Notes" section of the applicable form.
1.3.4 ROUTE completed checklists to SRT Leader for review as specified in step 1.2.3.
4 4
A I
NUC PI 16
,gy Qgr wg7QE7 Rev.0 Level of Use lnformation jA;
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j;p JMN 5 of 12
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1.4 Discrepancies e
NOTE Deficiencies are tracked and remain as open items until resolved.
Resolution of discrepancies is addressed m NUC PI 14," Project Process Administration."
lUPM l
1.4.1 IE required, Refer To applicable procedure and INITIATE an ACR for each applicable discrepancy:
RP-4," Adverse Condition Resolution Program"
=
(for Millstone)
ACP 1.2-16.5," Adverse Condition Report Process Implementation" (for Connecticut Yankee) i
(
1 I
A h
A A
NUC PI16 Level of Use
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" THINK'
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6 of 12 2-i 1
l
- 2. REFERENCES 2.1 Configuration Management Plan (CMP)
~
2.2 System Engineer Handbook Section 6.4,"Walkdown Guidelines" 2.3 RP-4," Adverse Condition Resolution Program" (for Millstone) 2.4 ACP 1.2-16.5," Adverse Condition Report Process implementation" (for Connecticut Yankee) 2.5 NUC PI 6, " Licensing Reviews" 2.6 NUC PI 7," Graded System Reviews" 2.7 NUC PI 8," Plant Verification and Readiness Team" 2.8 NUC PI 14," Project Process Administration"
- 3. COMMITMENTS None
- 4.
SUMMARY
OF CHANGES 4.1 OriginalIssue l
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NUC PI16
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AtlaCnfllellt i LB and DB Walkdown Checklist (Sheet 1 of 4)
'R Item Inspection Results Sat Unsat N/A N/I A All Equipment:
1.
Labeling and component identification installed and correct.
2.
Equipment covers and safety guards installed.
3.
As appropriate, equipment operation access platforms installed.
4.
Manufacturer's equipment tags and name plates installed and legible.
5: Bolting tight with proper hardware installed.
6.
General component installation per design drawings.
7.
Components installed in a manner that provides access for operation and maintenance, and does not present a personnel safety hazard.
8.
Existing components, systems, or structures undamaged.
9.
Construction debris removed and proper cleanliness level established.
B Valves:
1.
Valve glands and packinginstalled.
2.
Live load packing adjusted per manufacturer's recommendations.
1 i
3.
Pressure relief / safety valve / rupture disk settings per design (as indicated on f
attached valve tags).
4.
Pressure relief / safety valve / rupture disk discharge piping properly secured and discharge flow directed in a safe manner.
S.
Valve orientation correct (including check valves and non-return valves).
6.
Valve hand wheels installed.
7.
Manualvalves have sufficient clearance to be operated.
8.
Locking device provided for those valves / breakers / switches required to be locked in a certain position.
9.
Valves have manufacturer's labels and/or tags installed.
- 10. Solenoid valves installed with correct porting.
- 11. Solenoid valves have proper voltage rating.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
A l
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NUC PI 16 Level of USe
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LB and DB Walkdown Checklist (Sheet 2 of 4)
.R Item Inspection Results Sat Unsat N/A N/I C
Pumps, Fans, Compressors:
1.
Pumps, fans, compressors aligned and coupled; coupling guards installed.
- 2. ' Pumps and fans oriented correctly.
3.
Pump seals and packing installed.
4.
Pump seal or bearing cooling lines installed.
- 5. -Pump sealleakofflines or baseplate drain lines installed.
D Mounting and Supports:
1.
Equipment mounting bolts installed and tight.
2.
As required, equipment base plate grouted.
3.
Bolts and concrete anchors have thread engagement per design requirements.
4.
Pipe hangers, conduit supports, cable tray supports, and instrument line supports installed per design requirements.
5.
Support and hanger accessories (clips, U-bolts, etc.) installed per design requirements.
6.
Snubbers installed per design requirements and setpoints verified.
7.
Hanger spring cans installed and adjusted per design requirements.
,i 8.
Adjustable struts installed and adjusted per design requirements.
9.
Seismic anchors and restraints installed per design requirements.
- 10. Temporary supports removed.
E Instrument:
1.
Instrument sensing lines connected per design requirements and are tight.
2.
Equipment mounted instrumentation insta!!ed per design requirements.
3.
Physical protection for instrumentation installed per design requirements.
4.
Instrument tubing and fittings installed per design requirements.
5.
Surge suppressors for instrumentation installed per design requirements.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
[
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(Sheet 3 of 4)
R Item Inspection Results Sat Unsat N/A N/I F
Electrical Equipment:
1.
