ML20217F341

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Rev 3 to PP-01, System Vertical Slice Review
ML20217F341
Person / Time
Site: Millstone 
Issue date: 10/02/1997
From:
AFFILIATION NOT ASSIGNED
To:
Shared Package
ML20217F338 List:
References
PP-01, PP-1, NUDOCS 9710080127
Download: ML20217F341 (26)


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m PARSONS pp.01 MILLSTONE UNIT 2 ICAVP PROJECT PROCEDURES

Title:

System Vertical Slice Review i

REVISION 3 l

Date: /

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Prepared by:

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Approved by:

anag rfompany Qdality Program Approved by:

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Date: M Projepirector REVISION HISTORY REVISION DATE REVISION DESCRIPTION O

04/03/97 Procedure initiation 1

06/09/97 incorporation of NRC C,omments 2

06/27/97 incorporation of NRC Comments 3

10/2/97 Reissue as Revision 3 Incorporation of PI 01 & Sample Plan References DR DO 050 36 P

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' p MILLSTONE UNIT 2 ICAVP PP-01 PROJECT PROCEDURES

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TITL'E:

SYSTEM VERTICAL SLICE REVIEW REVislON: 3 DATE: 9'Yt*197 PAGE 2 OF 26 l

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l IABLE OF CONTENTS 1.0 PURPOSE.................................................................................................................................3

1. I B A C K G R O UN D........................................................................................................ 3 1.2APPROAClI....................................................................................,.................4 v

2.0 DEFINIT10NS.........................................................................................................................5

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3.0 P R E R E Q U l S i T ES................................................................................................................... 6 4.0 PROCEDURE.........................................................................-...............................................7 4.1 i N S P ECTI O N P RE P ARATION............................................................................. 8 4.2 CO N D U CT O F i N S P ECT10 N............................................................................. I 1 4.3 IN S PECTION ASSESShiENT AND REPORT.......................................................... I $

4.4 TEAM hiEETINGS/ REVIEW 3.........................................................

.........I8 4.5 SY STE M A S S ES S M ENT.................................................................... 17

5.0 REFERENCES

........................................................................................................................I8 APPENDiXA..................................................................................................................................19 APPENDIXH..................................................................................................................................22 APPENDIXC.................................................................................................................................23 APPENDIXD....................................................................................................................................25

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PROJECT PROCEDURES TITI'E:

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1.0 PURPOSE His procedure establishes the overall objectives, scope, and general approach for conducting the System Vertical Slice Review (SVSR) for Millstone Unit 2. De purpose of the SYSR is to con"rm that the selected system's physical and functional characteristics are in confonnance with its licensing and design bases. %e SYSR will proside independent verification, beyond Millstone Unit 2's quality assurance and management oversight, that they have identified and satisfactorily resolved existing nonconformances with the design and licensing bases and documented and utilized the licensing and design bases to resolve nonconformances.

1.1 UACKGROUND On August 14,1996, the Nuclear Regulatory Commission (NRC) issued a Confirmatory order directing the licensec to contract with a thisd party to implement an Independent Corrective Action Verification Plan (ICAVP) to verify the adequacy ofits efforts to establish adequate design bases and design controls. He ICAVP is to employ a review of selected Millstone Unit 2 systems to provide independent verification that, for the selected systems, the Millstone Unit 2 Configuration Management Plan (CMP) has identified and resolved existing problems, documented and utilized licensing and design bases, and established programs, processes and procedures for effective configuration in the future '

De corrective action verification prognm was ordered to include:

an in <lepth review of selected systems which will address control of the design and design e

basis since issuance of the operating license for each unit; selection of systems for review based on risk / safety based criteria similar to those used in e

implementing the Maintenance Rule (10 CFR 50.65);

development and documentation of an audit plan that will provide assurance that the quality of e

results of the Licensec's problem identification and corrective action programs on the selected