Electrical Environmental Qualification (EEQ) related equipment installed per design requirements.
2.
Electrical equipment, raceway, and cable installed to electrical design requirements.
3.,
Electrical connections made up and tight.
4.
Panelwiring neat and orderly.
5.
Conductor identification tags installed.
6.
Train separation per design requirements.
7.
Cable tray wiring neat and orderly.
8.
Permanently lifted or abandoned lead marked and documented.
9.
Mechanical protective devices for electrical conductors installed per design requirements.
G lleat Tracing, Insulation, Painting:
1.
Heat tracing installed per design requirements.
2.
Painting and other protective surface coatings satisfactorily installed.
3.
Insulation installed per design requirements.
II HVAC Equipment:
1.
Ventilation system filters and absorber units installed and properly oriented.
2.
Fire dampers properly oriented and installed.
3.
Fusible links of the proper temperature range installed.
4.
Ductwork access doors installed.
5.
Equipment condensation drains installed.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
I A
6 NUC PI 16 Level of USe
,ab _A,' v% ACTA 7.m' REVIEW Rev. O s.
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LB and DB Walkdown Checklist (Sheet 4 of 4)
IR Item Inspection Results
- Sat Unsat N/A N/I I
Piping:
1.
Restricting orifices and flow elements installed.
2.
Flow elements oriented correctly.
3.
Fi 'id system permanent filters installed.
4.
Startup 'ilters or strainers installed and identified.
5:.Permaner t piping spool pieces (to replace startup filters or strainers) are available tor installation.
6.
Original material / weld identification numbers are legible.
7.
Welding dams or purge paper used during piping installation removed or identified (so they can be removed after turnover).
8.
Temporary vent paths used for welding (i.e., valve bonnet or check valve intervals removed) have been restored.
9.
Fire barriers, cable tray separators and covers, and other fire protection features / equipment installed per Design requirements.
- 10. Security barriers and other physical security measures properly installed.
These attributes to be verified during walkdown by a representative of the Station Security Department J
Lubrication 1.
Lubrication reservoirs installed and at proper operating level.
2.
Equipment properly lubricated and lubrication records available.
K Cathodic Protection 1.
Cathodic protection installed per design requirements.
2.
Insulating Danges installed per design requirements.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
Walkdown
Participants:
l F
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a SE:
Date:
Supervisor:
Date:
^
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Additional Walkdown Checidist (Sheet 1 of 1) 4 Date:
Time:
System:
Inspection Results
- R Sat Unsat N/A N/I L
Inspection Attribute
)
l I.
2.
3 3 4.
5.
6.
i 7.
8.
9.
l 10.
11.
i 12.
l 13.
14.
15.
16.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
Walkdown
Participants:
i l
Date:
,l SE:
Date:
Supervisor:
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NUC PI 16 5
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NORTnEAST UTILITIES NUCLEAR CY NU COMMON PROCEDURE UP 1
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Procedure Basis Document Licensing Basis and Design Bases Walkdowns NUC PI 16 Rev.O This Project Instruction (PI) is part of implementation of the Configuration Mar.agement Plan (CMP).
Responsible Individual:
Basis J. Haseltine Document Subject Matter Expert:
' -l J. Haseltine
MP1, MP2, MP3, CY NU Common Procedure Licensing Basis and Design Bases Walkdowns TABLE OF CONTENTS 1.
INSTRUCTIONS..............
2 1.1 Establishing Walkdown Teams.......................
3 1.2 Walkdown Process............
4 1.3 Inspection Ite ms...................................
5 1.4 Discrepancies...........
.6 2.
REFERENCES...
7 3.
COMMITMENTS.........
.7 4.
SUMMARY
OF CHANGES.
7 ATTACHMENTS AND FORMS, "LB and DB Walkdown Checklist" 8
., " Additional Walkdown Checklist"..
12 i
l 1
NUC PI 16 Basis Document Rev.0 l
l of 12
- 1. INSTRUCTIONS The intent of this Project Instruction is to perform Licensing Basis (LB) and Design Bases (DB) walkdowns for systems identified in the unit-specific CMP Implementation Plans.
This PI provides guidance on the attributes to be investigated during the walkdown process and the documents necessary to record the walkdown results. Applicable
. system attributes provided by NUC PI 7, " Graded System Reviews," shall be
- utilized in the walkdowns.
Certain conditions may restrict accessibility for inspection. Consideration should be given to ALARA issues, safety, and plant conditions. Any such restrictions on
~
inspection performance are documented.
t NUC PI 16 Basis Document Rev.0 2 of 12 t
a
1.1 Establishing Walkdown Teams l SRT Leader l
1.1.1 ASSEMBLE walkdown team that typically includes the following:
System Engineer (SRT Leader)
Design Engineer Designer (as needed)
Maintenance and Operations personnel (as needed) v
=
NOTE The SRT Leader and Design Engineer have completed initial engineering c ualifications. Based upon their current job description and assigned c uties and responsibilities, they are generally qualified to perform walkdowns. Specific training in the CMP Walkdown Process will ensure their ability to meet PI objectives. Other team members, as assigned, require only those skill sets related to their specific job descriptions.
lUPM j"
1.1.2 VERIFY walkdown team is trained and qualified in those skill sets related to their specificjob descriptions for this Pl.
I i
l l
r I
NUC PI 16 f
l Basis Rev. 0 Document f
I 3 0f 12 i
I
1.2 Walkdown Process This section outlines the general approach to the walkdown process.
Inspection items to be addressed throughout walkdowns are contained in
- and Attachment 2.
[ SRT Leader l
1.2.1 DETERMINE approach to be used to perform walkdown, either:
Focus on where to start walkdown, considering major system components and (if applicable)long-standing issues.
Entire Walkdown Team performs preliminary walkdown to identify discrepancies.
Smaller groups within the Walkdown Team perform a series of walkdowns, with each walkdown having a particular focus.
Watkdown 1.2.2 DOCUMENT results of each walkdown (including any access Team restrictions or other issues impacting the inspection, or any deficiencies noted) on applicable form as specified in step 1.3.2:
JE LB or DB walkdown: Attachment 1 IE additional attributes from NUC PI 7 require walkdown:
l SRT Leader l
1.2.3 REVIEW walkdown findings.
~
1.2.4 IE any discrepancies are identified, PERFORM the following for each discrepancy:
a.
DEVELOP recommended resolution, b.
Refer To Section 1.4.
1.2.5 RETURN copy of completed Attachment 1 and Attachment 2 (with any discrepancy resolutions) to the NUC PI 7 System Team.
1.2.6 FILE original walkdown attachments in System Walkdown file.
NUC PI 16 Basis Rev. 0 Document 4 of 12
l l
1.3 Inspection Items I.
NOTE 1.
The NUC PI 7 System Team normally determines which Attachment 1 or Attachment 2 items are to be checked by the SRT, but the SRT Leader may also designate additional inspection items.
2.
There i,s no,"R" (inspection re, quired) column on Attachment 2, since mspection is required for any mspection attribute noted.
u l SRT Leader l
1.3.1 Refer To Attachment 1 and PLACE check mark in the "R" l
column for each item required to be inspected.
E any required inspection attribute is not shown, Refer To
- a. and RECORD attribute information.
I NOTE l
l 1.
For the purposes of this PI, any inspection item marked "Unsat" or "N/I" is treated as a discrepancy.
2.
Inspections may be performed in any order.
3.
Reasons recorded in the " Notes" section for discrepancies are " keyed" to the ins acetion item by noting the inspection category designator, followed by the specific item number. Example: On Attachment 1, a pump seal or packin~g ' discrepancy is coded "C3," and a sp~ecific reason for "Unsat" or "N/I" status is recorded.
l l
walkdown 1.3.2 INSPECT each required item and DOCUMENT inspection results l
Tearn on Attachment 1 or Attachment 2 (as applicable) as follows:
E no discrepancy is noted, CHECK " Sat."
l E a discrepancy is noted, CHECK "Unsat."
E inspection item does not apply to the inspection in progress,
=
j CHECK "N/A."
E inspection item is not accessible or inspected, CHECK "N/I."
=
1.3.3 E any inspection item is checked "Unsat" or "N/I," RECORD reason for discrepancy in the " Notes" section of the applicable form.
i 1.3.4 ROUTE completed checklists to SRT Leader for review.
NUC PI 16 Basis Rev.0 Document S of 12 j
l
1 1.4 Discrepancies lupu j"
1.4.1.
IE required, Refer To applicable procedure and INITIATE an ACR for each applicable discrepancy:
RP-4," Adverse Condition Resolution Program" (for Millstone)
ACP 1.2-16.5," Adverse Condition Report Process i
Implementation" (for Connecticut Yankee) l l
i I
l l
l l
1 NUC PI 16 Basis Rev.0 Document I
6of12 1
- 2. REFERENCES 2.1 Configuration Management Plan (CMP) 2.2. System Engineer Handbook Section 6.4, "Walkdown Guidelines" 2.3 RP-4, " Adverse Condition Resolution Program" (for Millstone) 2 ACP 1.2 16.5, " Adverse Condition Report Process Implementation" 2.4 (for Connecticut Yankee) j 2.5 NUC PI 7," Graded System Reviews"
- 3. COMMITMENTS None
- 4. S_UMMARY OF CHANGES 4.1 Original Issue NUC PI 16 asts Rev. O Document j
7 of 12
LB and DB Walkdown Checklist (Sheet 1 of 4)
R Item Inspection Results l
A All Equipment:
Sat Unsat N/A N/I l
- 1., Labeling and component identification installed and correct.