.O systems is representative of and consistent with that of other systems; V

' NRC Confirmatory Order, Page 11, item 11

I ED MILLSTONE UNIT 2 ICAVP PP-01 E

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PROJECT PROCEDURES 7

TITLE:

SYSTEM VERT 10AL SLICE REVIEW REVISION: 3 DATE: 10/01/97 PAGE 4 OF 26 l

procedures and schedules for parallel reponing of fmdmgs and recommendations by the e

ICAVP team to both the NRC and the Licensee; and procedures for the ICAVP team to comment on licensee's proposed resolution of the fmdings e

and recommendations.2 He ICAVP audit will be a multi tiered approach using different and dist nct inspection methods i

for each of a total of three tiers. %is procedure covers Tier 1. In Tier 1, four systems will be inspected using a system venical slice review process to test the thoroughness of the NNECo's reviews m identifying potential nonconformances with the design and licensing bases.

1.2 APPROACil The ICAVP SVSR will review the configuration of the selected system through a combination of inspecting techniques including document rniews, calculation reviews, and plant walkdowns.

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ne SVSR will assess the CMP as it applies to the selected systems through:

a rniew of engineering design and configuration control processes; e

verification of current, as-modified plant conditions against design basis and. licensing basis e

documentation; verification that design and licensing bases requirements are translated into operating e

procedures and maintenance and test procedures; verification of system perfornance through review of test records and/or observation of testing e

of particular systems; and review of proposed and implemented corrective actions for Licensee-identified design e

deficiencies?

The SVSR will examine system related activities from original design, construction, and testing to the present system configuration.

8 NRC Confirmatory Order, Page 12, item 111 & Page 14, item IV 8 NRC Confirmatory Order, Page 13, item 111 & Page 14/15, item IV

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Any discrepancies identified during the review, coupled with the type of discrepancy and its relative importance on the structure, system or components regulatory requirements, will provide the basis for SYSR reporting.

2.0 DEFINITIONS Design Basis.. that information that identifies the specific functions to be perfonned by a structure, system, or component of a facility and the specific values or ianges of vale ; chosen for controlling parameters as reference bounds for design. These values may be (1) restraints derived from generally accepted stme-of-the-art practices for achieving functional goals or (2) requirements derived from analysis (based on calculation and/or cxperiments) of the eficcts of a postulated accident for which a structure, system, or component must meet its functional goals.*

O 1.icensing Basis, for purposes of the SYSR, the licensing basis for Millstone Unit 2 consists of e

that set ofinformation upon which the Commission, in issuing an initial operating license, based its comprehensive determination that the design, constructioa, and proposed operation of j

the facility satisfied the Commission's requirements and provided reasonable assurance of adequate protection to public health and safety and common defense and security.5 Current Licensing Basis (CLD) is the set of NRC requirements applicable to a specific plant and a licensec's written commitments for ensuring compliance with and operation within applicable NRC requirements and the plant specific design basis (including all modifications and additions to such commitments over the life of the license) that are docketed and in effect.

The CLD includes the NRC regulations contained in 10 CFR Parts 2,19,20,21,26,30,40, 50, 51, 54, 55, 70, 72, 73,100 and appendices thereto; orders, license conditions; exemptions; and technical specifications. It also includes the plant specific design-basis information defined in 10 CFR 50.2 as documented in the most recent final safety analysis report (FSAR) as required by 10 CFR 50.71 and the licensing correspondence such as licensec responses to (v

  • 10 CFR50.2 5 Source: NRC Letter of October 9,1996 On Maintaining Plant Design

1 MILLSTONE UNIT 2 ICAVP PP-01 PROJECT PROCEDURES TITLE:

SYSTEM VERTICAL SLICE REVIEW REVISION: 3 DATE: 10/02/97 PAGE 6 OF 26 l

NRC Bulletins, generic letters, and enforcement actions, as well as licensee commitments documented in NRC safety evaluations or licensec event reports.'