2.
Equipment covers and safety guards installed.
l 3.
As appropriate, equipment operation access platforms installed.
- 4. Jianufacturer's equipment tags and name plates installed and legible.
5.
Bolting tight with proper hardware installed.
6.
General component installation per design drawings.
7.
Components installed in a manner that provides access for operation and maintenance, and does not present a personnel safety hazard.
8.
Existing components, systems, or structures undamaged.
9.
Construction debris removed and proper cleanliness level established.
B Valves:
1.
Valve glands and packing installed.
2.
Live load packing adjusted per manufacturer's recommendations.
3.
Pressure relief / safety valve / rupture disk settings per design (as indicated on attached valve tags).
4.
Pressure relief / safety valve / rupture disk discharge piping properly secured i
and discharge flow directed in a safe manner.
~
5.
Valve orientation correct (including check valves and non-return valves).'
6.
Wlve hand wheels installed.
7.
Manual valves have sufficient clearance to be operated.
8.
Locking device provided for those valves / breakers / switches required to be locked in a certain position.
9.
Wlves have manufacturer's labels and/or tags installed.
- 10. Solenoid valves installed with correct porting.
- 11. Solenoid valves have proper voltage rating.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
l r
NUC PI 16 i
Basis Document Rey.0 8 of 12 LB and DB Walkdown Checidist (Sheet 2 of 4) a-R Item Inspection Results C
Pumps, Fans, Compressors:
Sat Unsat N/A N/I 1.
Pumps, fans, compressors aligned and coupled; coupling guards installed.
2.
Pumps and fans oriented correctly.
3.
Pump seals and packinginstalled.
4.
Pump seal or bearing cooling lines installed.
5.iPump seal leakoff lines or baseplate drain lines installed.
j D
Mounting and Supports:
l 1.
Equipment mounting bolts installed and tight.
2.
As required, equipment base plate grouted.
3.
Bolts and concrete anchors have thread engagement per design requirements.
4.
Pipe hangers, conduit supports, cable tray supports, and instrument line i
supports installed per design requirements.
5.
Support and hanger accessories (clips, U-bolts, etc.) installed per design requirements.
6.
Snubbers installed per design requirements and setpoints verified.
7.
Hanger spring cans installed and adjusted per design requirements.
I 8.
Adjustable struts installed and adjusted per design requirements.
9.
Seismic anchors and restraints installed per design requirements.
- 10. Temporary supports removed.
E Instrument:
1.
Instrument sensing lines connected per design requirements and are tight.
2.
Equipment mounted instrumentation installed per design requirements.
3.
Physical protection for instrumentation installed per design requirements.
4.
Instrument tubing and fittings installed per design requirements.
5.
Surge suppressors for instrumentation installed per design requirements.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
1 I
I l
NUC PI 16 Basis Rev. 0 l
Document 90f12
LB and DB Walkdown Checklist (Sheet 3 of 4)
R ltem Inspection Results F
Electrical Equipment:
Sat Unsat N/A N/I 1.
Electrical Environmental Qualification (EEQ) related equipment installed
,per design requirements.
2.
Electrical equipment, raceway, and cable installed to electrical design requirements.
3.
Electrical connections made up and tight.
- 4. ' Panel wiring neat and orderly.
5.
Conductor identification tags instaSed.
6.
Train separation per design requirements.
7.
Cable tray wiring neat and orderly.
8.
Permanently lifted or abandoned lead marked and documented.
9.
Mechanical protective devices for electrical conductors installed per design requirements.
G IIcat Tracing, Insulation, Painting:
1.
Heat tracing installed per design requirements.
2.
Painting and other protective surface coatings satisfactorily installed.
3.
Insulation installed per design requirements.
11 IIVAC Equipment:
1.
Ventilation system filters and absorber units installed and properly oriented.
2.
Fire dampers properly oriented and installed.
3.
Fusible links of the proper temperature range installed.
4.
Ductwork access doors installed.
5.
Equipment condensation drains installed.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
NUC PI 16 Bas.is Rev.0 Document 10 of 12
LB and DB Walkdown Checklist (Sheet 4 of 4)
R ltem Inspection Results
- I Piping:
Sat Unsat N/A N/I 1.
Restricting orifices and flow elements installed.
- 2.. Flow elements oriented correctly.
3.
Fluid system permanent filters installed.
4.
Startup filters or strainers installed and identified.
- 5.. Permanent piping spool pieces (to replace startup filters or strainers) are
. available for installation.
6.
Original material / weld identification numbers are legible.
7.
Welding dams or purge paper used during piping installation removed or l
identified (so they can be removed after turnover).
l 8.
Temporary vent paths used for welding (i.e., valve bonnet or check valve l
intervals removed) have been restored.
I 9.
Fire barriers, cable tray separators and covers, and other fire protection l
features / equipment installed per Design requirements.
- 10. Security barriers and other physical security measures properly installed.
These attributes to be veri 5ed during walkdown by a representative of the Station Security Department.
J Lubrication 1.
Lubrication reservoirs installed and at proper operating level.
2.
Equipment properly lubricated and lubrication records available.
K Cathodie Protection 1.
Cathodic protection installed per design requirements.
2.
Insulating flanges installed per design requirements.
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable Notes:
l 1
l i
l Walkdown
Participants:
SE:
Date:
Supervisor:
Date:
i NUC PI 16 Basis Rev.0 Document 11 of 12 l
1
1 i
Additional Walkdown Checklist (Sheet 1 of 1)
Date:
Time:
System:
1 R
Inspection Results
- l L
Inspection Attribute Sat Unsat N/A N/I 1.
2.
3.
4.
5.
6.
l 7.
l 8.
9.
i 10.
11.
l 12.
!t 13.
14.
15.
16.
l
- Sat: Satisfactory Unsat: Unsatisfactory N/A: Not Applicable N/l: Not inspectable l
Notes:
l Walkdown
Participants:
SE:
Date:
Supervisor:
Date:
NUC PI 16 Basis Document Rev. 0 12 of 12 l
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Validation Commint and Resolution Form C oMAt EdTS f R om gene w (Sheet 1 of 2) og rHln (aceco, wcarws,is.es, um) i Procedure Number:
NO W
Revision:
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Procedure
Title:
NO T6D M/LLfTbME UN IT 3 5ffTE//f &WEUS Select Flold Simulated Table Top &
Comparison Validation Not Required
- Validation Validation Performance Walk-Through u.
Method
- If a validation is not required. provide an explanation and justification on sheet 2.
l rr IE a Field Validation ** Is being performed (validation of procedure using actual plant or spare equipment), VERIFY all of the following criteria are satisfied:
Independent reviewis complete.
If required, an AWO has been prepared and includes the following in " JOB DESCRIPTION":
- PORC or SORC APPROVE PROCEDURE PRIOR TO RETEST" Post-validation testing.that demonstrates the work was completed satisfactorily and the equipment is capable of performing its intended function when returned to senice, has been.specified.
mcmnmr>ca Department Head has designated the individual who is authorized to makedvenges to the )
J
'e implemented and the ac(tionperformed, a ch). (Before am modificadons to theprocedure are j.
procedure in the field enter name below ange must be documented and authori:ed by the selected indinduct on thisform.)
Name of AuthorizedIndividual:
i The Department Head has approved the procedure for validation on actual plant or spare equipment.
Department Head Approval for Field %1idation-Date:
The equipment is removed from senice.
l The equipment isolated and tagged in accordance with ACP-OA-206A or a Safety Evaluation has been prepared indicating that op,eration of the e validated and will not cause anyinteraction with,quipment is in accordance with the procedure being or impact on, any component imponant to safety.
l One of the following methods has been selected to be used to declare the equipment operable and return the equipment to senice following the validation:
L Final PORC or SORC approval of the procedure before unisolating and retesting and j
satisfactory completion of the retest before declaring the equipment operable and returnmg at to service.
i 2.
Using a current PORC or SORC approved procedure to restore the equipment, circuit, or system to its original con:iition.
- Upon completion of the field validation of a procedure, any changes must be incorporated into the procedure and concurrence obtained from the Independent Reviewer. 'Ihe revised procedure is presented to PORC or SORC for final approval. 0 PW AW
& 4 y. spy 2 kr IE a Simula d Perforr' nance i..be g performed, VERIFY the equipment is not considere 2 lant equipmen{#as-spec!!!cd in die definMons-provMed in the V&V l
-Paceduie, Sudon 1.S.2,msOBTAIN Department Head approval.
I Department Head Approval for Simulated Performance:_
Date:
l
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]t Validation Commet nd Resolution Form (Sheet 20f 2)
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