Engineering Design Bases (EDB) lhe set of design constraints that are not included in the e

Licensing Basis but are implemented to achieve economics oioperation, maintenance, procurement, installation, or construction. Such as:

Information that describes a system, structure, or component Operating values or parameters ' aat are not reference bounds for design Information that identifies f>ations important for economic, maintenance; installation, e

or other non-safety function of design basis systems, structures, or components information and operating values describing the functions of non-safety systems e

Calculations, descriptions, and other " outputs" e

Design Verification. The process ofindependently reviewing, confirming, or substantiating the design by one or more methods to provide assurance that the design meets the specified design criteria and design inputs. The extent of design verification may range from a detailed check of the total design to a check of the design approach and the results obtairx:d.

3.0 PREREOUISITES NRC announcement of the system (s) to be inspected e

ICAVP Audit Plan e

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' 10 CFR 54.3 (a) l

!D MILLSTONE UNIT 2 ICAVP PP-01 E

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4.0 pHOCEDURE Rumitmacishili1!u SYSR Group Leader Reviews and approves the System Specific Instructions and Checklists e

Supenises the overall SYSR Inspections e

Di octs the course of the SVSR and maintains review focus e

Periodically reviews functional plans and system review progress e

Reviews the documenting and reporting of any discrepancies noted during the review.

e SYSR System Lead Coordinates the administration of the overall system specific inspection q

e Dermes system boundaries and components to be evaluated e

NOTE Interface with, and portions of, other systems will be included within the boundary of the selectal system to the extent they are necessary to support the functional requirements of the selected system. System boundaries may be defir,ed at appropriate components that provide physical isolation, as long as the selected boundary does not split the component between systems. All passive devices such as support and restraints, within the system boundary are included within the scope of the SVSR.

Support system boundaries will be dermed as:

Mechanical the first level of support system interface.

As an example, at a heat exchanger, the interface will be data associated with the temperature and flow rate of the cooling media. We interfacing system equipment / data / design will be verified to the extent that the input parameters can be validated with respect to a verified calculation or vendor document.

Electrical - Electrical power will be verified from the actuating component or power supply to the ultimate on site source required for the component to perfomi its intended function. All selected system loads and their design parameters will be verified.

Verification will focus on the review ofloads associated with the selected j

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system. Design documents will be revinved to the level confimiing that the intended l

function can be accomplished.

Instrumentation and Control I&C will be verified from the indisidual field sensor to the component or device required to perform an intended function. Verification will include any portion of the instrument loop, power supplies, circuitry, interfacing hardware and range / set point required to assure the intended function is accomplished. The SVSR will

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concentrate on verifying (1) signals associated with the selected system, and (2) that the l

instrument loop performs its primary function. Design documents will reviewed to the level of confirming that the intended function can be accomplished.

Piping. will be reviewed to the point ofinterface with the component and/or supponing structures. Supporting stmetures will not be considered within the system boundary.

Directs the development of the system specific review instructions, checklists and observation / question fomis Dermes necessary resources to facilitate the review Provides orientation and training to team members on the approach, methodology and overall e

project expectations Reviews and approves system specific review instructions, checklists, and supplements.

e Develops a summary report of each system specific review and a comprehensive report of the inspection results SVSR Team Members Develop system specific review instructions and checklists Conduct the system reviews in accordance with this review plan and the system specific instructions and checklists Develop system specific reports and make appropriate presentations on the status of the system e

specific rniews to Team Supenision, Deputy Project Directcr, Project Director.

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E7A MILLSTONE UNIT 2 ICAVP PP-01 3-PROJECT PROCEDURES TIILEt SYSTEM VERTICAL SLICE REVIEW

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41 INSPECTION PREPARATION

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4.1.1 Staff Trainine and Mobiliration Resources Deputy Project Director SVSR Group lead Action 4.1.1.1 Assess Project personnel needs based on selected system 4.1.1.2 SYSR Group Lead revises Team discipline composition as required to cover the selected system inspection 4.1.1.3 Develop mobilization and training schedule for Deputy Project Director approval 4.1.1.4 Complete SVSR mobilization and training completed in accordance with approved schedule Action Output Trained Personnel 4,l.2 Identify System Specific inspection Scope and Documents liesources System leads System Team Members Action 4.1.2.1 Determine the selected System Inspection boundary including interfacing systems that are necessary to support the functional requirements of the selected system. Use PI-01 "SYSR 1mplementation Checklists and Workbook" to determine system boundaries.

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4.1.2.2 Identify a list of documents and other information associa j with the system. Typical information to consider:

Details of system boundaries / interfaces Identified system deficiencies or operating problems e

Regulatory documents containing requirements specific to selected system e

Modifications made to the selected system System Drawings e

Calculations System related actions from the Corrective Action Program Design changes Design Basis Documents O)

Licensing changes e

x Procedure changes e

Original design information System operational and test data Operating procedures e

Maintenance procedures e

System regulatory requirements such as emiromnental qualifications, fire protection, scismic qualific.ations NOTE:

The document list initiated in Step 4.1.2.2 will be completed for all applicable parameters and functions the team can identify for the selected system. A list of typical document types is prosided in Appendix B.

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4.1.2.3 Using the list of documents developed in Step 4.1.2.2, develop a system specific design basis and configuration management assessment checklists. Use the generic checklist framework prosided in PI-01 "SYSR implementation Checklists and Workbook".

NOTE Sampling plans may be used for selected repetitive component group cvaluations. The sample plan and its rationale will be proposed and submitted to the NRC for their review i

and oversight.

l 4.1.2.4 Deve'op h.. nf organizations (internal and external) associated with the items identified.

4.1.2.5 Deve op.che/,ile for inspecticn.

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Action Output System boundary and interface definition System specific checklist and workbook Document retrieval requirements e

Detailed Schedule for resource planning e

4.2 Conduct Of Inspection Detailed instructions to be used by the SYSR team for conduct of the inspection are provided in PI-01 "SVSR 1mplementation Checklists and Workbook". PI-01 is intended to supplement this pioject procedure. The inspection will be conducted in multiple phases, combining in-oflice document resiew and ver!Scation and in-plant walkdowns. Walkdowns will be used to obtain additional information, clarify information, verify commitments, and answer working questions.

A 100% review of the system against licensing and design bases shall be perfommd during Tier 1.

He review will include (but not be limited to) mechanical, electrical, l&C, and civil / structural requirements such as calculations, analysis, assumptions, and conclusions. Appropriate design documents and data for the selected system and the system components will be reviewed to the extent necessary to verify 100% of the selected system requirements.

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l For repetitive or identical component groups the verification will include a screening process to confirm that ac components are repetitive and identical followed by validation of the licensing or design basis requirement using a cornponent group process.

4.2.1 Evaluate Doruments l

l Resourres System Lead System Team Members A(tion 4.2.1.1 Retrieve necessary documents O

4.2.1.2 Review system documents and record the results of the evaluation. He review should determine whether:

%c system current configuration accurately reflects the licensing-bases, including the updated FSAR.

The system calculations and analyses were performed using recognized and acceptable analytical methods.

He assumptions made in any calculations or analysis supporting the change are technically sound.

The results of calculations or analysis supporting a unmodified portions of the original configuration and design changes are reasonable (based on engineering judgment) for the scope of the change.

NNECo considered the effect of a change on design margins and the design changes received the appropriate level of engineering and management review during the design phase and prior to implementation.

MILLSTONE UNIT 2 ICAVP PP-01 PROJECT PROCEDURES

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NNECo considered the efTect of a change on pre-operational, startup, or system baseline e

acceptance test results.

Design changes were accomplished in accordance with approved procalures.

Design changes are accurately re0ccted in operating, maintenance, and test procedures.

NOTE Procalures will be revinved in detail to verify that correct licensing and design bases infonnation have been incorporated into the procedures and that modi 6 cations, corrective actions, and changes in system licensing bases have not invalidated preoperational and/or startup acceptance.

Proposed design changes, subsequently canceled, were not replaced by proccdural changes that imposed excessive burdens on plant operators.

4.2.1.3 As documents are rniewed, prepare walkdown checklists detailing items needing additional infonnation or clari6 cation.

Action Outag A list ofinspection walkdown requirements A record of documents rniewed and their disposition NOTE:

T rical design input requirements to be used in evaluating system documents are listed in Appendix C.

3 Typical design rniew questions to be usod in evaluating system documents are listed in Appendix D.

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4.2.2 Plant Walkdowns Resources System Lead System Team Members Attion 4.2.2.1 Develop Walkdown Package. Typical contents will be:

System components and/or area to inspect during the walkdown Specific modification package elements to inspect e

System specific Corrective Actions identified by the Millstone Unit 2 Configuration e

Management Program to inspect and evaluate Measurements / observations to make e

System procedures to walkthrough e

Location of components or structures Marked up drawings showing walkdown requirements e

4.2.2.2 Obtain clearance and/or access pennits. Examples:

Radiation work permit ScafTolding Specialoperational requirements l

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4.2.2.3 Conduct the walkdown, emphasizing:

NOTE The system vertical slice reviews will be focused on licensing and design bases requirements and will utilize appropriate level documentation (drawings, calculations, design documents, etc.) to the inspection detail necessary to verify and validate conformance to the requirements.

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Control of operational procedures, maintenance procedures, test and surveillance procedures, e

and control of the plant simulator configuration.

Configuration control consistency with the licensing bases at the level of detail contained in 13 g

piping and instnimentation diagrams (P&lDs) or system flow diagrams, piping isometric drawings, electrical single-line diagrams, and emergency, abnonnal, and normal operating procedures.

Engineering design and configuration control processes; Verification of current, as-modified plant conditions against design basis and licensing basis e

documentation; Verification that design and licensing bases requirements have been and are being translated e

into operating procedures and maintenance and test procedures; Verification of system perfonnance through review of specific test records and/or obsen ation e

of selected testing of particular systems; and Review of proposed and impicmented corrective actions for Millstone Unit 2 identified design e

deficiencies.

Action Output Completed Walkdown Package

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MILLSTONE UNIT 2 ICAVP PP-01 PROJECT PROCEDURES TITLE:

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4.2.3 Conduct Structured Data Gatherine Resouren SYSR Team Members SYSR System leader Action 4.2.3.1 Prepare a list of specine infomation to be obtained based on a need for clari0 cation, infomation that the SVSR team can not 6nd, or further investigation into answering a working question. This will help ensure that the information requirement is focused.

4.2.3.2 Identify the organization orjob function that may be able to supply the specinc O*

information. Arrange for a data gathering conference to obtain nooded infomation.

NOTE All data gathering conferences will be conducted in accordance with the Communication Plan (PLN-02).

Action Output Guidance and clari0 cations regarding NNECo positions or decisions Additionalinfomation 4.3 INSPECTION ASSESSMENT AND REPORT Resources Deputy Project Director SVSR Group Leader SVSR System Lead SVSR Team Members l

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Action 4.3.1 Collect and assess the results of the inspection preparation and system inspections from each of the inspection teams.

4.3.2 Prepare a draft report of the SVSR activities, results, and conclusions. The report is to consist of, as a minimum:

input to an executive summary, e

A summary description of the methods used, e

A summary of what was reviewed, Results of the vertical slice reviews, and e

The conclusions that can be drawn from the results of the reviews.

The conclusions are to include a determination of whether; 1he current configuration accurately reflects the licensing-bases, including the UFSAR, at the level of detail contained in piping and instrumentation diagrams (P&lDs) electrical single-line diagrams, and plant operating procedures.

Calculations and analyses were performed using recognized and acceptable analytical 4 hods and that assumptions made in calculations or analysis supporting changes are

.scally sound.

1he results of calculatior.3 or analysis supporting the unmodified portions of the original cofiguration and design changes are reasonable (based on engineering judgment) for the scope of the change.

NNiiCo considered the etTect of a change on design nwgins and that the design changes received the appropriate level of engineering and management review during the desip phase and prior to implementation.

NNECo considered the etTect of a change on pre-operational, startup, or system baseline acceptance test results.

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Design changes are accurately reflected in operating, rnaintenance, and test procedures, as well as in training materials.

Proposed design changes, subsequently cancelcd, were not replaced by procedural changes that imposed excessive burdens on plant operators.

4.3.3 Support internal ICAVhevicws of the drafl report as necessary.

4.3.4 Resolve comments and finalize tne report for issue.

Action Output j

Final Report Project backup documentation i

4.4 TEAM MEETINGS / REVIEWS v

During the SYSR, meetings and status reviews will be held periodically. He following guidelines shall govern the regularly scheduled meetings.

Meetings of the system teams shall be held daily.

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He daily meetings shall be chaired by the System Lead and shall cover inspection entus, progress, working questions under review, and discrepancies to date.

Combined Team meetings shall be held at least weekly.

The weekly meetings shall be chaired by the SVSR Group Lead or the Deputy Project Director and shall cover the overall progress of the inspection including working questions under review and discrepancies to date in all areas.

4.5 SYSTE!W ASSESSMENT Systera Assgssment As Working Questions are identified by the SVSR Team Members, they are to be documented for further investigation.

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Follow up by SVSR Team Members will determine that eithe; l) upon obtaining further information, no question exists, o-2) it is an identified discrepancy with a documented basis.

Discrepancies are evaluated per Project Procedure PP-07. Each discrepancy fonvarded for PP-07 renew will be provided with a complete description, including all pertinent background information.

5.0 BEFERENCES NRC Inspection Procedure 93801, Safety System Functional laspection (SSFI)

NRC Inspection Manual Chapter 0350, " Staff Guidelines for Restart Approval" NRC Inspection Manual Chapter 2535, " Design Verification Progrants" A

Millstone Unit 3 Restart Assessment Plan NRC Confirmatory Order to Northew Utilities Energy Company dated August 14,1997 l

NRC ICAVP Oversight Guidelir.: Document NRC ICAVP Oversight inspection Plan 4

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APPENDIX A SYSTEM SEl,ECTION CRITERIA Introductio The Parsons Power Group criteria for selecting systems for vertical slice review has been developed to provide an additiceal selection process to that criteria described by the NRC in the ICAVP Oversight inspection Plan.

O The ICAVP Oversight Plan (page 5) stipulates that the NRC will select the systems to be inspected during

\\J Tier I and that they will consider,in addition to the contractors proposed criteria, NRC criteria based on; I, risk significance,

2. design and operating characteristics,
3. the number and complexity of changes to the system, and
4. the number of previously identified deficiencies or operating problems ne focus of the ICAVP, the Millstone Unit 2 Configuration Management Corrective Action Plan, includes in its scope the Millstone Unit 2 systems categorized by NNECo as either Group 1 (safety-related and risk significant) and Group 2 (safety-related m risk significant). Using the Group 1 and 2 systems as a starting point, the selection criteria will apply quantitative selectice criteria to determine which of the systems in these two groups are likely candidates for the vertical slice inspection.

The initial systems to be reviewed will be selected from those systems categorized as Group 1 or Group 2 using criteria developed as part of maintenance rule implementation (10CFR50.65). Also, it is assumed that the utilization of the selection criteria will be done by the NRC.

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System Selection Criteria Factors have been developed on specific system attributes that, when measured and ranked, proside the basis for determining the Tier I candidates. Dese attributes are measured through an intensive examination of system operational, configuration and regulatoy history Attributes Factor #1-Risk Significance identify those sysa ms that have a high ks el of risk significance base on PRA insights as determined by a panel ofindividuals familiar with Millstone Unit 2 PRA. Cut sets (accident sequence failure combinations) with a high level of risk significance are examined to identify specific systems /compents. Based on the risk significance of systems and/or components, a qualitative risk factor is developed for final determination of system ranking by the expert panel.

Factor #2-Number of Modification Events (Fws)

For purpose of the ICAVP selection criteria, a modification is defined as any change to any aspect of the system (components, procedures, design, calculations, etc.) that will alter or revise in any way 1) systems design bases; 2) system maintenance; 3) system controls; and 4) system operation.

Fms is developed by reviewing all documentation for each Group I and Group 2 system and developing a matrix of system modifications and the count of modification events. Modification events are changes and/or revisions to design bases, maintenance, controls and/or operations of the system made during the modification. The modification events for each system are then summed to arrive at the total number. The concluding step is to compile system rankings as a function of the number of modifications events per system.

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REVISION: 3 DATE: 10/02/97 PAGE 22 OF 26 Factor #3 - Number of Major Modifications / Interfaces (Fmu) ne selection criteria defines a major modification as a design change involving internal interfaces between major discipline areas and'or external imerfaces with one of more of the following: the NSSS vendor, component vendors, or an engineering senice organization (s).

Fxa is developed in matrix form by reviewing all documentation for the systems and noting the number ofinterfaces involved in the various modifications for each system. He total r. umber of interfaces per modification and system will be derived for the total factor pr system. Ac systems will be ranked accordingly.

Factor #4 - Plant System IIistory (Fes)

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Licensee Event Reports (LERs) provide an extensive record of system problems to be used for system selection. LERs provide information on both the system and the system components. For purposes of system selection, an LER will be counted as applicable ifit relates in anyway, to: 1) systems design bases; 2) system maintenance; 3) system controls; and 4) system operation. Frs is the summed LERS for each system.

Factor #5 -Industry System IIistory (F s) i Input for system selection for Factor #5 will be based on industry data on system and equipment failure rates. He data input will be derived on a system by system basis from the Nuclear Plant Reliability Data System and the CE Owners Group, ne data and its collection will be similar to Factor #4 but on an industry wide, NSSS specific basis. The F si will be summed failure on a system by system basis.

An Expert Panel will make the final determmation of the relative rankmg of the systems based on the V

results of the system selection survey, system boundaries, industry experience, and their own knowledge of the systems and the requirements of the ICAVP.

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APPENDIX B TYPICAL DOCUMENT REKW/SAMPl,E TOPICS FOR INSPECTION

1. System Design Review - Fluid and Material llandling Systems
2. Fluid System Diagram; System Description; for complex systems, Logie and Loop Diagrams 3.

System Design Review - Structural 4.

Bracing Arrangement and Stability Analysis

5. System Design Review - Electrical System 6.

One-line Diagram and System Description

7. System Design Review - Infornution Processing / Control Philosophy 8.

Description of Control Philosophy 9.

System Design Review - Facilities Design Systems

10. IIVAC, Fire Protection, and Architectural
11. Layout Design Review
12. Layout Drawing, Layout Description, Code Reviews, and Life Safety Analysis
13. Site Arrangement Review
14. Ultimate Site Development Plan
15. Cooling Water Source
16. Environmental Constraints
17. Common or Shared Facilities
18. Railroad Access
19. Foundation Type Review
20. Geotechnical Limitations
21. Soil Bearing Capacity
22. Water Table Considerations
23. Alternative Methods
24. Transmission and Distribution Design Review
25. Modification Packages

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Al-PENDIX C TYPICAL DESIGN INPUT REQUIREMENTS

1. Scope / Basic functions of structure, system or component Performance requirements, input senices (air, electricity) as well as outputs (capacity, rating) 2.
3. Codes Standards, and regulatory requirements including applicable issue end/or addenda 4.

Design Conditions such as temperature, pressure, fluid, chemistry and volage 5, Loads such as seismic, wind, thermal and d>mamic 6.

Environmental conditions anticipated, such as pressure, temperature, humidity, corrosiveness, site elevation, wind direction, nuclear radiation, electromagnetic radiation, and duration of exposure including 10CFR50.49 application

7. Interface requirements and constructability including definition of the functional and physical interfaces including structures, systems, and components
8. Material requirements such items as compatibility, electrical insulation properties, protective coating, and corrosion resistance
9. Mechanical requirements such as vibration, stress, shock and reaction forces
10. Structural requirements covering such items as equipment foundations and pipe supporte
11. Hydraulic requirements such as NPSH, allowable pressure drops, and fluid velocities
12. Chemistry requirements such as provisions for sampling and limitations on water chemistry
13. Electrical requirements such as source of power, voltage, raceway requirements, electrical insulation, motor requirements, load / voltage studies and EDG ioading
14. Layout and arrangement quirements
15. Operational requirements under various conditions such as plant start-up, normal plant operation, plant shutdown, plant emergency operation, special or infrequent operation, and system abnormal or emergency operation
16. Instrumentation a,d control requirements including indicating instruments, controls and alarms required for operation, testing and maintenance.

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17. Access and administrative control requirements required for plant security
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18. Redundancy, diversity, and separation requirements
19. Failure efTects requirements including of those events which they must withstand

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20. Test requirements including pre-operational and subsequent periodic in-plant and the condition under which thy must operate
21. Accessibility, maintenance, repair and in-service inspection requirements
22. Personnel requirements and limitations
23. Transportability requirements such as size and shippirS weight
24. Fire protection or fire resistance requirements
25. liandling, storage, cleaning and shipping requirements
26. Other requirements to prevent undue risk to the health and safety of public
27. Materials, processes, parts, and equipment suitab e for application
28. Safety requirements for preventing personnel inju;y
29. Quality and quality assurance requirements
30. Reliability requirements including their interactions, which may impair safety

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31. Interface requirements between plant equipment and operation and maintenance personnel

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32. Requirements for criticality control and accountability of special nuclear materials
33. Special ALARA considerations
34. Special human factors considerations
35. High Energy Line Breaks are affected
36. Flooding
37. Missiles 38.10CFR50 Appendix R, including Safe Shutdmvn Analysis l
39. Seismic Category 11 over 1
40. SpecialliVAC requirements
41. Station Blackout Analysis
42. Post Accident Monitoring Requirements
43. OTiiER requirements, as necessary

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APPENDIX D TYPICAL, DESIGN REVIEW OUESTIONS

1. Were the inputs correctly selected and incorporated into design?
2. Are assumptions necessary to perform the design activity adequately described and reasonable?

Where necessary, are the assumptions identified for subsequent reverification when the detailed design activities are completed?

3. Are the appropriate quality and quality assurance requirements specified?
4. Are the appropriate codes, standards, and regulatory requirements specified?
5. llave applicable operating and construction experiences been considered?
6. llave the design interface requirements been satisfied?
7. Was an appropriate design method used?

8.

Is the output reasonable compared to the inputs?

I O) 9.

Are the specified parts, equipment, and processes suitable for the required application?

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10. Are the specified materials compatible with each other and the design environmental conditions I

to which the material will be exposed?

I1.11 ave adequate maintenance features and requirements been specified?

12. Are accessibility and other provisions adequate for performance of needed maintenance and repair?

13.11ad adequate accessibility been provided to perform the in-senice inspection expected to be required during the plant life?

14. lias the design properly considered radiation exposure?
15. Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?
16. Have adequate pre-operational and subsequent periodical test requirements been appropriately specified?
17. Are adequate handling, storage, cleaning, and shipping requirements specified? Are adequate identification requirements specified?
18. Are requirements for record preparation, review, approval, retention, etc., adequately 73

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